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Sample records for rcra disposal units

  1. Detailed analysis of a RCRA landfill for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-04-01

    The purpose of this detailed analysis is to provide a preliminary compilation of data, information, and estimated costs associated with a RCRA landfill alternative for UNC Disposal Site. This is in response to Environmental Protection Agency (EPA) comment No. 6 from their review of a open-quotes Feasibility Study for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee.close quotes

  2. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-07-19

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  3. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    International Nuclear Information System (INIS)

    2010-01-01

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  4. Resource Conservation and Recovery Act (RCRA) contingency plan for hazardous waste treatment, storage, and disposal units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1994-08-01

    The Y-12 RCRA Contingency Plan will be continually reviewed and revised if any of the following occur: the facility permit is revised, the plan is inadequate in an emergency, the procedures can be improved, the operations of the facility change in a way that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Management Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste treatment, storage, or disposal units. The 90-day accumulation areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  5. Resource Conservation and Recovery Act (RCRA) general contingency plan for hazardous waste treatment, storage, and disposal units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    Skaggs, B.E.

    1993-11-01

    The Y-12 RCRA Contingency Plan will be continually reviewed and revised if any of the following occur: the facility permit is revised, the plan is inadequate in an emergency, the procedures herein can be improved, the operations of the facility change in a way that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Management Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste treatment, storage, or disposal units. The 90-day accumulation areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  6. Obtaining variances from the treatment standards of the RCRA Land Disposal Restrictions

    International Nuclear Information System (INIS)

    1990-05-01

    The Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs) [40 CFR 268] impose specific requirements for treatment of RCRA hazardous wastes prior to disposal. Before the LDRs, many hazardous wastes could be land disposed at an appropriately designed and permitted facility without undergoing treatment. Thus, the LDRs constitute a major change in the regulations governing hazardous waste. EPA does not regulate the radioactive component of radioactive mixed waste (RMW). However, the hazardous waste component of an RMW is subject to RCRA LDR regulations. DOE facilities that manage hazardous wastes (including radioactive mixed wastes) may have to alter their waste-management practices to comply with the regulations. The purpose of this document is to aid DOE facilities and operations offices in determining (1) whether a variance from the treatment standard should be sought and (2) which type (treatability or equivalency) of petition is appropriate. The document also guides the user in preparing the petition. It shall be noted that the primary responsibility for the development of the treatability petition lies with the generator of the waste. 2 figs., 1 tab

  7. RCRA Treatment, Disposal, and Storage Site Boundaries in Louisiana, Geographic NAD83, EPA (2002) [RCRA_TSD_LA_poly_EPA_2002)

    Data.gov (United States)

    Louisiana Geographic Information Center — This is a shapefile of RCRA Treatment, Storage, and Disposal facility boundaries developed by PRC Environmental Management, Inc (PRC) per a Work Assignment from the...

  8. ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

    International Nuclear Information System (INIS)

    Romano, Stephen; Welling, Steven; Bell, Simon

    2003-01-01

    The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

  9. RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

  10. RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

  11. Costs of RCRA corrective action: Interim report

    International Nuclear Information System (INIS)

    Tonn, B.; Russell, M.; Hwang Ho-Ling; Goeltz, R.; Warren, J.

    1991-09-01

    This report estimates the cost of the corrective action provisions of the Resource Conservation and Recovery Act (RCRA) for all non-federal facilities in the United States. RCRA is the federal law which regulates the treatment, storage, disposal, and recovery of hazardous waste. The 1984 amendment to RCRA, known as the Hazardous and Solid Waste Amendments, stipulates that facilities that treat, store or dispose of hazardous wastes (TSDs) must remediate situations where hazardous wastes have escaped into the environment from their solid waste management units (SWMUs). The US Environmental Protection Agency (USEPA 1990a), among others, believes that the costs of RCRA corrective action could rival the costs of SUPERFUND. Evaluated herein are costs associated with actual remedial actions. The remedial action cost estimating program developed by CH2M Hill is known as the Cost of Remedial Action Model (CORA). It provides cost estimates, in 1987 dollars, by technology used to remediate hazardous waste sites. Rules were developed to categorize each SWMU in the RTI databases by the kinds of technologies that would be used to remediate them. Results were then run through CORA using various assumptions for variable values that could not be drawn from the RTI databases and that did not have CORA supplied default values. Cost estimates were developed under several scenarios. The base case assumes a TSD and SWMU universe equal to that captured in the RTI databases, a point of compliance at the SWMU boundary with no ability to shift wastes from SWMU to SWMU, and a best-as-practical clean-up to health-based standards. 11 refs., 12 figs., 12 tabs

  12. RCRA Facility Investigation/Remedial Investigation Report for Gunsite 720 Rubble Pit Unit (631-16G) - March 1996

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1996-03-01

    Gunsite 720 Rubble Pit Unit is located on the west side of SRS. In the early to mid 1980`s, while work was being performed in this area, nine empty, partially buried drums, labeled `du Pont Freon 11`, were found. As a result, Gunsite 720 became one of the original waste units specified in the SRS RCRA Facility Assessment (RFA). The drums were excavated on July 30, 1987 and placed on a pallet at the unit. Both the drums and pallet were removed and disposed of in October 1989. The area around the drums was screened during the excavation and the liquid (rainwater) that collected in the excavated drums was sampled prior to disposal. No evidence of hazardous materials was found. Based on the review of the analytical data and screening techniques used to evaluate all the chemicals of potential concern at Gunsite 720 Rubble Pit Unit, it is recommended that no further remedial action be performed at this unit.

  13. RCRA Facility Investigation/Remedial Investigation Report for Gunsite 720 Rubble Pit Unit (631-16G) - March 1996

    International Nuclear Information System (INIS)

    Palmer, E.

    1996-03-01

    Gunsite 720 Rubble Pit Unit is located on the west side of SRS. In the early to mid 1980's, while work was being performed in this area, nine empty, partially buried drums, labeled 'du Pont Freon 11', were found. As a result, Gunsite 720 became one of the original waste units specified in the SRS RCRA Facility Assessment (RFA). The drums were excavated on July 30, 1987 and placed on a pallet at the unit. Both the drums and pallet were removed and disposed of in October 1989. The area around the drums was screened during the excavation and the liquid (rainwater) that collected in the excavated drums was sampled prior to disposal. No evidence of hazardous materials was found. Based on the review of the analytical data and screening techniques used to evaluate all the chemicals of potential concern at Gunsite 720 Rubble Pit Unit, it is recommended that no further remedial action be performed at this unit

  14. RCRA corrective action program guide (Interim)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The US Department of Energy (DOE) is responsible for compliance with an increasingly complex spectrum of environmental regulations. One of the most complex programs is the corrective action program proposed by the US Environmental Protection Agency (EPA) under the authority of the Resource Conservation and Recovery Act (RCRA) as amended by the Hazardous and Solid Waste Amendments (HSWA). The proposed regulations were published on July 27, 1990. The proposed Subpart S rule creates a comprehensive program for investigating and remediating releases of hazardous wastes and hazardous waste constituents from solid waste management units (SWMUs) at facilities permitted to treat, store, or dispose of hazardous wastes. This proposed rule directly impacts many DOE facilities which conduct such activities. This guidance document explains the entire RCRA Corrective Action process as outlined by the proposed Subpart S rule, and provides guidance intended to assist those persons responsible for implementing RCRA Corrective Action at DOE facilities.

  15. The WIPP RCRA Part B permit application for TRU mixed waste disposal

    International Nuclear Information System (INIS)

    Johnson, J.E.

    1995-01-01

    In August 1993, the New Mexico Environment Department (NMED) issued a draft permit for the Waste Isolation Pilot Plant (WIPP) to begin experiments with transuranic (TRU) mixed waste. Subsequently, the Department of Energy (DOE) decided to cancel the on-site test program, opting instead for laboratory testing. The Secretary of the NMED withdrew the draft permit in 1994, ordering the State's Hazardous and Radioactive Waste Bureau to work with the DOE on submittal of a revised permit application. Revision 5 of the WIPP's Resource Conservation and Recovery Act (RCRA) Part B Permit Application was submitted to the NMED in May 1995, focusing on disposal of 175,600 m 3 of TRU mixed waste over a 25 year span plus ten years for closure. A key portion of the application, the Waste Analysis Plan, shifted from requirements to characterize a relatively small volume of TRU mixed waste for on-site experiments, to describing a complete program that would apply to all DOE TRU waste generating facilities and meet the appropriate RCRA regulations. Waste characterization will be conducted on a waste stream basis, fitting into three broad categories: (1) homogeneous solids, (2) soil/gravel, and (3) debris wastes. Techniques used include radiography, visually examining waste from opened containers, radioassay, headspace gas sampling, physical sampling and analysis of homogeneous wastes, and review of documented acceptable knowledge. Acceptable knowledge of the original organics and metals used, and the operations that generated these waste streams is sufficient in most cases to determine if the waste has toxicity characteristics, hazardous constituents, polychlorinated biphenyls (PBCs), or RCRA regulated metals

  16. Closure Report for Corrective Action Unit 110: Areas 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    J. L. Smith

    2001-08-01

    This Closure Report (CR) has been prepared for the Area 3 Radioactive Waste Management Site (RWMS) U-3ax/bl Disposal Unit Corrective Action Unit (CAU) 110 in accordance with the reissued (November 2000) Resource Conservation and Recovery Act (RCRA) Part B operational permit NEV HW009 (Nevada Division of Environmental Protection [NDEP], 2000) and the Federal Facility and Consent Order (FFACO) (NDEP et al., 1996). CAU 110 consists of one Corrective Action Site 03-23-04, described as the U-3ax/bl Subsidence Crater. Certifications of closure are located in Appendix A. The U-3ax/bl is a historic disposal unit within the Area 3 RWMS located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit was closed under the RCRA, as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (m{sup 3}) (8.12 x 10{sup 6} cubic feet [ft{sup 3}]) of waste. NTS atmospheric nuclear device testing generated approximately 95% of the total waste volume disposed of in U-3ax/bl; 80% of the total volume was generated from the Waste Consolidation Project. Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is normally in a state of moisture deficit.

  17. Corrective action management unit application for the Environmental Restoration Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ``Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.`` The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ``package`` for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package.

  18. Corrective action management unit application for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ''Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.'' The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ''package'' for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package

  19. Planning for closures of hazardous waste land disposal units at the Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    Welch, S.H.; Kelly, B.A.; DeLozier, M.F.P.; Manrod, W.E.

    1988-01-01

    Eight hazardous waste land disposal units at the Oak Ridge Y-12 Plant are being closed in accordance with the Resource Conservation and Recovery Act (RCRA) under an integrated multi-year program. The units, some of which date back to the early 1950s and include five surface impoundments, two landfills and a land treatment unit, have been used for the management of a variety of types of hazardous wastes. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. The units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. Closure of all eight units must be initiated by November 8, 1988. Funding for the eight closures is being provided by a new Department of Energy budget category, the environmental Restoration Budget Category (ERBC), which is intended to allow for a more rapid response to environmental problems and regulatory requirements. A major project, Closure and Post-Closure Activities (CAPCA) has been identified for ERBC funding to close the land disposal units in accordance with RCRA requirements. Establishing the project scope has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA project include risk assessments and the preparation of an integrated project schedule

  20. RCRA Part A permit characterization plan for the U-2bu subsidence crater. Revision 1

    International Nuclear Information System (INIS)

    1998-04-01

    This plan presents the characterization strategy for Corrective Action Unit (CAU) 109, U-2bu Subsidence Crater (referred to as U-2bu) in Area 2 at the Nevada Test Site (NTS). The objective of the planned activities is to obtain sufficient characterization data for the crater soils and observed wastes under the conditions of the current Resource Conservation and Recovery Act (RCRA) Part A permit. The scope of the characterization plan includes collecting surface and subsurface soil samples with hand augers and for the purpose of site characterization. The sampling strategy is to characterize the study area soils and look for RCRA constituents. Observable waste soils and surrounding crater soils will be analyzed and evaluated according to RCRA closure criteria. Because of the status of the crater a RCRA Part A permit site, acquired radionuclide analyses will only be evaluated in regards to the health and safety of site workers and the disposition of wastes generated during site characterization. The U-2bu Subsidence Crater was created in 1971 by a Lawrence Livermore National Laboratory underground nuclear test, event name Miniata, and was used as a land-disposal unit for radioactive and hazardous waste from 1973 to 1988

  1. Hanford Site Waste Managements Units reports

    International Nuclear Information System (INIS)

    1992-01-01

    The Hanford Site Waste Management Units Report (HSWMUR) was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments (HSWA) of the 1984 United States Code (USC 1984). This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in this report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of this report, the listing of sites is more extensive than required by Section 3004(u) of HSWA. The information in this report is extracted from the Waste Information Data System (WIDS). The WIDS provides additional information concerning the waste management units contained in this report and is maintained current with changes to these units. This report is updated annually if determined necessary per the Hanford Federal Facility Agreement and Consent Order Order (commonly referred to as the Tri-Party Agreement, Ecology et al. 1990). This report identifies 1,414 waste management units. Of these, 1,015 units are identified as solid waste management units (SWMU), and 342 are RCRA treatment, storage, and disposal units. The remaining 399 are comprised mainly of one-time spills to the environment, sanitary waste disposal facilities (i.e., septic tanks), and surplus facilities awaiting decontamination and decommissioning

  2. Interpreting the SARA and RCRA training requirements

    International Nuclear Information System (INIS)

    Moreland, W.M.; Wells, S.M.

    1987-01-01

    The Resource Conservation and Recovery Act (RCRA) and the Superfund Amendments and Reauthorization Act (SARA) promulgated by the EPA (RCRA) and the OSHA (SARA) require hazardous materials training for all individuals working with hazardous materials. Facilities that are involved in the generation, storage, treatment, transportation, or disposal/removal of hazardous materials/waste must comply with all relevant training regulations. Using the guidelines contained in the RCRA and SARA regulations, decisions must be made to determine: the type of regulatory requirement based on facility function (i.e., whether the facility is a RCRA or CERCLA facility). The type of training required for specific categories of workers (e.g. managers, supervisors, or general site workers). The level of training needed for each category of worker. This presentation outlines how the Environmental Compliance and Health Protection Technical Resources and Training Group, working with waste operations personnel, establishes specific training requirements

  3. The Hazardous Waste/Mixed Waste Disposal Facility

    International Nuclear Information System (INIS)

    Bailey, L.L.

    1991-01-01

    The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996

  4. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 2, Battery recycling and disposal

    Energy Technology Data Exchange (ETDEWEB)

    Corbus, D

    1992-09-01

    Recycling and disposal of spent sodium-sulfur (Na/S) batteries are important issues that must be addressed as part of the commercialization process of Na/S battery-powered electric vehicles. The use of Na/S batteries in electric vehicles will result in significant environmental benefits, and the disposal of spent batteries should not detract from those benefits. In the United States, waste disposal is regulated under the Resource Conservation and Recovery Act (RCRA). Understanding these regulations will help in selecting recycling and disposal processes for Na/S batteries that are environmentally acceptable and cost effective. Treatment processes for spent Na/S battery wastes are in the beginning stages of development, so a final evaluation of the impact of RCRA regulations on these treatment processes is not possible. The objectives of tills report on battery recycling and disposal are as follows: Provide an overview of RCRA regulations and requirements as they apply to Na/S battery recycling and disposal so that battery developers can understand what is required of them to comply with these regulations; Analyze existing RCRA regulations for recycling and disposal and anticipated trends in these regulations and perform a preliminary regulatory analysis for potential battery disposal and recycling processes. This report assumes that long-term Na/S battery disposal processes will be capable of handling large quantities of spent batteries. The term disposal includes treatment processes that may incorporate recycling of battery constituents. The environmental regulations analyzed in this report are limited to US regulations. This report gives an overview of RCRA and discusses RCRA regulations governing Na/S battery disposal and a preliminary regulatory analysis for Na/S battery disposal.

  5. Hanford Site Waste Management Units Report

    International Nuclear Information System (INIS)

    1991-01-01

    This Hanford Site Waste Management Units Report (HSWMUR) was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments (HSWA) of the 1984 United States Code (USC). The report provides a comprehensive inventory of all types of waste management units at the Hanford Site and consists of waste disposal units, including (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structure, (5) RCRA treatment and storage units, and (6) other storage areas. Because of the comprehensive nature of this report, the listing of sites is more extensive than required by Section 3004(u) of HSWA. In support of the Hanford RCRA permit, a field was added to designate whether the waste management unit is a solid waste management unit (SWMU). As SWMUs are identified, they will added to the Hanford Waste Information Data System (WIDS), which is the database supporting this report, and added to the report at its next annual update. A quality review of the WIDS was conducted this past year. The review included checking all data against their reference and making appropriate changes, updating the data elements using the most recent references, marking duplicate units for deletion, and addition additional information. 6 refs

  6. Hanford Site Waste Management Units Report

    International Nuclear Information System (INIS)

    1991-01-01

    This Hanford Site Waste Management Units Report (HSWMUR) was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments (HSWA) of the 1984 United States Code (USC). The report provides a comprehensive inventory of all types of waste management units at the Hanford Site and consists of waste disposal units, including (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment and storage units, and (6) other storage areas. Because of the comprehensive nature of this report, the listing of sites is more extensive than required by Section 3004(u) of HSWA. In support of the Hanford RCRA permit, a field was added to designate whether the waste management unit is a solid waste management unit (SWMU). As SWMUs are identified, they will added to the Hanford Waste Information Data System (WIDS), which is the database supporting this report, and added to the report at its next annual update. A quality review of the WIDS was conducted this past year. The review included checking all data against their reference and making appropriate changes, updating the data elements using the most recent references, marking duplicate units for deletion, and adding additional information. 6 refs

  7. Ground-water monitoring under RCRA

    International Nuclear Information System (INIS)

    Coalgate, J.

    1993-11-01

    In developing a regulatory strategy for the disposal of hazardous waste under the Resource Conservation and Recovery Act (RCRA), protection of ground-water resources was the primary goal of the Environmental Protection Agency (EPA). EPA's ground-water protection strategy seeks to minimize the potential for hazardous wastes and hazardous constituents in waste placed in land disposel units to migrate into the environment. This is achieved through liquids management (limiting the placement of liquid wastes in or on the land, requiring the use of liners beneath waste, installing leachate collection systems and run-on and run-off controls, and covering wastes at closure). Ground-water monitoring serves to detect any failure in EPA's liquids management strategy so that ground-water contamination can be detected and addressed as soon as possible

  8. Resource conversation and recovery act (RCRA) Contingency Plan for interim status or permitted units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1992-08-01

    The official mission of the Y-12 Plant is to serve as a manufacturing technology center for key processes such that capabilities are maintained for safe, secure, reliable, and survivable nuclear weapons systems and other applications of national importance. The Y-12 RCRA Contingency Plan will be reviewed and revised if necessary if the facility RCRA operating permits are revised, the plan is inadequate in an emergency, the procedures herein can be improved, the facility's operations change in a manner that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Preparedness Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste interim status or permitted treatment, storage, or disposal facilities. The 90-day storage areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  9. NPL deletion policy for RCRA-regulated TSD facilities finalized

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Under a new policy published by EPA on March 20, 1995, certain sites may be deleted from the National Priorities List (NPL) and deferred to RCRA corrective action. To be deleted from the NPL, a site must (1) be regulated under RCRA as a treatment, storage, or disposal (TSD) facility and (2) meet the four criteria specified by EPA. The new NPL deletion policy, which does not pertain to federal TSD facilities, became effective on April 19, 1995. 1 tab

  10. Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money

    International Nuclear Information System (INIS)

    Brill, Angie; Boles, Roger; Byars, Woody

    2003-01-01

    The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude

  11. RCRA corrective action determination of no further action

    International Nuclear Information System (INIS)

    1996-06-01

    On July 27, 1990, the U.S. Environmental Protection Agency (EPA) proposed a regulatory framework (55 FR 30798) for responding to releases of hazardous waste and hazardous constituents from solid waste management units (SWMUs) at facilities seeking permits or permitted under the Resource Conservation and Recovery Act (RCRA). The proposed rule, 'Corrective Action for Solid Waste Management Units at Hazardous Waste Facilities', would create a new Subpart S under the 40 CFR 264 regulations, and outlines requirements for conducting RCRA Facility Investigations, evaluating potential remedies, and selecting and implementing remedies (i.e., corrective measures) at RCRA facilities. EPA anticipates instances where releases or suspected releases of hazardous wastes or constituents from SWMUs identified in a RCRA Facility Assessment, and subsequently addressed as part of required RCRA Facility Investigations, will be found to be non-existent or non-threatening to human health or the environment. Such releases may require no further action. For such situations, EPA proposed a mechanism for making a determination that no further corrective action is needed. This mechanism is known as a Determination of No Further Action (DNFA) (55 FR 30875). This information Brief describes what a DNFA is and discusses the mechanism for making a DNFA. This is one of a series of Information Briefs on RCRA corrective action

  12. RCRA facility stabilization initiative

    International Nuclear Information System (INIS)

    1995-02-01

    The RCRA Facility Stabilization Initiative was developed as a means of implementing the Corrective Action Program's management goals recommended by the RIS for stabilizing actual or imminent releases from solid waste management units that threaten human health and the environment. The overall goal of stabilization is to, as situations warrant, control or abate threats to human health and/or the environment from releases at RCRA facilities, and/or to prevent or minimize the further spread of contamination while long-term remedies are pursued. The Stabilization initiative is a management philosophy and should not be confused with stabilization technologies

  13. Resource Conservation and Recovery Act (RCRA) Part B permit application for tank storage units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1994-05-01

    In compliance with the Resource Conservation and Recovery Act (RCRA), this report discusses information relating to permit applications for three tank storage units at Y-12. The storage units are: Building 9811-1 RCRA Tank Storage Unit (OD-7); Waste Oil/Solvent Storage Unit (OD-9); and Liquid Organic Solvent Storage Unit (OD-10). Numerous sections discuss the following: Facility description; waste characteristics; process information; groundwater monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plan, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification. Sixteen appendices contain such items as maps, waste analyses and forms, inspection logs, equipment identification, etc

  14. Achieving RCRA compliance in DOE defense waste management operations

    International Nuclear Information System (INIS)

    Frankhauser, W.A.; Shepard, M.D.

    1989-01-01

    The U.S. Department of Energy (DOE) generates significant volumes of radioactive mixed waste (RMW) through its defense-related activities. Defense RMW is co-regulated by DOE and the U.S. Environmental Protection Agency/State agencies in accordance with requirements of the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). This paper highlights some of the problems encountered in co-regulation and discusses achievements of the defense waste management program in integrating RCRA requirements into RMW operations. Defense waste sites are planning facility modifications and major new construction projects to develop treatment, storage and disposal capacity for existing RMW inventories and projected needs

  15. 200-BP-11 operable unit and 216-B-3 main pond work/closure plan, Hanford Site, Richland, Washington. Volume 1: Field investigation and sampling strategy

    International Nuclear Information System (INIS)

    1994-09-01

    This document coordinates a Resource Conservation and Recovery Act (RCRA) past-practice work plan for the 200-BP-11 Operable Unit and a RCRA closure/postclosure plan for the 216-B-3 Main Pond and 216-B-3-3 Ditch [treatment, storage, and/or disposal (TSD) unit]. Both RCRA TSD and past-practice waste management units are contained within the 200-BP-11 Operable Unit. The 200-BP-11 Operable Unit is a source operable unit located on the east side of the B Plant Source Aggregate Area in the 200 East Area of the Hanford Site. The operable unit lies just east of the 200 East Area perimeter fence and encompass approximately 476 hectares (1,175 acres). Source operable units include waste management units that are potential sources of radioactive and/or hazardous substance contamination. Source waste management units are categorized in the Hanford Federal Facility Agreement and Consent Order as either RCRA TSD, RCRA past-practice, or Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) past-practice. As listed below and in the Tri-Party Agreement, the 200-BP-11 Operable Unit contains five RCRA past-practice and five RCRA TSD waste management units. Additionally, for RCRA TSD permitting purposes, the RCRA TSD waste management units are subdivided into two RCRA TSD units

  16. Hanford Site waste management units report

    International Nuclear Information System (INIS)

    1993-04-01

    The Hanford Site Waste Management Units Report was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments of the 1984. This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in the report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of the units report, the list of units is more extensive than required by Section 3004(u) of Hazardous and Solid Waste Amendments of the 1984. In Sections 3.0 through 6.0 of this report, the four aggregate areas are subdivided into their operable units. The operable units are further divided into two parts: (1) those waste management units assigned to the operable unit that will be remediated as part of the Environmental Restoration Remedial Actions (ERRA) Program, and (2) those waste management units located within the operable unit boundaries but not assigned to the ERRA program. Only some operable unit sections contain the second part

  17. Annual report of 1991 groundwater monitoring data for the Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin at the Y-12 Plant: Reporting and statistical evaluation of the subsequent year (sixth) data

    International Nuclear Information System (INIS)

    McMahon, L.W.; Mercier, T.M.

    1992-02-01

    This annual report has historically been prepared to meet the annual reporting requirements of the Tennessee Department of and Environment and Conservation (TDEC), Hazardous Waste Management Regulation 1200-1-11-.05 (6)(e), for detection monitoring data collected on Resource Conservation and Recovery Act (RCRA) wells in place around facilities which are accorded interim status. The regulatory authority for these units at the Y-12 Plant is currently in transition. A Federal Facility Agreement (FFA) with an effective date of January 1, 1992, has been negotiated with the Department of Energy (DOE) for the Oak Ridge Reservation. This agreement provides a framework for remediation of the Oak Ridge Reservation so that both RCRA and CERCLA requirements are integrated into the remediation process and provides for State, EPA, and DOE to proceed with CERCLA as the lead regulatory requirement and RCRA as an applicable or relevant and appropriate requirement. This report is presented for the RCRA certified wells for two interim status units at the Y-12 Plant. These units are Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin. Kerr Hollow is currently undergoing clean closure under RCRA. The Chestnut Ridge Sediment Disposal Basin (CRSDB) was closed in 1989 under a TDEC approved RCRA closure plan. The relevance of a RCRA Post-Closure Permit to either of these units is a matter of contention between DOE and TDEC since the FFA does not contemplate post-closure permits

  18. Low-level radioactive mixed waste land disposal facility -- Permanent disposal

    International Nuclear Information System (INIS)

    Erpenbeck, E.G.; Jasen, W.G.

    1993-03-01

    Radioactive mixed waste (RMW) disposal at US Department of Energy (DOE) facilities is subject to the Resource Conservation and Recovery Act of 1976 (RCRA) and the Hazardous and Solid Waste Amendments of 1984 (HSWA). Westinghouse Hanford Company, in Richland, Washington, has completed the design of a radioactive mixed waste land disposal facility, which is based on the best available technology compliant with RCRA. When completed, this facility will provide permanent disposal of solid RMW, after treatment, in accordance with the Land Disposal Restrictions. The facility includes a double clay and geosynthetic liner with a leachate collection system to minimize potential leakage of radioactive or hazardous constituents from the landfill. The two clay liners will be capable of achieving a permeability of less than 1 x 10 -7 cm/s. The two clay liners, along with the two high density polyethylene (HDPE) liners and the leachate collection and removal system, provide a more than conservative, physical containment of any potential radioactive and/or hazardous contamination

  19. RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

  20. RCRA closures at Rocky Flats Plant: A programmatic perspective and case study

    International Nuclear Information System (INIS)

    Ogg, Randy T.; Peterman, Bruce D.

    1992-01-01

    The Interagency Agreement (IAG) integrates a unique mechanism for remediating hazardous waste sites at the Rocky Flats Plant (RFP), which include utilizing RCRA and CERCLA technical/regulatory processes. Pursuant to the IAG signed by the Department of Energy (DOE), Environmental Protection Agency (EPA), and the Colorado Department of Health (CDH) on January 22, 1991, sixteen operable units (OUs) were defined for characterization and remediation at RFP. Of the sixteen OUs, six are classified as Resource Conservation and Recovery Act (RCRA) closure units. The six RCRA interim status closure units are: Solar Evaporation Ponds-OU 4, Present LandfUl-OU 7, Original Process Waste Lines-OU 9, Other Outside Closures-OU 10, West Spray Field-OU II, and Inside Building Closures-OU 15. The IAG will function as a technical/regulatory mechanism for managing/complying with all aspects of the RCRA interim status closure units at RFP. (author)

  1. Expediting the commercial disposal option: Low-level radioactive waste shipments from the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    Rice, S.; Rothman, R.

    1995-12-31

    In April, Envirocare of Utah, Inc., successfully commenced operation of its mixed waste treatment operation. A mixed waste which was (a) radioactive, (b) listed as a hazardous waste under the Resource Conservation and Recovery Act (RCRA), and (c) prohibited from land disposal was treated using Envirocare`s full-scale Mixed Waste Treatment Facility. The treatment system involved application of chemical fixation/stabilization technologies to reduce the leachability of the waste to meet applicable concentration-based RCRA treatment standards. In 1988, Envirocare became the first licensed facility for the disposal of naturally occurring radioactive material. In 1990, Envirocare received a RCRA Part B permit for commercial mixed waste storage and disposal. In 1994, Envirocare was awarded a contract for the disposal of DOE mixed wastes. Envirocare`s RCRA Part B permit allows for the receipt, storage, treatment, and disposal of mixed wastes that do not meet the land-disposal treatment standards of 40 CFR (Code of Federal Regulations) 268. Envirocare has successfully received, managed, and disposed of naturally occurring radioactive material, low-activity radioactive waste, and mixed waste from government and private generators.

  2. Calendar Year 2007 Resource Conservation and Recovery Act Annual Monitoring Report for the U.S. Department of Energy Y-12 National Security Complex, Oak Ridge, Tennessee - RCRA Post-Closure Permit Nos. TNHW-113, TNHW-116, and TNHW-128

    Energy Technology Data Exchange (ETDEWEB)

    Elvado Environmental

    2008-02-01

    This report contains groundwater quality monitoring data obtained during calendar year (CY) 2007 at the following hazardous waste treatment, storage, and disposal (TSD) units located at the US Department of Energy (DOE) Y-12 National Security Complex (hereafter referenced as Y-12) in Oak Ridge, Tennessee; this S-3 Site, Oil Landfarm, Bear Creek Burial Grounds/Walk-In Pits (BCBG/WIP), Eastern S-3 Site Plume, Chestnut Ridge Security Pits (CRSP), Chestnut Ridge Sediment Disposal Baste (CRSDB), few Hollow Quarry (KHQ), and East Chestnut Ridge Waste Pile (ECRWP). Hit monitoring data were obtained in accordance with the applicable Resource Conservation and Recovery Act of 1976 (RCRA) hazardous waste post-closure permit (PCP). The Tennessee Department of Environment and Conservation (TDEC) - Division of Solid Waste Management issued the PCPs to define the requirements for RCRA post-closure inspection, maintenance, and groundwater monitoring at the specified TSD units located within the Bear Creek Hydrogeologic Regime (PCP no. TNHW-116), Upper East Fork Poplar Creek Hydrogeologic Regime (PCP no. TNHW-113), and Chestnut Ridge Hydrogeologic Regime (PCP no. TNHW-128). Each PCP requires the Submittal of an annual RCRA groundwater monitoring report containing the groundwater sampling information and analytical results obtained at each applicable TSD unit during the preceding CY, along with an evaluation of groundwater low rates and directions and the analytical results for specified RCRA groundwater target compounds; this report is the RCRA annual groundwater monitoring report for CY 2007. The RCRA post-closure groundwater monitoring requirements specified in the above-referenced PCP for the Chestnut Ridge Regime replace those defined in the previous PCP (permit no. TNHW-088), which expired on September 18, 2005, but remained effective until the TDEC issued the new PCP in September 2006. The new PCP defines site-specific groundwater sampling and analysis requirements for the

  3. RCRA facility investigation report for the 200-PO-1 operable unit. Revision 1

    International Nuclear Information System (INIS)

    1997-05-01

    This Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) report is prepared in support of the RFI/corrective measures study process for the 200-PO-1 Groundwater Operable Unit in the 200 East Area of the Hanford Site. This report summarizes existing information on this operable unit presented in the 200 East and PUREX Aggregate Area Management Study Reports, contaminant specific studies, available modeling data, and groundwater monitoring data summary reports. Existing contaminant data are screened against current regulatory limits to determine contaminants of potential concern (COPC). Each identified COPC is evaluated using well-specific and plume trend analyses

  4. Implementing RCRA during facility deactivation

    International Nuclear Information System (INIS)

    Lebaron, G.J.

    1997-01-01

    RCRA regulations require closure of permitted treatment, storage and disposal (TSD) facilities within 180 days after cessation of operations, and this may essentially necessitate decommissioning to complete closure. A more cost effective way to handle the facility would be to significantly reduce the risk to human health and the environment by taking it from its operational status to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to decommissioning. This paper presents an innovative approach to the cost effective deactivation of a large, complex chemical processing facility permitted under RCRA. The approach takes into account risks to the environment posed by this facility in comparison to risks posed by neighboring facilities at the site. The paper addresses the manner in which: 1) stakeholders and regulators were involved; 2) identifies a process by which the project proceeds and regulators and stakeholders were involved; 3) end points were developed so completion of deactivation was clearly identified at the beginning of the project, and 4) innovative practices were used to deactivate more quickly and cost effectively

  5. Characterizing cemented TRU waste for RCRA hazardous constituents

    International Nuclear Information System (INIS)

    Yeamans, D.R.; Betts, S.E.; Bodenstein, S.A.

    1996-01-01

    Los Alamos National Laboratory (LANL) has characterized drums of solidified transuranic (TRU) waste from four major waste streams. The data will help the State of New Mexico determine whether or not to issue a no-migration variance of the Waste Isolation Pilot Plant (WIPP) so that WIPP can receive and dispose of waste. The need to characterize TRU waste stored at LANL is driven by two additional factors: (1) the LANL RCRA Waste Analysis Plan for EPA compliant safe storage of hazardous waste; (2) the WIPP Waste Acceptance Criteria (WAC) The LANL characterization program includes headspace gas analysis, radioassay and radiography for all drums and solids sampling on a random selection of drums from each waste stream. Data are presented showing that the only identified non-metal RCRA hazardous component of the waste is methanol

  6. Alternative Site Technology Deployment-Monitoring System for the U-3ax/bl Disposal Unit at the Nevada Test Site

    International Nuclear Information System (INIS)

    Dixon, J.M.; Levitt, D.G.; Rawlinson, S.E.

    2001-01-01

    In December 2000, a performance monitoring facility was constructed adjacent to the U-3ax/bl mixed waste disposal unit at the Nevada Test Site (NTS). Recent studies conducted in the arid southwestern United States suggest that a vegetated monolayer evapotranspiration (ET) closure cover may be more effective at isolating waste than traditional Resource Conservation and Recovery Act (RCRA) multi-layered designs. The monitoring system deployed next to the U-3ax/bl disposal unit consists of eight drainage lysimeters with three surface treatments: two are left bare; two are revegetated with native species; two are being allowed to revegetate with invader species; and two are reserved for future studies. Soil used in each lysimeter is native alluvium taken from the same location as the soil used for the cover material on U-3ax/bl. The lysimeters were constructed so that any drainage to the bottom can be collected and measured. To provide a detailed evaluation of the cover performance, an ar ray of 16 sensors was installed in each lysimeter to measure soil water content, soil water potential, and soil temperature. Revegetation of the U-3ax/bl closure cover establishes a stable plant community that maximizes water loss through transpiration while at the same time, reduces water and wind erosion and ultimately restores the disposal unit to its surrounding Great Basin Desert environment

  7. The implications of RCRA [Resource Conservation and Recovery Act] regulation for the disposal of transuranic and high-level waste

    International Nuclear Information System (INIS)

    Sigmon, C.F.; Sharples, F.E.; Smith, E.D.

    1988-01-01

    In May of 1987 the Department of Energy (DOE) published a rule interpreting the definition of ''byproduct'' under the Atomic Energy Act. This byproduct rule clarified the role of the Resource Conservation and Recovery Act (RCRA) in the regulation of DOE's radioactive waste management activities. According to the rule, only the radioactive portion of DOE's mixed radioactive and hazardous waste (mixed waste), including mixed transuranic (TRU) and high-level waste (HLW), is exempt from RCRA under the byproduct exemption. The portion of a waste that is hazardous as defined by RCRA is subject to full regulation under RCRA. Because the radioactive and hazardous portions of m any, if not most, DOE wastes are likely to be inseparable, the rule in effect makes most mixed wastes subject to dual regulation. The potential application of RCRA to facilities such as the Waste Isolation Pilot Plant (WIPP) and the HLW repository creates unique challenges for both the DOE and regulatory authorities. Strategies must be developed to assure compliance with RCRA without either causing excessive administrative burdens or abandoning the goal of minimizing radiation exposure. This paper will explore some of the potential regulatory options for and recent trends in the regulation of TRU and HLW under RCRA

  8. Storing, Transporting and Disposing of Mercury in Your Home

    Science.gov (United States)

    ... RCRA) Recycling and Disposal Requirements that Apply to Business and Industry RCRA designates some widely generated hazardous ... Contact Us Hotlines FOIA Requests Frequent Questions Follow. Facebook Twitter YouTube Flickr Instagram Last updated on June ...

  9. RCRA closure of eight land-based units at the Y-12 plant

    International Nuclear Information System (INIS)

    Stone, J.E.; Welch, S.H.

    1988-01-01

    Eight land-based hazardous waste management units at the Oak Ridge Y-12 Plant are being closed under an integrated multi-year program. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. These units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. The closure of these sites will be funded by a new Department of Energy budget category, the Environmental Restoration Budget Category (ERBC), which is intended to provide greater flexibility in the response to closure and remedial activities. A major project, Closure and Post-Closure Activities (CAPCA), has been identified for ERBC funding to close and remediate the land units in accordance with RCRA requirements. Establishing the scope of this program has required the development of risk assessments and the preparation of an integrated schedule

  10. Hanford Site waste management units report

    International Nuclear Information System (INIS)

    1993-04-01

    The Hanford Site Waste Management Units Report was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments of the 1984. This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in the report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of the units report, the list of units is more extensive than required by Section 3004(u) of Hazardous and Solid Waste Amendments of the 1984. In Sections 3.0 through 6.0 of this report, the four aggregate areas are subdivided into their operable units. The operable units are further divided into two parts: (1) those waste management units assigned to the operable unit that will be remediated as part of the Environmental Restoration Remedial Actions (ERRA) Program, and (2) those waste management units located within the operable unit boundaries but not assigned to the ERRA program. Only some operable unit sections contain the second part.Volume two contains Sections 4.0 through 6.0 and the following appendices: Appendix A -- acronyms and definition of terms; Appendix B -- unplanned releases that are not considered to be units; and Appendix C -- operable unit maps

  11. Decontamination Study for Mixed Waste Storage Tanks RCRA Closure

    International Nuclear Information System (INIS)

    Leaphart, D.M.; Reed, S.R.; Rankin, W.N.

    1995-01-01

    The Savannah River Site (SRS) plans to close six underground tanks storing mixed waste under RCRA regulations. In support of this closure effort, a study was performed to determine the optimal method of decontaminating these tanks to meet the closure requirements. Items consaidered in the evaluation of the decontamination methods included effectiveness, compatibility with existing waste residues, possible cleaning solution disposal methods, and cost

  12. Preparation of radioactive ''mixed'' waste samples for measurement of RCRA [Resource Conservation and Recovery Act] organic compounds

    International Nuclear Information System (INIS)

    Tomkins, B.A.; Caton, J.E.

    1987-01-01

    A radioactive ''mixed'' waste typically contains alpha-, beta-, or gamma-emitting radionuclides and varying quantities of semivolatile or volatile organic species, some or all of which may be named specifically by the Resource Conservation and Recovery Act (RCRA). Because there are no acceptable means available currently for disposing of these mixed wastes, they are presently stored above-ground in sealed drums. For this reason, analytical procedures which can determine RCRA organics in radioactive waste are necessary for deciding the proper approach for disposal. An important goal of this work is the development of methods for preparing mixed waste samples in a manner which allows the RCRA organics to be measured in conventional organic analysis laboratories without special precautions. Analytical procedures developed for handling mixed waste samples must satisfy not only the usual constraints present in any trace-level organic chemical determination, but also those needed to insure the protection of the operator from radioactive contamination. Consequently, procedures should be designed to use the least amount of radioactive sample commensurate with achieving acceptable sensitivity with the RCRA analytical methods. Furthermore, the unusual laboratory glassware which would normally be used should be replaced with disposable materials wherever possible, in order to reduce the ''clean-up'' time required, and thereby reduce the operator's exposure to radioactivity. Actual sample handling should be reduced to the absolute minimum. Finally, the final isolate must exhibit a sufficiently low level of alpha, beta, or gamma activity to permit detailed characterization in a conventional organic analysis laboratory. 4 refs., 5 tabs

  13. RCRA and operational monitoring 1994 fiscal year work plan, WBS 1.5.3

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    RCRA & Operational Monitoring (ROM) Program Office manages the direct funded Resource Conservation Recovery Act (RCRA) and Operational Monitoring under Work Breakdown Structure (WBS) 1.5.3. The ROM Program Office is a Branch of liquid Waste Disposal, a part of Restoration and Remediation of Westinghouse Hanford Company (WHC). The Fiscal Year Work Plan (FYWP) takes it direction from the Multi-Year Program Plan (MYPP). The FYWP provides the near term, enhanced details for the Program Office to use as baseline Cost, Scope and Schedule. Changs Control administered during the fiscal year is against the baseline provided by the FYWP.

  14. RCRA and operational monitoring 1994 fiscal year work plan, WBS 1.5.3

    International Nuclear Information System (INIS)

    1993-12-01

    RCRA ampersand Operational Monitoring (ROM) Program Office manages the direct funded Resource Conservation Recovery Act (RCRA) and Operational Monitoring under Work Breakdown Structure (WBS) 1.5.3. The ROM Program Office is a Branch of liquid Waste Disposal, a part of Restoration and Remediation of Westinghouse Hanford Company (WHC). The Fiscal Year Work Plan (FYWP) takes it direction from the Multi-Year Program Plan (MYPP). The FYWP provides the near term, enhanced details for the Program Office to use as baseline Cost, Scope and Schedule. Changs Control administered during the fiscal year is against the baseline provided by the FYWP

  15. Development of guidance for preparing treatability variance petitions from the RCRA Land Disposal Restrictions for DOE [Department of Energy] mixed-waste streams

    International Nuclear Information System (INIS)

    Harms, T.; Scheuer, N.; Martin, R.; Van Epp, T.; Triplett, M.

    1990-01-01

    In response to the Department of Energy's (DOE) anticipated need for variances from the Resource Conservation and Recovery Act (RCRA) Land Disposal Restriction (LDR) treatment requirements, a treatability variance guidance document is being prepared for use by DOE facilities and operations offices. The guidance document, although applicable to non-mixed hazardous waste streams, provides specific guidance regarding radioactive mixed-waste streams. Preparation of the guidance manual has involved developing an overview of the Land Disposal Restrictions, as well as an overview of the petition preparation process. The DOE internal review requirements are specifically addressed in the manual. Specific data requirements and engineering analyses are also described. A discussion of EPA's criteria for granting a treatability variance is also provided. A checklist for completeness of the petition is provided. Model language for use in DOE treatability variance petitions will be provided in a petition for a DOE waste stream as an appendix to the document

  16. Resource Conservation and Recovery Act (RCRA) Part B Permit Application for Production Associated Units at the Oak Ridge Y-12 Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This is the RCRA required permit application for Radioactive and Hazardous Waste Management at the Oak Ridge Y-12 Plant for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; Cyanide Treatment Unit. All four of these units are associated with the recovery of enriched uranium and other metals from wastes generated during the processing of nuclear materials.

  17. Resource Conservation and Recovery Act (RCRA) Part B Permit Application for Production Associated Units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1994-09-01

    This is the RCRA required permit application for Radioactive and Hazardous Waste Management at the Oak Ridge Y-12 Plant for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; Cyanide Treatment Unit. All four of these units are associated with the recovery of enriched uranium and other metals from wastes generated during the processing of nuclear materials

  18. Managing previously disposed waste to today's standards

    International Nuclear Information System (INIS)

    1990-01-01

    A Radioactive Waste Management Complex (RWMC) was established at the Idaho National Engineering Laboratory (INEL) in 1952 for controlled disposal of radioactive waste generated at the INEL. Between 1954 and 1970 waste characterized by long lived, alpha emitting radionuclides from the Rocky Flats Plant was also buried at this site. Migration of radionuclides and other hazardous substances from the buried Migration of radionuclides and other hazardous substances from the buried waste has recently been detected. A Buried Waste Program (BWP) was established to manage cleanup of the buried waste. This program has four objectives: (1) determine contaminant sources, (2) determine extent of contamination, (3) mitigate migration, and (4) recommend an alternative for long term management of the waste. Activities designed to meet these objectives have been under way since the inception of the program. The regulatory environment governing these activities is evolving. Pursuant to permitting activities under the Resource Conservation and Recovery Act (RCRA), the Department of Energy (DOE) and the Environmental Protection Agency (EPA) entered into a Consent Order Compliance Agreement (COCA) for cleanup of past practice disposal units at the INEL. Subsequent to identification of the RWMC as a release site, cleanup activities proceeded under dual regulatory coverage of RCRA and the Atomic Energy Act. DOE, EPA, and the State of Idaho are negotiating a RCRA/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interagency Agreement (IAG) for management of waste disposal sites at the INEL as a result of the November 1989 listing of the INEL on the National Priority List (NPL). Decision making for selection of cleanup technology will be conducted under the CERCLA process supplemented as required to meet the requirements of the National Environmental Policy Act (NEPA). 7 figs

  19. RCRA land unit closures at the Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Welch, S.H.; Kelly, B.A.; Delozier, M.F.P.; Manrod, W.E.

    1987-01-01

    Eight land-based hazardous waste management units at the Y-12 Plant are being closed under an integrated multi-year program. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. These units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. The closure of these sites will be funded by a new Department of Energy budget category, the Environmental Restoration Budget Category (ERBC), which is intended to provide greater flexibility in the response to closure and remedial activities. A major project, Closure and Post-Closure Activities (CAPCA), has been identified for ERBC funding to close and remediate the land units in accordance with RCRA requirements. Establishing the scope of this program has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA program include the development of risk assessments and the preparation of an integrated schedule

  20. Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Oakley, L.B.; Siberell, J.K.; Voskuil, T.L.

    1993-06-01

    Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruction Report is to summarize numerous technical reports and provide CERCLA documentation for completion of the remedial actions. Other CERCLA reports, such as the Feasibility Study for the UNC Disposal Site, provide documentation leading up to the remedial action decision. The remedial action chosen, placement of a modified RCRA cap, was completed successfully, and performance standards were either met or exceeded. This remedial action provided solutions to two environmentally contaminated areas and achieved the goal of minimizing the potential for contamination of the shallow groundwater downgradient of the site, thereby providing protection of human health and the environment. Surveillance and maintenance of the cap will be accomplished to ensure cap integrity, and groundwater monitoring downgradient of the site will continue to confirm the acceptability of the remedial action chosen

  1. First annual report RCRA post-closure monitoring and inspections for the U-3fi waste unit. Final report, July 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.

    1997-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi RCRA Unit, located in Area 3 of the Nevada Site (NTS), Nye County, Nevada during the July 1995 to October 1996 period. Inspections of the U-3fi RCRA Unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 420 ft ER3-3 borehole and detect changes that may be indicative of moisture movement in the regulated interval. This is the first annual report on the U-3fi closure and includes the first year baseline monitoring data as well as one quarter of compliance monitoring data

  2. Regulated Disposal of NORM/TENORM Waste in Colorado: The Deer Trail Landfill

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Retallick, P.G.; Kehoe, J.H.; Webb, M.M.; Nielsen, D.B.; Spaanstra, J.R.; Kornfeld, L.M.

    2006-01-01

    On January 31, 2005, Clean Harbors Environmental Services submitted a license application to the Colorado Department of Public Health and Environment (CDPHE) for the disposal of naturally occurring radioactive material (NORM) and technologically enhanced radioactive material (TENORM) at Clean Harbor's Deer Trail RCRA Subtitle C landfill. Deer Trail is located 70 miles east of Denver, Colorado. The license application for Deer Trail was submitted under CCR 1007-1, Part 14 [1] the Colorado State equivalent of 10 CFR Part 61 [2] for radioactive waste disposal. A disposal license is required since some of the NORM/TENORM waste in Colorado is licensed by CDPHE. The license application does not extend to byproduct or source material, and thus does not include the broader categories found in Class A radioactive waste. The license application requires the establishment of a radiation protection program, assuring that all NORM/TENORM waste, even non-licensed waste disposed under RCRA, will have appropriate radiological controls for workers, the public, and the environment. Because Deer Trail is a RCRA Subtitle C facility with an active RCRA Permit and because of the overlapping and similar requirements in the process to obtain either a RCRA permit or a radioactive waste disposal license, the license process for Deer Trail was appropriately focused. This focusing was accomplished by working with the Colorado Department of Public Health and Environment (CDPHE) and excluding or waiving selected radioactive materials license requirements from further consideration because they were found to be adequately addressed under the RCRA Permit. Of most significance, these requirements included: - Institutional Information - Federal or State ownership will not be required, since the State's Radiation Control regulations allow for private site ownership, consistent with the same financial assurance and institutional control requirements of RCRA. - Development of Additional Technical

  3. RCRA Facility Investigation/Remedial Investigation Report with Baseline Risk Assessment for the Central Shops Burning/Rubble Pit (631-6G), Volume 1 Final

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The Burning/Rubble Pits at the Savannah River Site were usually shallow excavations approximately 3 to 4 meters in depth. Operations at the pits consisted of collecting waste on a continuous basis and burning on a monthly basis. The Central Shops Burning/Rubble Pit 631- 6G (BRP6G) was constructed in 1951 as an unlined earthen pit in surficial sediments for disposal of paper, lumber, cans and empty galvanized steel drums. The unit may have received other materials such as plastics, rubber, rags, cardboard, oil, degreasers, or drummed solvents. The BRP6G was operated from 1951 until 1955. After disposal activities ceased, the area was covered with soil. Hazardous substances, if present, may have migrated into the surrounding soil and/or groundwater. Because of this possibility, the United States Environmental Protection Agency (EPA) has designated the BRP6G as a Solid Waste Management Unit (SWMU) subject to the Resource Conservation Recovery Act/Comprehensive Environmental Response, Compensation and Liability Act (RCRA/CERCLA) process.

  4. Exiting RCRA Subtitle C regulation data for supporting a new regulatory path for immobilized mixed debris

    Energy Technology Data Exchange (ETDEWEB)

    Porter, C.L. [Jetseal, Inc., Idaho Falls, ID (United States); Carson, S.D.; Cheng, Wu-Ching [Sandia National Labs., Albuquerque, NM (United States)

    1995-12-31

    This paper presents analytical and empirical data that provide technical support for the position that mixed debris (debris contaminated with both radioactive and hazardous constituents) treated by immobilization in accordance with 40 CFR 268.45 can exit RCRA Subtitle C requirements at the time the treatment is complete. Pathways analyses and risk assessments of low-level waste and RCRA mixed waste disposal facilities show that these two types of facilities provide equivalent long-term (> 100 years) performance and protection of human health and the environment. A proposed two-tier approach for waste form performance criteria is discussed.

  5. Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Oakley, L.B.; Siberell, J.K.; Voskuil, T.L.

    1993-06-01

    Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruction Report is to summarize numerous technical reports and provide CERCLA documentation for completion of the remedial actions. Other CERCLA reports, such as the Feasibility Study for the UNC Disposal Site, provide documentation leading up to the remedial action decision. The remedial action chosen, placement of a modified RCRA cap, was completed successfully, and performance standards were either met or exceeded. This remedial action provided solutions to two environmentally contaminated areas and achieved the goal of minimizing the potential for contamination of the shallow groundwater downgradient of the site, thereby providing protection of human health and the environment. Surveillance and maintenance of the cap will be accomplished to ensure cap integrity, and groundwater monitoring downgradient of the site will continue to confirm the acceptability of the remedial action chosen.

  6. Hanford Facility RCRA permit handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    Purpose of this Hanford Facility (HF) RCRA Permit Handbook is to provide, in one document, information to be used for clarification of permit conditions and guidance for implementing the HF RCRA Permit.

  7. Groundwater Monitoring Plan for the 1301-N, 1324-N/NA, and 1325-N RCRA Facilities

    International Nuclear Information System (INIS)

    Hartman, Mary J.

    2001-01-01

    The 1301-N and 1325-N Liquid Waste Disposal Facilities, the 1324-N Surface Impoundment, and the 1324-NA Percolation Pond, located in the 100 N Area of the Hanford Site, are regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The closure plans for these facilities stipulate that groundwater is monitored according to the 100-N Pilot Project: Proposed Consolidated Groundwater Monitoring Program (BHI-00725). This document supplements the consolidated plan by providing information on sampling and analysis protocols, quality assurance, data management, and a conceptual model for the RCRA sites. Monitoring well networks, constituents, and sampling frequency remain the same as in the consolidated plan or the previous groundwater monitoring plan (Hartman 1996)

  8. Commercial mixed waste treatment and disposal

    International Nuclear Information System (INIS)

    Vance, J.K.

    1994-01-01

    At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

  9. Nonradiological groundwater quality at low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Goode, D.J.

    1986-04-01

    The NRC is investigating appropriate regulatory options for disposal of low-level radioactive waste containing nonradiological hazardous constituents, as defined by EPA regulations. Standard EPA/RCRA procedures to determine hazardous organics, metals, indicator parameters, and general water quality are applied to samples from groundwater monitoring wells at two commercial low-level radioactive waste disposal sites. At the Sheffield, IL site (nonoperating), several typical organic solvents are identified in elevated concentrations in onsite wells and in an offsite area exhibiting elevated tritium concentrations. At the Barnwell, SC site (operating), only very low concentrations of three organics are found in wells adjacent to disposal units. Hydrocarbons associated with petroleum products are detected at both sites. Hazardous constituents associated with previosuly identified major LLW mixed waste streams, toluene, xylene, chromium, and lead, are at or below detection limits or at background levels in all samples. Review of previously collected data also supports the conclusion that organic solvents are the primary nonradiological contaminants associated with LLW disposal

  10. Deployment of an Alternative Closure Cover and Monitoring System at the Mixed Waste Disposal Unit U-3ax/bl at the Nevada Test Site

    International Nuclear Information System (INIS)

    Levitt, D.G.; Fitzmaurice, T.M.

    2001-01-01

    In October 2000, final closure was initiated of U-3ax/bl, a mixed waste disposal unit at the Nevada Test Site (NTS). The application of approximately 30 cm of topsoil, composed of compacted native alluvium onto an operational cover, seeding of the topsoil, installation of soil water content sensors within the cover, and deployment of a drainage lysimeter facility immediately adjacent to the disposal unit initiated closure. This closure is unique in that it required the involvement of several U.S. Department of Energy (DOE) Environmental Management (EM) groups: Waste Management (WM), Environmental Restoration (ER), and Technology Development (TD). Initial site characterization of the disposal unit was conducted by WM. Regulatory approval for closure of the disposal unit was obtained by ER, closure of the disposal unit was conducted by ER, and deployment of the drainage lysimeter facility was conducted by WM and ER, with funding provided by the Accelerated Site Technology Deployment ( ASTD) program, administered under TD. In addition, this closure is unique in that a monolayer closure cover, also known as an evapotranspiration (ET) cover, consisting of native alluvium, received regulatory approval instead of a traditional Resource Conservation and Recovery Act (RCRA) multi-layered cover. Recent studies indicate that in the arid southwestern United States, monolayer covers may be more effective at isolating waste than layered covers because of the tendency of clay layers to desiccate and crack, and subsequently develop preferential pathways. The lysimeter facility deployed immediately adjacent to the closure cover consists of eight drainage lysimeters with three surface treatments: two were left bare; two were revegetated with native species; two were allowed to revegetate with invader species; and two are reserved for future studies. The lysimeters are constructed such that any drainage through the bottoms of the lysimeters can be measured. Sensors installed in the

  11. Resource Conservation and Recovery Act (RCRA)

    International Nuclear Information System (INIS)

    1989-01-01

    This Resource Conservation and Recovery Act (RCRA) Facility Investigation Program Plan has been developed to provide a framework for the completion of RCRA Facility Investigations (RFI) at identified units on the Savannah Rive Site (SRS) facility. As such, the RFI Program Plan provides: technical guidance for all work to be performed, managerial control, a practical, scientific approach. The purpose of this Overview is to demonstrate how the basic RFI Program Plan elements (technical, management, and approach) are interwoven to provide a practical and workable plan. The goal of the RFI Program Plan is to provide a systematic, uniform approach for performance and reporting. In addition, the RFI Program Plan has been developed to be specific to the SRS facility and to adhere to the Environmental Protection Agency (EPA) RFI guidance received as part of the SRS. The US EPA publication ''Characterization of Hazardous Waste Sites'' has been liberally adapted for use in this RFI Program Plan

  12. Quarterly report of RCRA groundwater monitoring data for period January 1--March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This quarterly report contains data received between January and March 1995, which are the cutoff dates for this reporting period. This report may contain not only data from the January through March quarter, but also data from earlier sampling events that were not previously reported. Nineteen Resource Conservation and Recovery Act of 1976 (RCRA) groundwater monitoring projects are conducted at the Hanford Site. These projects include treatment, storage, and disposal facilities for both solid and liquid waste. The groundwater monitoring programs described in this report comply with the interim-status federal (Title 40 Code of Federal Regulation [CFR] Part 265) and state (Washington Administrative Code [WAC] 173-303-400) regulations. The RCRA projects are monitored under one of three programs: background monitoring, indicator parameter evaluation, or groundwater quality assessment.

  13. RCRA corrective action and closure

    International Nuclear Information System (INIS)

    1995-02-01

    This information brief explains how RCRA corrective action and closure processes affect one another. It examines the similarities and differences between corrective action and closure, regulators' interests in RCRA facilities undergoing closure, and how the need to perform corrective action affects the closure of DOE's permitted facilities and interim status facilities

  14. Treatment, Storage and Disposal (TSD) Corrective Action Facility Polygons, Region 9, 2015, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — RCRA Treatment, Storage and Disposal facilities (TSDs) are facilities that have treated, stored or disposed of hazardous wastes. They are required to clean up...

  15. Resource Conservation and Recovery Act (RCRA) new-employee training manual for the Operations Division RCRA personnel

    Energy Technology Data Exchange (ETDEWEB)

    Barkenbus, B.D.

    1987-03-01

    This manual has been prepared for the training of new employees who will work with RCRA hazardous waste management in the Operations Division. It will be taught by a person who is trained in hazardous waste regulations/procedures. It consists of nine modules. The topics of these modules are: RCRA Training, Hazardous Waste Regulations, Transportation Regulations, Hazardous Waste Management at ORNL, Chemical Hazards and Safety, Hazardous Waste Operations Training, Sampling of Hazardous Waste, Hazardous Waste Identification/Classification, and RCRA Contingency Plans and Emergency Procedures. The on-the-job training areas are identified in the modules. They are an integral part of training.

  16. Clues to interpretation of RCRA regulations

    International Nuclear Information System (INIS)

    Siebach, P.R.; Brown, P.H.

    1992-01-01

    Waste waters from industrial facilities are often treated at waste water treatment plants and then discharged to streams or rivers, or may be reused. Discharges of pollutants to waterways are regulated under the Clean Water Act, and require a permit. The Resource Conservation and Recovery Act (RCRA) regulates the management of solid wastes. This paper discusses the status of waste water treatment plant discharges and sludges pursuant to RCRA. It concludes that some exceptions to RCRA allow waste water treatment plants to accept dilute solvent mixtures, treat them, and discharge effluent without needing a RCRA permit. If residual sludges do not exhibit a hazardous characteristic, then they may be managed as nonhazardous solid waste. For DOE and other generators of mixed waste (both radioactive and hazardous), this may allow sludges to be managed as low level radioactive waste. (author)

  17. Successful completion of a RCRA closure for the Fernald Environmental Management Project

    International Nuclear Information System (INIS)

    Lippitt, J.M.; Kolthoff, K.

    1995-01-01

    This paper discusses the successful completion of a RCRA (Resource Conservation and Recovery Act) closure of a HF (hydrofluoric acid) tank car at FEMP, which is on the national priorities list of hazardous waste sites and is undergoing CERCLA remediation. The HF tank car closure was conducted by FERMCO. Through a combination of sound planning and team work, the HF tank car was closed safely and ahead of schedule. During > 22,000 hr field work required for construction modifications and neutralization of 9,600 gallons of HF and decontamination rinseates, there were no OSHA recordable incidents. The system design avoided additional costs by maximizing use of existing equipment and facilities. This successful closure of the HF tank car demonstrates FEMP's commitment to reducing risks and cleaning up the facility in a manner consistent with objectives of RCRA regulations and the Ohio EPA hazardous waste rules. This in turn facilitated ongoing negotiations with Ohio EPA to integrate RCRA closure and the ongoing CERCLA remediation activities. This paper addresses why the unit was clean closed under an approved RCRA Closure Plan. Integration of EPA regulations for RCRA and CERCLA programs and the DOE-Orders impacting design, construction and operation of an acid neutralization system is also reviewed. The paper concludes with a discussion of lessons learned in the process in preparing the closure plant and through final project close out

  18. DOE Land Disposal Restrictions strategy report for radioactive mixed waste

    International Nuclear Information System (INIS)

    1989-09-01

    This report is based on preliminary information available at the time of the Land Disposal Restrictions (LDR) Strategy Workshop in June 1989, and the critical review of the workshop data conducted by the Office Of Defense Programs and the affected Operations Offices in July and August 1989. The purpose of the workshop and this subsequent report is to identify the magnitude and scope of LDR issues and impacts regarding the storage, treatment, and disposal of RMW, and to suggest potential strategies for addressing LDR requirements. This report was prepared under the overall direction and coordination of the Department of Energy (DOE) Headquarters Environmental Guidance Division, RCRA/CERCLA Unit (EH-231). The report is a product of the LDR Strategy Workshop held during the month of June 1989. The workshop was divided into two work groups: a Land Disposal Restriction compliance strategy group and a RMW Best Demonstrated Available Technology and National Capacity Variance group

  19. Disposal of Draeger Tubes at Savannah River Site

    International Nuclear Information System (INIS)

    Malik, N.P.

    2000-01-01

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed

  20. RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

    International Nuclear Information System (INIS)

    2010-01-01

    The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

  1. RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-06-17

    The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

  2. Groundwater monitoring plan for the Hanford Site 216-B-3 pond RCRA facility

    International Nuclear Information System (INIS)

    Barnett, D.B.; Chou, C.J.

    1998-06-01

    The 216-B-3 pond system was a series of ponds for disposal of liquid effluent from past Hanford production facilities. In operation since 1945, the B Pond system has been a RCRA facility since 1986, with Resource Conservation and Recovery Act (RCRA) interim-status groundwater monitoring in place since 1988. In 1994, discharges were diverted from the main pond, where the greatest potential for contamination was thought to reside, to the 3C expansion pond. In 1997, all discharges to the pond system were discontinued. In 1990, the B Pond system was elevated from detection groundwater monitoring to an assessment-level status because total organic halogens and total organic carbon were found to exceed critical means in two wells. Subsequent groundwater quality assessment failed to find any specific hazardous waste contaminant that could have accounted for the exceedances, which were largely isolated in occurrence. Thus, it was recommended that the facility be returned to detection-level monitoring

  3. Dewatering and RCRA partial closure action on solar evaporation ponds, Rocky Flats Plant, Golden, Colorado

    International Nuclear Information System (INIS)

    1991-06-01

    The Department of Energy (DOE) has prepared an Environmental Assessment (DOE/EA-0487) on its proposal to partially close five solar evaporation ponds at the Rocky Flats Plant (RFP) pursuant to the requirements of the Resource Conservation and Recovery Act (RCRA). This proposal would be known as a RCRA partial closure and would be accomplished by dewatering the ponds, where necessary, and converting any remaining sludge or evaporator concentrate to a solid wasteform (pondcrete and saltcrete). The pond sites would be stabilized to prevent erosion or other disturbance to the soil and to prevent infiltration of rain or snowmelt. The solid wasteform would be transported offsite for disposal. The five solar ponds (designated 207-A, 207-B (north, center, and south), and 207-C), are the only solar evaporation ponds that exist at the RFP. A finding of no significant impact is included

  4. Guide to ground water remediation at CERCLA response action and RCRA corrective action sites

    International Nuclear Information System (INIS)

    1995-10-01

    This Guide contains the regulatory and policy requirements governing remediation of ground water contaminated with hazardous waste [including radioactive mixed waste (RMW)], hazardous substances, or pollutants/contaminants that present (or may present) an imminent and substantial danger. It was prepared by the Office of Environmental Policy and Assistance, RCRA/CERCLA Division (EH-413), to assist Environmental Program Managers (ERPMs) who often encounter contaminated ground water during the performance of either response actions under CERCLA or corrective actions under Subtitle C of RCRA. The Guide begins with coverage of the regulatory and technical issues that are encountered by ERPM's after a CERCLA Preliminary Assessment/Site Investigation (PA/SI) or the RCRA Facility Assessment (RFA) have been completed and releases into the environment have been confirmed. It is based on the assumption that ground water contamination is present at the site, operable unit, solid waste management unit, or facility. The Guide's scope concludes with completion of the final RAs/corrective measures and a determination by the appropriate regulatory agencies that no further response action is necessary

  5. National RCRA Hazardous Waste Biennial Report Data Files

    Science.gov (United States)

    The United States Environmental Protection Agency (EPA), in cooperation with the States, biennially collects information regarding the generation, management, and final disposition of hazardous wastes regulated under the Resource Conservation and Recovery Act of 1976 (RCRA), as amended. Collection, validation and verification of the Biennial Report (BR) data is the responsibility of RCRA authorized states and EPA regions. EPA does not modify the data reported by the states or regions. Any questions regarding the information reported for a RCRA handler should be directed to the state agency or region responsible for the BR data collection. BR data are collected every other year (odd-numbered years) and submitted in the following year. The BR data are used to support regulatory activities and provide basic statistics and trend of hazardous waste generation and management. BR data is available to the public through 3 mechanisms. 1. The RCRAInfo website includes data collected from 2001 to present-day (https://rcrainfo.epa.gov/rcrainfoweb/action/main-menu/view). Users of the RCRAInfo website can run queries and output reports for different data collection years at this site. All BR data collected from 2001 to present-day is stored in RCRAInfo, and is accessible through this website. 2. An FTP site allows users to access BR data files collected from 1999 - present day (ftp://ftp.epa.gov/rcrainfodata/). Zip files are available for download directly from this

  6. Determining how much mixed waste will require disposal

    International Nuclear Information System (INIS)

    Kirner, N.P.

    1990-01-01

    Estimating needed mixed-waste disposal capacity to 1995 and beyond is an essential element in the safe management of low-level radioactive waste disposal capacity. Information on the types and quantities of mixed waste generated is needed by industry to allow development of treatment facilities and by states and others responsible for disposal and storage of this type of low-level radioactive waste. The design of a mixed waste disposal facility hinges on a detailed assessment of the types and quantities of mixed waste that will ultimately require land disposal. Although traditional liquid scintillation counting fluids using toluene and xylene are clearly recognized as mixed waste, characterization of other types of mixed waste has, however, been difficult. Liquid scintillation counting fluids comprise most of the mixed waste generated and this type of mixed waste is generally incinerated under the supplemental fuel provisions of the Resource Conservation and Recovery Act (RCRA) Because there are no Currently operating mixed waste land disposal facilities, it is impossible to make projections of waste requiring land disposal based on a continuation of current waste disposal practices. Evidence indicates the volume of mixed waste requiring land disposal is not large, since generators are apparently storing these wastes. Surveys conducted to date confirm that relatively small volumes of commercially generated mixed waste volume have relied heavily oil generators' knowledge of their wastes. Evidence exists that many generators are confused by the differences between the Atomic Energy Act and the Resource Conservation and Recovery Act (RCRA) on the issue of when a material becomes a waste. In spite of uncertainties, estimates of waste volumes requiring disposal can be made. This paper proposes an eight-step process for such estimates

  7. When RCRA meets ALARA

    International Nuclear Information System (INIS)

    Kirner, N.P.

    1990-01-01

    This paper proposes a method to identify an inconsistency between RCRA and AEA and for distinguishing a true inconsistency from a compliance difficulty. The paper also provides examples of each situation, accommodating specific RCRA requirements to maintain adherence to radiation protection requirements. The proposed method is derived from radiation protection guidance to Federal agencies for occupational exposure that was issued by EPA, under authority derived from Executive Order 10831, the AEA, and Reorganization Plan No. 3 of 1970. This EPA guidance was approved by President Reagan on January 20, 1987 and closely reflects the guidance of national and international radiation standard-setting groups

  8. CERCLA and RCRA requirements affecting cleanup of a hazardous waste management unit at a Superfund site: A case study

    International Nuclear Information System (INIS)

    Walsh, T.J.

    1995-03-01

    The Fernald Environmental Management Project (FEMP) attempted to address both RCRA and CERCLA requirements at the fire training facility (FTF) by integrating a CERCLA removal action work plan with a RCRA closure plan. While the regulatory agencies involved with the FTF cleanup agreed the integrated document was a good idea, implementation proved complicated, owing to disposition of clean debris from a Superfund site, treatment of contaminated media, duration of cleanup activities, and cleanup certification. While all the complications have not been resolved, solutions to all have been proposed to Ohio EPA and U.S. EPA. Both agencies have worked closely with FEMP to find the most effective fulfillment of RCRA and CERCLA requirements

  9. Waste management and the land disposal restriction storage prohibition

    International Nuclear Information System (INIS)

    1992-05-01

    RCRA Sect. 3004(j) prohibits storage of wastes that have been prohibited from land disposal, unless that storage is for the purpose of accumulating sufficient quantities of hazardous wastes to facilitate proper recovery, treatment, or disposal. This requirement was incorporated as part of the Land Disposal Restriction (LDR) regulations. Under the LDR storage prohibition, facilities may only store restricted wastes in containers and tanks. As stated in the Third LDR rule, storage of prohibited waste is only allowed in non-land based storage units since land-based storage is a form of disposal. The EPA has recognized that generators and storers of radioactive mixed waste (RMW) may find it impossible to comply with storage prohibition in cases where no available treatment capacity exists. Additionally, under the current regulatory interpretation, there is no provision that would allow for storage of wastes for which treatment capacity and capability are not available, even where capacity is legitimately being developed. Under the LDR program, restricted wastes that are disposed of, or placed into storage before an LDR effective date, are not subject to the LDR requirements. However, if such wastes are removed from a storage or disposal site after the effective date, such wastes would be subject to LDR requirements. The purpose of this information brief is to clarify what waste management practices constitute removal from storage

  10. Environmental restoration disposal facility applicable or relevant and appropriate requirements study report. Revision 00

    International Nuclear Information System (INIS)

    Roeck, F.V.; Vedder, B.L.; Rugg, J.E.

    1995-10-01

    The Environmental Restoration Disposal Facility (ERDF) will be a landfill authorized under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and will comply with the Resource Conservation and Recovery Act of 1976 (RCRA) substantive requirements. The facility will also comply with applicable or relevant and appropriate requirements (ARAR), including portions of the U.S. Environmental Protection Agency (EPA) regulations, Washington Administrative Code (WAC), and to-be-considered (TBC) elements such as U.S. Department of Energy (DOE) Orders. In considering the requirements of CERCLA, a detailed analysis of various alternatives for ERDF was completed using the nine CERCLA criteria, National Environmental Policy Act of 1969 (NEPA), and public comments. The ERDF record of decision (ROD) selected an alternative that includes a RCRA-compliant double-lined trench for the disposal of radioactive, hazardous, and mixed wastes resulting from the remediation of operable units (OU) within the National Priorities List (NPL) sites in the 100, 200, and 300 Areas. Only wastes resulting from the remediation of Hanford NPL sites will be allowed in the ERDF. Of the various siting and design alternatives proposed for ERDF, the selected alternative provides the best combination of features by balancing the nine CERCLA criteria, ARAR compliance, environmentally protective site, and various stakeholder and public recommendations. The ERDF trench design, compliant with RCRA Subtitle C minimum technical requirements (MTR), will be double lined and equipped with a leachate collection system. This design provides a more reliable system to protect groundwater than other proposed alternatives. The ERDF is located on the Hanford Site Central Plateau, southeast of the 200 West Area

  11. Superfund TIO videos: Set C. Land disposal restrictions. Part 3. Audio-Visual

    International Nuclear Information System (INIS)

    1990-01-01

    The videotape discusses the fundamental requirements of the Land Disposal Restrictions (LDRs) under RCRA, methods for determining whether LDRs are applicable or relevant and appropriate requirements for a CERCLA response, and LDR compliance options

  12. RCRA permit modifications and the functional equivalency demonstration: A case study

    International Nuclear Information System (INIS)

    Kinker, J.; Lyon, W.; Carnes, R.; Loehr, C.; Elsberry, K.; Garcia, P.

    1996-01-01

    Hazardous waste operating permits issued under the Resource Conservation and Recovery Act (RCRA) often impose requirements, typically by reference to the original permit application, that specific components and equipment be used. Consequently, changing these items, even for the purpose of routine maintenance, may first require that the owner/operator request a potentially time-consuming and costly permit modification. However, the owner/operator may demonstrate that a modification is not required because the planned changes are functionally equivalent, as defined by RCRA, to the original specifications embodied by the permit. The Controlled-Air Incinerator at Los Alamos National Laboratory is scheduled for maintenance and improvements that involve replacement of components. The incinerator's carbon adsorption unit/high efficiency particulate air filtration system, in particular, was redesigned to improve reliability and minimize maintenance. A study was performed to determine whether the redesigned unit would qualify as functionally equivalent to the original component. in performing this study, the following steps were taken: (a) the key performance factors were identified; (b) performance data describing the existing unit were obtained; (c) performance of both the existing and redesigned units was simulated; and (d) the performance data were compared to ascertain whether the components could qualify as functionally equivalent

  13. Ground Water Monitoring Requirements for Hazardous Waste Treatment, Storage and Disposal Facilities

    Science.gov (United States)

    The groundwater monitoring requirements for hazardous waste treatment, storage and disposal facilities (TSDFs) are just one aspect of the Resource Conservation and Recovery Act (RCRA) hazardous waste management strategy for protecting human health and the

  14. RCRA Facility Investigation/Remedial Investigation Report for the Gunsite 113 Access Road Unit (631-24G) - March 1996

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1996-03-01

    Gunsite 113 Access Road Unit is located in the northeast corner of SRS. In the mid 1980`s, sparse vegetation, dead trees, and small mounds of soil were discovered on a portion of the road leading to Gunsite 113. This area became the Gunsite 113 Access Road Unit (Gunsite 113). The unit appears to have been used as a spoil dirt and / or road construction debris disposal area. There is no documentation or record of any hazardous substance management, disposal, or any type of waste disposal at this unit. Based upon the available evidence, there are no potential contaminants of concern available for evaluation by a CERCLA baseline risk assessment. Therefore, there is no determinable health risk associated with Gunsite 113. In addition, it is also reasonable to conclude that, since contamination is below risk-based levels, the unit presents no significant ecological risk. It is recommended that no further remedial action be performed at this unit.

  15. RCRA Facility Investigation/Remedial Investigation Report for the Gunsite 113 Access Road Unit (631-24G) - March 1996

    International Nuclear Information System (INIS)

    Palmer, E.

    1996-03-01

    Gunsite 113 Access Road Unit is located in the northeast corner of SRS. In the mid 1980's, sparse vegetation, dead trees, and small mounds of soil were discovered on a portion of the road leading to Gunsite 113. This area became the Gunsite 113 Access Road Unit (Gunsite 113). The unit appears to have been used as a spoil dirt and / or road construction debris disposal area. There is no documentation or record of any hazardous substance management, disposal, or any type of waste disposal at this unit. Based upon the available evidence, there are no potential contaminants of concern available for evaluation by a CERCLA baseline risk assessment. Therefore, there is no determinable health risk associated with Gunsite 113. In addition, it is also reasonable to conclude that, since contamination is below risk-based levels, the unit presents no significant ecological risk. It is recommended that no further remedial action be performed at this unit

  16. Quarterly report of RCRA groundwater monitoring data for period October 1 through December 31, 1994

    International Nuclear Information System (INIS)

    1995-04-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and open-quotes Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilitiesclose quotes (Title 40 Code of Federal Regulations [CFR] Part 265), as amended. Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. The location of each facility is shown. Westinghouse Hanford Company (WHC) manages the RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Performing project management, preparing groundwater monitoring plans, well network design and installation, specifying groundwater data needs, performing quality control (QC) oversight, data management, and preparing project sampling schedules are all parts of this responsibility. Pacific Northwest Laboratory (PNL) administers the contract for analytical services and provides groundwater sampling services to WHC for the RCRA groundwater monitoring program. This quarterly report contains data received between October and December 1994, which are the cutoff dates for this reporting period. This report may contain not only data from the October through December quarter, but also data from earlier sampling events that were not previously reported

  17. Low-level radioactive waste disposal technologies used outside the United States

    International Nuclear Information System (INIS)

    Templeton, K.J.; Mitchell, S.J.; Molton, P.M.; Leigh, I.W.

    1994-01-01

    Low-level radioactive waste (LLW) disposal technologies are an integral part of the waste management process. In the United States, commercial LLW disposal is the responsibility of the State or groups of States (compact regions). The United States defines LLW as all radioactive waste that is not classified as spent nuclear fuel, high- level radioactive waste, transuranic waste, or by-product material as defined in Section II(e)(2) of the Atomic Energy Act. LLW may contain some long-lived components in very low concentrations. Countries outside the United States, however, may define LLW differently and may use different disposal technologies. This paper outlines the LLW disposal technologies that are planned or being used in Canada, China, Finland, France, Germany, Japan, Sweden, Taiwan, and the United Kingdom (UK)

  18. Evaluating pharmaceutical waste disposal in pediatric units.

    Science.gov (United States)

    Almeida, Maria Angélica Randoli de; Wilson, Ana Maria Miranda Martins; Peterlini, Maria Angélica Sorgini

    2016-01-01

    To verify the disposal of pharmaceutical waste performed in pediatric units. A descriptive and observational study conducted in a university hospital. The convenience sample consisted of pharmaceuticals discarded during the study period. Handling and disposal during preparation and administration were observed. Data collection took place at pre-established times and was performed using a pre-validated instrument. 356 drugs disposals were identified (35.1% in the clinic, 31.8% in the intensive care unit, 23.8% in the surgical unit and 9.3% in the infectious diseases unit). The most discarded pharmacological classes were: 22.7% antimicrobials, 14.8% electrolytes, 14.6% analgesics/pain killers, 9.5% diuretics and 6.7% antiulcer agents. The most used means for disposal were: sharps' disposable box with a yellow bag (30.8%), sink drain (28.9%), sharps' box with orange bag (14.3%), and infectious waste/bin with a white bag (10.1%). No disposal was identified after drug administration. A discussion of measures that can contribute to reducing (healthcare) waste volume with the intention of engaging reflective team performance and proper disposal is necessary. Verificar o descarte dos resíduos de medicamentos realizado em unidades pediátricas. Estudo descritivo e observacional, realizado em um hospital universitário. A amostra de conveniência foi constituída pelos medicamentos descartados durante o período de estudo. Observaram-se a manipulação e o descarte durante o preparo e a administração. A coleta dos dados ocorreu em horários preestabelecidos e realizada por meio de instrumento pré-validado. Identificaram-se 356 descartes de medicamentos (35,1% na clínica, 31,8% na unidade de cuidados intensivos, 23,8% na cirúrgica e 9,3% na infectologia). As classes farmacológicas mais descartadas foram: 22,7% antimicrobianos, 14,8% eletrólitos, 14,6% analgésicos, 9,5% diuréticos e 6,7% antiulcerosos. Vias mais utilizadas: caixa descartável para perfurocortante com

  19. Accelerating RCRA corrective action: The principles of the DOE approach

    International Nuclear Information System (INIS)

    Kimmell, T.A.; Green, D.R.; Ranek, N.L.; Coalgate, J.L.

    1995-01-01

    The US Department of Energy (DOE) is involved in the remediation of environmental contamination at many of its facilities under the Resource Conservation and Recovery Act (RCRA). RCRA's corrective action provisions were established by the Hazardous and Solid Waste Amendments of 1984 (HSWA). In response to the HSWA mandate, EPA established a program for the conduct of RCRA corrective action that was similar to that established under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). In addition, EPA developed and implemented its ''stabilization'' initiative as a means of quickly addressing immediate risks posed by releases until long term solutions can be applied. To improve the efficiency of environmental restoration at its facilities, DOE is developing guidance and training programs on accelerated environmental restoration under RCRA. A RCRA guidance document, entitled ''Accelerating RCRA Corrective Action at DOE Facilities,'' is currently being developed by DOE's Office of Environmental Policy and Assistance. The new guidance document will outline a decision-making process for determining if acceleration is appropriate for individual facilities, for identifying, evaluating, and selecting options for program acceleration, and for implementing selected acceleration options. The document will also discuss management and planning strategies that provide a firm foundation for accelerating RCRA corrective action. These strategies include a number of very basic principles that have proven effective at DOE and other federal facilities, as well as some new approaches. The purpose of this paper is to introduce DOE's new guidance document, discuss the general approach presented in the guidance for accelerating RCRA corrective action, and to emphasize some of the more important principles of effective management and planning

  20. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Corbus, D.

    1992-09-01

    Recycling and disposal of spent sodium-sulfur (Na/S) batteries are important issues that must be addressed as part of the commercialization process of Na/S battery-powered electric vehicles. The use of Na/S batteries in electric vehicles will result in significant environmental benefits, and the disposal of spent batteries should not detract from those benefits. In the United States, waste disposal is regulated under the Resource Conservation and Recovery Act (RCRA). Understanding these regulations will help in selecting recycling and disposal processes for Na/S batteries that are environmentally acceptable and cost effective. Treatment processes for spent Na/S battery wastes are in the beginning stages of development, so a final evaluation of the impact of RCRA regulations on these treatment processes is not possible. The objectives of tills report on battery recycling and disposal are as follows: Provide an overview of RCRA regulations and requirements as they apply to Na/S battery recycling and disposal so that battery developers can understand what is required of them to comply with these regulations; Analyze existing RCRA regulations for recycling and disposal and anticipated trends in these regulations and perform a preliminary regulatory analysis for potential battery disposal and recycling processes. This report assumes that long-term Na/S battery disposal processes will be capable of handling large quantities of spent batteries. The term disposal includes treatment processes that may incorporate recycling of battery constituents. The environmental regulations analyzed in this report are limited to US regulations. This report gives an overview of RCRA and discusses RCRA regulations governing Na/S battery disposal and a preliminary regulatory analysis for Na/S battery disposal.

  1. Annual report of 1995 groundwater monitoring data for the Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-02-01

    The Kerr Hollow Quarry (KHQ) and the Chestnut Ridge Sediment Disposal Basin (CRSDB) are inactive waste management sites located at the Oak Ridge Y-12 Plant. The KHQ and CRSDB are regulated as treatment, storage, or disposal (TSD) facilities under the Resource Conservation and Recovery Act (RCRA). The facilities were granted interim status in calendar year (CY) 1986 under Tennessee Department of Environment and Conservation (TDEC) Hazardous Waste Management Rule 1200-1-11-.05. Historical environmental monitoring data and baseline characterization under interim status indicated that releases of contaminants to groundwater had not occurred; thus, the detection monitoring was implemented at the sites until either clean closure was completed or post-closure permits were issued. The CRSDB was closed in Cy 1989 under a TDEC-approved RCRA closure plan. A revised RCRA PCPA for the CRSDB was submitted by DOE personnel to TDEC staff in September 1994. A final post-closure permit was issued by the TDEC on September 18, 1995. Closure activities at KHQ under RCRA were completed in October 1993. The Record of Decision will also incorporate requirements of the RCRA post-closure permit once it is issued by the TDEC

  2. Quarterly report of RCRA groundwater monitoring data for period April 1 through June 30, 1994

    International Nuclear Information System (INIS)

    1994-10-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and ''Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities,'' as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. Westinghouse Hanford Company manages RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Project management, specifying data needs, performing quality control oversight, managing data, and preparing project sampling schedules are all parts of this responsibility. This quarterly report contains data received between May 20 and August 19, 1994, which are the cutoff dates for this reporting period. This report may contain not only data from the April through June quarter but also data from earlier sampling events that were not previously reported

  3. Establishing a regulatory framework for a RCRA corrective action program

    International Nuclear Information System (INIS)

    Krueger, J.W.

    1989-01-01

    Recently, the environmental community has become keenly aware of problems associated with integration of the demanding regulations that apply to environmental restoration activities. Once can not attend an EPA-sponsored conference on Superfund without hearing questions concerning the Resource, Conservation, and Recovery Act (RCRA) and the applicability of the National Contingency Plan (NCP) to sites that do not qualify for the National Priorities List (NPL). In particular, the U.S. Department of Energy (DOE) has been greatly criticized for its inability to define a comprehensive approach for cleaning up its hazardous waste sites. This article presents two decision flowcharts designed to resolve some of this confusion for DOE. The RCRA/CERCLA integration diagram can help the environmental manager determine which law applies and under what conditions, and the RCRA corrective action decision flowchart can guide the manager in determining which specific sections of RCRA apply to a RCRA-lead environmental restoration program

  4. Low temperature setting iron phosphate ceramics as a stabilization and solidification agent for incinerator ash contaminated with transuranic and RCRA metals

    International Nuclear Information System (INIS)

    Medvedev, P.G.; Hansen, M.; Wood, E.L.; Frank, S.M.; Sidwell, R.W.; Giglio, J.J.; Johnson, S.G.; Macheret, J.

    1997-01-01

    Incineration of combustible Mixed Transuranic Waste yields an ash residue that contains oxides of Resource Conservation and Recovery Act (RCRA) and transuranic metals. In order to dispose of this ash safely, it has to be solidified and stabilized to satisfy appropriate requirements for repository disposal. This paper describes a new method for solidification of incinerator ash, using room temperature setting iron phosphate ceramics, and includes fabrication procedures for these waste forms as well as results of the MCC-1 static leach test, XRD analysis, scanning electron microscopy studies and density measurements of the solidified waste form produced

  5. NGLW RCRA Storage Study

    International Nuclear Information System (INIS)

    Waters, R.J.; Ochoa, R.; Fritz, K.D.; Craig, D.W.

    2000-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory contains radioactive liquid waste in underground storage tanks at the INTEC Tank Farm Facility (TFF). INTEC is currently treating the waste by evaporation to reduce the liquid volume for continued storage, and by calcination to reduce and convert the liquid to a dry waste form for long-term storage in calcine bins. Both treatment methods and activities in support of those treatment operations result in Newly Generated Liquid Waste (NGLW) being sent to TFF. The storage tanks in the TFF are underground, contained in concrete vaults with instrumentation, piping, transfer jets, and managed sumps in case of any liquid accumulation in the vault. The configuration of these tanks is such that Resource Conservation and Recovery Act (RCRA) regulations apply. The TFF tanks were assessed several years ago with respect to the RCRA regulations and they were found to be deficient. This study considers the configuration of the current tanks and the RCRA deficiencies identified for each. The study identifies four potential methods and proposes a means of correcting the deficiencies. The cost estimates included in the study account for construction cost; construction methods to minimize work exposure to chemical hazards, radioactive contamination, and ionizing radiation hazards; project logistics; and project schedule. The study also estimates the tank volumes benefit associated with each corrective action to support TFF liquid waste management planning

  6. NGLW RCRA Storage Study

    Energy Technology Data Exchange (ETDEWEB)

    R. J. Waters; R. Ochoa; K. D. Fritz; D. W. Craig

    2000-06-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory contains radioactive liquid waste in underground storage tanks at the INTEC Tank Farm Facility (TFF). INTEC is currently treating the waste by evaporation to reduce the liquid volume for continued storage, and by calcination to reduce and convert the liquid to a dry waste form for long-term storage in calcine bins. Both treatment methods and activities in support of those treatment operations result in Newly Generated Liquid Waste (NGLW) being sent to TFF. The storage tanks in the TFF are underground, contained in concrete vaults with instrumentation, piping, transfer jets, and managed sumps in case of any liquid accumulation in the vault. The configuration of these tanks is such that Resource Conservation and Recovery Act (RCRA) regulations apply. The TFF tanks were assessed several years ago with respect to the RCRA regulations and they were found to be deficient. This study considers the configuration of the current tanks and the RCRA deficiencies identified for each. The study identifies four potential methods and proposes a means of correcting the deficiencies. The cost estimates included in the study account for construction cost; construction methods to minimize work exposure to chemical hazards, radioactive contamination, and ionizing radiation hazards; project logistics; and project schedule. The study also estimates the tank volumes benefit associated with each corrective action to support TFF liquid waste management planning.

  7. 78 FR 65390 - Exemption From Licensing for Disposal of Low-Activity Radioactive Waste at the US Ecology Idaho...

    Science.gov (United States)

    2013-10-31

    ... Disposal of Low-Activity Radioactive Waste at the US Ecology Idaho Resource Conservation and Recovery Act..., Pennsylvania, at the US Ecology Idaho (USEI) Resource Conservation and Recovery Act (RCRA) Subtitle C disposal... from the US Ecology, Inc. (US Ecology), dated July 7, 2013 (ADAMS Accession No. ML13198A017), for...

  8. Remedial investigation/feasibility study work plan for the 100-KR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-07-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Figure 1-1 shows the location of these areas. Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-KR-1 operable unit. The 100-KR-1 source operable unit is one of three source operable units in the 100-K Area. Source operable units include facilities and unplanned release sites that are potential sources of hazardous substance contamination

  9. The disposal of redundant teletherapy units from NHS hospitals

    International Nuclear Information System (INIS)

    Gaffka, A.P.; Ord, M.A.

    1994-01-01

    The removal/disposal of redundant teletherapy units from NHS hospitals is described, detailing the operational procedures and the transport package background. The Harwell section of the Transport Technology Department has been carrying out these operations since 1991, where initially the service was just offered to the NHS; however, today their specialist transport service has significantly widened and is now offered to other business sectors. Due to the level of radioactivity found in each teletherapy unit, it was necessary to design a special transport packaging to meet the requirements for shipment of these units. Approval was sought from the Department of Transport to adapt a standard Type B package as no other packaging could be found to comply with the necessary requirements. All work undertaken on the removal and disposal of these units complied with an approved scheme of work and was carried out in accordance with a Quality Assurance workplan. However, to keep abreast of modern standards in a manner which is cost effective to customers and acceptable to the general public, the full development of a new Type B packaging is taking place, which is specifically designed to undertake these removal/disposal duties. (author)

  10. Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

    International Nuclear Information System (INIS)

    Bell, J.T.; Haas, P.A.; Rudolph, J.C.

    1995-01-01

    The Oak Ridge National Laboratory (ORNL) is participating in a program to apply a molten salt oxidation (MSO) process to treatment of mixed (radioactive and RCRA) wastes. The salt residues from the MSO treatment will require further separations or other processing to prepare them for final disposal. A bench-scale MSO apparatus is being installed at ORNL and will be operated on real Oak Ridge wastes. The treatment concepts to be tested and demonstrated on the salt residues from real wastes are described

  11. Remedial investigation/feasibility study work plan for the 100-BC-5 Operable Unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-04-01

    Four areas of the Hanford Site (the 100, 200, 300 and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Figure 1-1 shows the location of these areas. Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plant and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-BC-5 operable unit. The 100-B/C Area consists of the 100-BC-5 groundwater operable unit and four source operable units. The 100-BC-5 operable unit includes all contamination found in the aquifer soils and water beneath the 100-B/C Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination

  12. Source term analysis for a RCRA mixed waste disposal facility

    International Nuclear Information System (INIS)

    Jordan, D.L.; Blandford, T.N.; MacKinnon, R.J.

    1996-01-01

    A Monte Carlo transport scheme was used to estimate the source strength resulting from potential releases from a mixed waste disposal facility. Infiltration rates were estimated using the HELP code, and transport through the facility was modeled using the DUST code, linked to a Monte Carlo driver

  13. Rocky Flats Solar Evaporation Ponds RCRA hybrid-closure case study

    International Nuclear Information System (INIS)

    Ogg, R.T.; Everett, L.G.; Cullen, S.J.

    1994-01-01

    The Solar Evaporation Ponds (SEP)/Operable Unit 4 (OU 4), located at the Rocky Flats Plant (RFP) sixteen miles northwest of Denver, Colorado, is currently undergoing remediation/Resource Conservation and Recovery Act (RCRA) closure in accordance with the Rocky Flats Interagency Agreement (IAG) signed by the US Department of Energy (DOE), US Environmental Protection Agency (EPA) and Colorado Department of Health (CDH) on January 22, 1991. Based on the ''Phase 1'' (source and soils) RCRA Facility Investigation/Remedial Investigation (RFM data and interpretations), the DOE and EG and G Rocky Flats, Inc. (EG and G) have selected a permanent surface engineered/isolation barrier as the technological option for remediation of the SEP. The DOE and EG and G will utilize all natural materials to create an ''impermeable'' barrier/structure to isolate the waste being left in place from impacting human health and the environment for a minimum of 1,000 years. Their rationale for utilizing natural materials is two fold; (1) optimize long term performance of the barrier and; (2) design a structure which will be near maintenance free (passive remediation) for 1,000 years. The DOE and EG and G have taken a proactive approach in providing post closure performance assessment for this RCRA closure action. An integrated monitoring system has been designed which will include monitoring the engineered barrier, vadose zone and ground water systems. Rocky Flats will integrate instrumentation into the permanent engineered barrier which will provide early warning of potential liquid migration through the barrier and into the waste zone

  14. Impacts of proposed RCRA regulations and other related federal environmental regulations on fossil fuel-fired facilities: Final report, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    Estimation of the costs associated with implementation of the Resource Conservation and Recovery Act (RCRA) regulations for non-hazardous and hazardous material disposal in the utility industry are provided. These costs are based on engineering studies at a number of coal-fired power plants in which the costs for hazardous and non-hazardous disposal are compared to the costs developed for the current practice design for each utility. The relationship of the three costs is displayed. The emphasis of this study is on the determination of incremental costs rather than the absolute costs for each case (current practice, non-hazardous, or hazardous). For the purpose of this project, the hazardous design cost was determined for minimum versus maximum compliance.

  15. Hazardous Waste/IGD: EF_RCRA

    Data.gov (United States)

    U.S. Environmental Protection Agency — EF_RCRA is a subset of facilities from FRS_INTEREST and FRS_FACILITY_SITE which are updated on a monthly basis as part of the Locational Reference Tables (LRT)...

  16. The relationship between the Resource Conservation and Recovery Act and the storage and disposal of spent nuclear fuel and high-level waste

    International Nuclear Information System (INIS)

    Gertz, C.P.; Cloke, P.L.

    1993-01-01

    This paper addresses the potential applicability of the requirements of the Resource Conservation and Recovery Act (RCRA) to the disposal of spent commercial nuclear fuel and of high-level (vitrified) radioactive waste. The Atomic Energy Act of 1954, as amended, and the associated regulations issued by the US NRC provides many requirements that apply to these waste forms and largely, if not entirely, pre-empts the applicability of RCRA. The RCRA would apply only to the non-radioactive components of these wastes, and then only in respect to hazardous components. In view of these restrictions it becomes important to evaluate whether any components of spent fuel or high-level waste are toxic, as defined by the RCRA regulations. Present indications are that they are not and, hence, the US DOE is proceeding on the basis that these wastes and others that may be generated in the future are non-hazardous in respect to RCRA definitions

  17. EPA R1 RCRA Corrective Action 2020 Baseline Site Property Boundaries

    Data.gov (United States)

    U.S. Environmental Protection Agency — Property boundaries as indicated in figures of all facilities subject to RCRA Corrective Action on the 2020 baseline in Region 1. For more information on the RCRA...

  18. Hazardous waste landfill research: U. S. E. P. A. (United States Environmental Protection Agency) Program

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.

    1984-06-01

    The hazardous waste land disposal research program is collecting data necessary to support implementation of disposal guidelines mandated by the 'Resource Conservation and Recovery Act of 1976' (RCRA) PL 94-580. This program relating to the categorical areas of landfills, surface impoundments, and underground mines encompasses state-of-the-art documents, laboratory analysis, economic assessment, bench and pilot studies, and full-scale field verification studies. Over the next five years the research will be reported as Technical Resource Documents in support of the RCRA Guidance Documents. These documents will be used to provide guidance for conducting the review and evaluation of land disposal permit applications. This paper will present an overview of this program and will report the current status of the work.

  19. Quarterly RCRA Groundwater Monitoring Data for the Period July through September 2006

    Energy Technology Data Exchange (ETDEWEB)

    Hartman, Mary J.

    2007-02-01

    This report provides information about RCRA groundwater monitoring for the period July through September 2006. Eighteen Resource Conservation and Recovery Act (RCRA) sites were sampled during the reporting quarter.

  20. RCRA groundwater data analysis protocol for the Hanford Site, Washington

    International Nuclear Information System (INIS)

    Chou, C.J.; Jackson, R.L.

    1992-04-01

    The Resource Conservation and Recovery Act of 1976 (RCRA) groundwater monitoring program currently involves site-specific monitoring of 20 facilities on the Hanford Site in southeastern Washington. The RCRA groundwater monitoring program has collected abundant data on groundwater quality. These data are used to assess the impact of a facility on groundwater quality or whether remediation efforts under RCRA corrective action programs are effective. Both evaluations rely on statistical analysis of groundwater monitoring data. The need for information on groundwater quality by regulators and environmental managers makes statistical analysis of monitoring data an important part of RCRA groundwater monitoring programs. The complexity of groundwater monitoring programs and variabilities (spatial, temporal, and analytical) exhibited in groundwater quality variables indicate the need for a data analysis protocol to guide statistical analysis. A data analysis protocol was developed from the perspective of addressing regulatory requirements, data quality, and management information needs. This data analysis protocol contains four elements: data handling methods; graphical evaluation techniques; statistical tests for trend, central tendency, and excursion analysis; and reporting procedures for presenting results to users

  1. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site's potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed

  2. EXAMPLE OF A RISK-BASED DISPOSAL APPROVAL: SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE

    International Nuclear Information System (INIS)

    PRIGNANO AL

    2007-01-01

    The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26,2005 to June 9,2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP

  3. Current researches on safety assessment of radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Tasaka, Hiroshi; Kiyose, Ryohei

    1980-01-01

    Recently, the problem of safe disposal of radioactive waste generated from nuclear fuel cycle becomes more important in Japan. On the other hand, many researches on shallow land burial of low-level wastes and geologic isolation of high-level wastes have been carried out in the United States of America. In this report, the researches on the safety assessment of radioactive waste disposal in the United States of America were briefly introduced with emphasis on the studies on behavior and migration of radionuclide from disposed waste in geosphere. (author)

  4. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention

  5. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL`s assessment of the need for further remedial attention.

  6. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention.

  7. Closure of hazardous and mixed radioactive waste management units at DOE facilities

    International Nuclear Information System (INIS)

    1990-06-01

    This is document addresses the Federal regulations governing the closure of hazardous and mixed waste units subject to Resource Conservation and Recovery Act (RCRA) requirements. It provides a brief overview of the RCRA permitting program and the extensive RCRA facility design and operating standards. It provides detailed guidance on the procedural requirements for closure and post-closure care of hazardous and mixed waste management units, including guidance on the preparation of closure and post-closure plans that must be submitted with facility permit applications. This document also provides guidance on technical activities that must be conducted both during and after closure of each of the following hazardous waste management units regulated under RCRA

  8. Financial responsibilities under RCRA. Hearing before the Subcommittee on Commerce, Transportation, and Tourism of the Committee on Energy and Commerce, House of Representatives, Ninety-Ninth Congress, First Session on H. R. 3692, November 13, 1985

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    Representatives of environmental organizations, the Hazardous Waste Treatment Council, and regulators were among those testifying at a hearing on H.R. 3692, which amends the Resource Conservation and Recovery Act (RCRA) of 1976. The bill is in response to concerns that the Environmental Protection Agency (EPA) has not compiled with the intent of RCRA in its failure to move beyond interim permits to issue final permits to land disposal facilities accepting hazardous wastes. Reported leakage and environmental risks from sites operating under interim permits raises questions about how disposal companies could deal with liability claims. At issue was whether Congress needs to take new action to develop regulations under which financially responsible companies can operate or whether new EPA rules can solve the problem. A spokesman for EPA reviewed the liability insurance problem and the status of the insurance market in this context. Material submitted for the record follows the text of H.R. 3692 and the testimony of 11 witnesses.

  9. Zero air emission and zero drilling waste landfill leachate collection well installation method

    International Nuclear Information System (INIS)

    Miller, M.S.; Hornsby, R.G.

    1992-01-01

    Landfilling of industrial wastes is an extensively used means of disposal throughout the US. Prior to RCRA, many landfills were little more than excavated trenches. During the construction and filling of such trenches, the long-term environmental impact was seldom considered. Water (leachate) management for these early landfills was not part of engineering or operating considerations. Today, waste management facilities succeed or fail on the quality of their leachate management efforts, as judged by groundwater quality around the landfill. The CECOS International Inc. facility near Livingston, Louisiana has three pre-RCRA disposal units (landfills) that were designed, constructed, and closed by a previous owner. These disposal units were constructed without any type of leachate removal system. During 1984-1985, samples from two nearby monitor wells revealed evidence of groundwater contamination in the area, principally in the shallow (30-foot) zone. A one-year, state-approved groundwater assessment revealed the nature and extent of groundwater contamination. Later, the Louisiana Department of Environmental Quality (LDEQ) approved a remedial action plan (RAP) for this area that included: Installation of an engineered slurry wall surrounding the disposal units to isolate the shallow groundwater regime. Placement of an engineered cap over the units to prevent rainwater infiltration. Installation of several recovery wells inside the units to facilitate removal of leachate. While efforts are now underway to provide for removal of impacted groundwater in the vicinity of these old wells, the long-term solution is to reduce or, to the greatest extent possible, eliminate the liquid volume inside the cells. This paper deals with the installation of 16 leachate recovery wells inside the pre-RCRA disposal units

  10. Evaluation of Landfill Cover Design Options for Waste Disposal Sites in the Coastal Regions of Ghana

    Directory of Open Access Journals (Sweden)

    Kodwo Beedu Keelson

    2015-01-01

    Full Text Available Uncontrolled leachate generation from operational and closed waste disposal sites is a major environmental concern in the coastal regions of Ghana which have abundant surface water and groundwater resources. The Ghana Landfill Guidelines requires the provision of a final cover or capping system as part of a final closure plan for waste disposal sites in the country as a means of minimizing the harmful environmental effects of these emissions. However, this technical manual does not provide explicit guidance on the material types or configuration for landfill covers that would be suitable for the different climatic conditions in the country. Four landfill cover options which are based on the USEPA RCRA-type and evapotranspirative landfill cover design specifications were evaluated with the aid of the HELP computer program to determine their suitability for waste disposal sites located in the Western, Central and Greater Accra regions. The RCRA Subtitle C cover which yielded flux rates of less than 0.001 mm/yr was found to be suitable for the specific climatic conditions. The RCRA Subtitle D cover was determined to be unsuitable due to the production of very large flux rates in excess of 200 mm/yr. The results for the anisotropic barrier and capillary barrier covers were inconclusive. Recommendations for further study include a longer simulation period as well the study of the combined effects of different topsoil vegetative conditions and evaporative zone depths on the landfill water balance. The use of other water balance models such as EPIC, HYDRUS-2D and UNSAT-H for the evaluation of the evapotranspirative landfill cover design options should also be considered.

  11. Notification: EPA Progress on Meeting Resource Conservation and Recovery Act Statutory Mandate for Minimum Frequency of Inspections at Hazardous Waste Disposal Facilities

    Science.gov (United States)

    Project #OPE-FY15-0018, January 20, 2015. The EPA OIG plans to begin preliminary research on EPA’s progress in meeting minimum inspection requirements under the RCRA at treatment, storage and disposal facilities (TSDFs).

  12. A review of the disposal of miscellaneous radioactive wastes in the United Kingdom

    International Nuclear Information System (INIS)

    Hookway, B.

    1980-01-01

    Current practices in the United Kingdom for waste disposal from ''minor users'' of radioactive materials are reviewed. The regulation of the disposal of solid, liquid and airborne wastes is discussed. (H.K.)

  13. Project report for the commercial disposal of mixed low-level waste debris

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

    1994-05-01

    This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project.

  14. Project report for the commercial disposal of mixed low-level waste debris

    International Nuclear Information System (INIS)

    Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

    1994-05-01

    This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project

  15. Complying with Land Disposal Restrictions (LDR) for CERCLA remedial actions involving contaminated soil and debris

    International Nuclear Information System (INIS)

    Bascietto, J.

    1991-01-01

    CERCLA Sect. 121(e) requires that remedial actions must comply with at least the minimum standards of all ''applicable or relevant and appropriate requirements'' (ARARs) of federal and state laws. EPA has determined that RCRA land disposal restrictions may be ARAR for certain CERCLA remedial actions involving soil and debris. This means that soil and debris contaminated with prohibited or restricted wastes cannot be land disposed if (1) these wastes have not attained the treatment standards set by EPA for a specified waste or (2) have been the subject of a case-by-case extension, national capacity variance, or successful ''no migration'' petition. RCRA LDR treatment standards are based on ''Best Demonstrated Available Technology'' (BDAT), not on health-based concentrations. Because the treatment of the soil and debris matrix presents technological difficulties not yet addressed by EPA (BDAT standards are generally set for industrial process wastes), compliance options such as obtaining a Treatability Variance, are available and will generally be necessary for soil and debris wastes. In the recently promulgated revisions to the National Contingency Plan (NCP) for CERCLA implementation, EPA provides important information for CERCLA project managers regarding LDR compliance, particularly for obtaining a treatability variance for land disposal of contaminated soil and debris

  16. 40 CFR 257.5 - Disposal standards for owners/operators of non-municipal non-hazardous waste disposal units that...

    Science.gov (United States)

    2010-07-01

    ... compliance with §§ 257.7 through 257.30 prior to the receipt of CESQG hazardous waste. (b) Definitions.... Waste management unit boundary means a vertical surface located at the hydraulically downgradient limit.../operators of non-municipal non-hazardous waste disposal units that receive Conditionally Exempt Small...

  17. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    International Nuclear Information System (INIS)

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations

  18. Coordination of groundwater activities in the 100 N Area

    International Nuclear Information System (INIS)

    Hartman, M.J.

    1995-09-01

    The initiation of the N Springs Expedited Response Action (ERA) in the 100 N Area will affect the groundwater monitoring networks of two Resource Conservation and Recovery Act of 1976 (RCRA) units. The 1301-N and 325-N facilities are treatment, storage, or disposal (TSD) units that have been monitored under RCRA since 1987. In September 1994, the Washington State Department of Ecology issued an action memorandum, instructing the US Department of Energy (DOE) to take the action. The planned pump-and-treat system will preclude meeting the specific objectives of interim-status RCRA groundwater monitoring representative samples and detect adverse impacts of the TSD units on. However, under RCRA final-status requirements, which will be implemented in 1999, corrective action for groundwater contamination will probably be required. The US Environmental Protection Agency (EPA) has declared parity between RCRA corrective action and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 remedial action decisions. The 1301-N and 1325-N facilities are still in interim-status and therefore are not in the category of ''RCRA corrective action.'' However, DOE's position is that parity exists between RCRA and the ERA because RCRA corrective action will almost certainly be required in the future

  19. Evaluation on radioactive waste disposal amount of Kori Unit 1 reactor vessel considering cutting and packaging methods

    International Nuclear Information System (INIS)

    Choi, Yu Jong; Lee, Seong Cheol; Kim, Chang Lak

    2016-01-01

    Decommissioning of nuclear power plants has become a big issue in South Korea as some of the nuclear power plants in operation including Kori unit 1 and Wolsung unit 1 are getting old. Recently, Wolsung unit 1 received permission to continue operation while Kori unit 1 will shut down permanently in June 2017. With the consideration of segmentation method and disposal containers, this paper evaluated final disposal amount of radioactive waste generated from decommissioning of the reactor pressure vessel in Kori unit 1 which will be decommissioned as the first in South Korea. The evaluation results indicated that the final disposal amount from the top and bottom heads of the reactor pressure vessel with hemisphere shape decreased as they were cut in smaller more effectively than the cylindrical part of the reactor pressure vessel. It was also investigated that 200 L and 320 L radioactive waste disposal containers used in Kyung-Ju disposal facility had low payload efficiency because of loading weight limitation

  20. RCRA and CERCLA requirements affecting cleanup activities at a federal facility superfund site

    International Nuclear Information System (INIS)

    Walsh, T.J.

    1994-01-01

    The Fernald Environmental Management Project (FEMP) achieved success on an integrated groundwater monitoring program which addressed both RCRA and CERCLA requirements. The integrated plan resulted in a cost savings of approximately $2.6 million. At present, the FEMP is also working on an integrated closure process to address Hazardous Waste Management Units (HWMUs) at the site. To date, Ohio EPA seems willing to discuss an integrated program with some stipulations. If an integrated program is implemented, a cost savings of several million dollars will be realized since the CERCLA documents can be used in place of a RCRA closure plan. The success of an integrated program at the FEMP is impossible without the support of DOE and the regulators. Since DOE is an owner/operator of the facility and Ohio EPA regulates hazardous waste management activities at the FEMP, both parties must be satisfied with the proposed integration activities. Similarly, US EPA retains CERCLA authority over the site along with a signed consent agreement with DOE, which dictates the schedule of the CERCLA activities. Another federal facility used RCRA closure plans to satisfy CERCLA activities. This federal facility was in a different US EPA Region than the FEMP. While this approach was successful for this site, an integrated approach was required at the FEMP because of the signed Consent Agreement and Consent Decree. For federal facilities which have a large number of HWMUs along with OUs, an integrated approach may result in a timely and cost-effective cleanup

  1. Proposed modifications to the RCRA post-closure permit for the Chestnut Ridge Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Chestnut Ridge Hydrogeologic Regime (CRHR) (permit number TNHW-088, EPA ID No. TN3 89 009 0001). These permit conditions define the requirements for RCRA post-closure detection groundwater monitoring at the Chestnut Ridge Sediment Disposal Basin (CRSDB) and Kerr Hollow Quarry (KHQ), and RCRA post-closure corrective action groundwater monitoring at the Chestnut Ridge Security Pits (CRSPs). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring at the CRSPs with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) record of decision (ROD), (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA monitoring programs during 1996, (3) replace several of the technical procedures included in the PCP with updated versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP), and (4) correct inaccurate regulatory citations and references to permit conditions and permit attachments. With these modifications, the Y- 12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2 provides the technical justification for each proposed permit modification. Section 3.0 contains proposed changes to Section II of the PCP. Modifications to site-specific permit conditions are presented in Section 4.0 (CRSDB), Section 5.0 (CRSPs), and Section 6.0 (KHQ). Sections 7.0 and 8.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the permit attachments

  2. Proposed modifications to the RCRA post-closure permit for the Chestnut Ridge Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Chestnut Ridge Hydrogeologic Regime (CRHR) (permit number TNHW-088, EPA ID No. TN3 89 009 0001). These permit conditions define the requirements for RCRA post-closure detection groundwater monitoring at the Chestnut Ridge Sediment Disposal Basin (CRSDB) and Kerr Hollow Quarry (KHQ), and RCRA post-closure corrective action groundwater monitoring at the Chestnut Ridge Security Pits (CRSPs). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring at the CRSPs with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) record of decision (ROD), (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA monitoring programs during 1996, (3) replace several of the technical procedures included in the PCP with updated versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP), and (4) correct inaccurate regulatory citations and references to permit conditions and permit attachments. With these modifications, the Y- 12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2 provides the technical justification for each proposed permit modification. Section 3.0 contains proposed changes to Section II of the PCP. Modifications to site-specific permit conditions are presented in Section 4.0 (CRSDB), Section 5.0 (CRSPs), and Section 6.0 (KHQ). Sections 7.0 and 8.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the permit attachments.

  3. Decommissioning of a RCRA Treatment, Storage, and Disposal Facility: A case study of the 216-A-29 ditch at the Hanford Site

    International Nuclear Information System (INIS)

    Smith, D.L.; Hayward, W.M.

    1991-09-01

    The 216-A-29 ditch is located in the central portion of the Hanford Site with Operable Unit 200-PO-5. The ditch is classified under the Resource Conservation and Recovery Act of 1976 as a Treatment, Storage, and Disposal (TSD) Facility and as such, is to be removed from service in support of the Hanford Federal Facility Agreement and Consent Order Tri-Party Agreement (Ecology et al. 1989) Milestone M-17-10, which states ''cease all liquid discharges to hazardous land disposal units unless such units have been clean closed in accordance with the Resource Conservation and Recovery Act of 1976''. The 216-A-29 ditch is one stream feeding the 216-B-3 Pond system, and its removal from service was necessary to support the closure strategy for the 216-B-3 Pond system. Interim stabilization of the 216-A-29 ditch is the first step required to comply with the Tri-Party Agreement (Ecology et al. 1989) and the eventual decommissioning of the entire B Pond system. Interim stabilization was required to maintain the 216-A-29 ditch in a stable configuration until closure actions have been determined and initiated. 4 refs., 3 figs

  4. Quarterly RCRA Groundwater Monitoring Data for the Period April Through June 2006

    Energy Technology Data Exchange (ETDEWEB)

    Hartman, Mary J.

    2006-11-01

    This report provides information about RCRA groundwater monitoring for the period April through June 2006. Seventeen RCRA sites were sampled during the reporting quarter. Sampled sites include seven monitored under groundwater indicator evaluation (''detection'') programs, eight monitored under groundwater quality assessment programs, and two monitored under final-status programs.

  5. EPA seeks to make RCRA more effective through legislative changes

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Since RCRA was enacted in 1976 and amended in 1984, hazardous waste management has been transformed. To protect human health and the environment as mandated by the act, EPA has developed a complex cradle-to-grave system for managing hazardous waste. The agency recognizes that some targeted legislative changes could make RCRA even more useful, particularly by (1) establishing some open-quotes middle groundclose quotes for waste posing low risks, and (2) emphasizing sensible and enforceable hazardous waste management practices

  6. Role of disposal in developing Federal Facility Compliance Act mixed waste treatment plans

    International Nuclear Information System (INIS)

    Case, J.T.; Rhoderick, J.

    1994-01-01

    The Federal Facilities Compliance Act (FFCA) was enacted on October 6, 1992. This act amends the Solid Waste Disposal Act, which was previously amended by the Resource Conservation and Recovery Act (RCRA). The FFCA set in place a process for managing the Department of Energy's (DOE) mixed low-level radioactive wastes (MLLW), wastes that contain both hazardous and low-level radioactive constituents, with full participation of the affected states. The FFCA provides the framework for the development of treatment capacity for DOE's mixed waste. Disposal of the treatment residues is not addressed by the FFCA. DOE has initiated efforts in concert with the states in the development of a disposal strategy for the treated mixed wastes. This paper outlines DOE efforts in development of a mixed waste disposal strategy which is integrated with the FFCA Site Treatment Planning process

  7. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Science.gov (United States)

    2010-01-01

    ... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.52 Land disposal... wastes by placing in disposal units which are sufficiently separated from disposal units for the other... between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer zone...

  8. Preliminary disposal limits, plume interaction factors, and final disposal limits

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2018-01-11

    In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

  9. Radioactive mixed waste disposal

    International Nuclear Information System (INIS)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

  10. A summary of radiological waste disposal practices in the United States and the United Kingdom - 16379

    International Nuclear Information System (INIS)

    Maranville, Victoria M.; McGrath, Richard

    2009-01-01

    A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. The main focus of the review consisted of a literature search of available documents and other published sources on low level radioactive waste (LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by the United Kingdom's (UK) Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site. The review contained a summary of the US and UK radiological waste classification requirements including a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices. A regulatory overview and evolution of regulatory requirements in the US is presented. The UK regulatory environment is also discussed and contrasted to the US process. The public participation, as part of the US regulatory process, is provided and the mechanism for stakeholder identification and involvement is detailed. To demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies, in which remediation activities were carried out, were reviewed. The following information was compiled: type of wastes disposed of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is discussed within the case studies. Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are presented in this publication for

  11. An Illustration of the Corrective Action Process, The Corrective Action Management Unit at Sandia National Laboratories/New Mexico

    International Nuclear Information System (INIS)

    Irwin, M.; Kwiecinski, D.

    2002-01-01

    Corrective Action Management Units (CAMUs) were established by the Environmental Protection Agency (EPA) to streamline the remediation of hazardous waste sites. Streamlining involved providing cost saving measures for the treatment, storage, and safe containment of the wastes. To expedite cleanup and remove disincentives, EPA designed 40 CFR 264 Subpart S to be flexible. At the heart of this flexibility are the provisions for CAMUs and Temporary Units (TUs). CAMUs and TUs were created to remove cleanup disincentives resulting from other Resource Conservation Recovery Act (RCRA) hazardous waste provisions--specifically, RCRA land disposal restrictions (LDRs) and minimum technology requirements (MTRs). Although LDR and MTR provisions were not intended for remediation activities, LDRs and MTRs apply to corrective actions because hazardous wastes are generated. However, management of RCRA hazardous remediation wastes in a CAMU or TU is not subject to these stringent requirements. The CAMU at Sandia National Laboratories in Albuquerque, New Mexico (SNL/NM) was proposed through an interactive process involving the regulators (EPA and the New Mexico Environment Department), DOE, SNL/NM, and stakeholders. The CAMU at SNL/NM has been accepting waste from the nearby Chemical Waste Landfill remediation since January of 1999. During this time, a number of unique techniques have been implemented to save costs, improve health and safety, and provide the best value and management practices. This presentation will take the audience through the corrective action process implemented at the CAMU facility, from the selection of the CAMU site to permitting and construction, waste management, waste treatment, and final waste placement. The presentation will highlight the key advantages that CAMUs and TUs offer in the corrective action process. These advantages include yielding a practical approach to regulatory compliance, expediting efficient remediation and site closure, and realizing

  12. MethodS of radioactive waste processing and disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Tolstykh, V.D.

    1983-01-01

    The results of investigations into radioactive waste processing and disposal in the United Kingdom are discussed. Methods for solidification of metal and graphite radioactive wastes and radioactive slime of the Magnox reactors are described. Specifications of different installations used for radioactive waste disposal are given. Climatic and geological conditions in the United Kingdom are such that any deep storages of wastes will be lower than the underground water level. That is why dissolution and transport by underground waters will inevitably result in radionuclide mobility. In this connection an extended program of investigations into the main three aspects of disposal problem namely radionucleide release in storages, underground water transport and radionuclide migration is realized. The program is divided in two parts. The first part deals with retrival of hydrological and geochemical data on geological formations, development of specialized methods of investigations which are necessary for identification of places for waste final disposal. The second part represents theoretical and laboratory investigations into provesses of radionuclide transport in the system of ''sttorage-geological formation''. It is concluded that vitrification on the base of borosilicate glass is the most advanced method of radioactive waste solidification

  13. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    International Nuclear Information System (INIS)

    Traynor, J. L.

    2001-01-01

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure

  14. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    Energy Technology Data Exchange (ETDEWEB)

    J. L. Traynor

    2001-03-01

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure.

  15. Glossary of CERCLA, RCRA and TSCA related terms and acronyms

    International Nuclear Information System (INIS)

    1993-10-01

    This glossary contains CERCLA, RCRA and TSCA related terms that are most often encountered in the US Department of Energy (DOE) Environmental Restoration and Emergency Preparedness activities. Detailed definitions are included for key terms. The CERCLA definitions included in this glossary are taken from the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as amended and related federal rulemakings. The RCRA definitions included in this glossary are taken from the Resource Conservation and Recovery Act (RCRA) and related federal rulemakings. The TSCA definitions included in this glossary are taken from the Toxic Substances and Control Act (TSCA) and related federal rulemakings. Definitions related to TSCA are limited to those sections in the statute and regulations concerning PCBs and asbestos.Other sources for definitions include additional federal rulemakings, assorted guidance documents prepared by the US Environmental Protection Agency (EPA), guidance and informational documents prepared by the US Department of Energy (DOE), and DOE Orders. The source of each term is noted beside the term. Terms presented in this document reflect revised and new definitions published before July 1, 1993

  16. Control of water infiltration into near surface LLW disposal units

    International Nuclear Information System (INIS)

    O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

    1989-01-01

    Water infiltration to buried waste is the prime problem of concern in designing waste disposal units for the humid areas. Conventional compacted clay layers (resistance layer barriers) have been subject to failure by subsidence and by permeability increases brought about by plant roots. A clay barrier with a rock cover sans plants is being investigated. Also a combination of a resistive layer overlying a conductive layer is being investigated. Laboratory studies indicate that this approach can be very effective and field evaluations are underway. However, it must be noted that subsidence will negate the effectiveness of any buried layer barriers. A surface barrier (bioengineering management) has been valuated in the field and found to be very effective in preventing water entry into waste disposal units. This surface barrier is easily repairable if damaged by subsidence and could be the system of choice under active subsidence conditions

  17. RCRA closure plan for the Bear Creek Burial Grounds B Area and Walk-In Pits at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1992-11-01

    The Bear Creek Burial Grounds (BCBG) are located on the southwest flank of Pine Ridge ∼1.5 miles west of the Oak Ridge Y-12 Plant in Bear Creek Valley. This facility consists of several contiguous disposal sites identified as Burial Grounds A, B, C, and D. Each burial site consists of a series of trenches used for disposal of solid wastes and, in some cases, liquid wastes. Initially, the RCRA Closure/Postclosure plan for the BCBG was intended to apply to A Area, C-West, B Area, and the walk-in pits for BCBG. However, a plan was provided to include the B Area in the walk-in pits so that both areas cold be closed under one cap. The closure plan for B Area and the walk-in pits is presented in this document. The actual quantity and identity of materials is uncertain. The largest volume of material disposed in BCBG consists of uranium-contaminated industrial trash (paper, wood, steel, glass, and rubble)

  18. Quarterly report of RCRA groundwater monitoring data for period January 1, 1993 through March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. This quarterly report contains data received between March 8 and May 24, 1993, which are the cutoff dates for this reporting period. This report may contain not only data from the January through March quarter but also data from earlier sampling events that were not previously reported.

  19. Analysis of TRU waste for RCRA-listed elements

    International Nuclear Information System (INIS)

    Mahan, C.; Gerth, D.; Yoshida, T.

    1996-01-01

    Analytical methods for RCRA listed elements on Portland cement type waste have been employed using both microwave and open hot plate digestions with subsequent analysis by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), graphite furnace atomic absorption (GFAA) and cold vapor atomic absorption and fluorescence (CVAA/CVAFS). Four different digestion procedures were evaluated including an open hot plate nitric acid digestion, EPA SW-846 Method 3051, and 2 methods using modifications to Method 3051. The open hot plate and the modified Method 3051, which used aqua regia for dissolution, were the only methods which resulted in acceptable data quality for all 14 RCRA-listed elements. Results for the nitric acid open hot plate digestion were used to qualify the analytical methods for TRU waste characterization, and resulted in a 99% passing score. Direct chemical analysis of TRU waste is being developed at Los Alamos National Laboratory in an attempt to circumvent the problems associated with strong acid digestion methods. Technology development includes laser induced breakdown spectroscopy (LIBS), laser ablation inductively coupled plasma mass spectrometry (LA-ICPMS), dc arc CID atomic emission spectroscopy (DC-AES), and glow discharge mass spectrometry (GDMS). Analytical methods using the Portland cement matrix are currently being developed for each of the listed techniques. Upon completion of the development stage, blind samples will be distributed to each of the technology developers for RCRA metals characterization

  20. Development of DUST: A computer code that calculates release rates from a LLW disposal unit

    International Nuclear Information System (INIS)

    Sullivan, T.M.

    1992-01-01

    Performance assessment of a Low-Level Waste (LLW) disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the disposal unit source term). The major physical processes that influence the source term are water flow, container degradation, waste form leaching, and radionuclide transport. A computer code, DUST (Disposal Unit Source Term) has been developed which incorporates these processes in a unified manner. The DUST code improves upon existing codes as it has the capability to model multiple container failure times, multiple waste form release properties, and radionuclide specific transport properties. Verification studies performed on the code are discussed

  1. Hanford facility RCRA permit condition II.U.1 report: mapping of underground piping

    Energy Technology Data Exchange (ETDEWEB)

    Hays, C.B.

    1996-09-27

    The purpose of this report is to fulfill Condition Il.U.1. of the Hanford Facility (HF) Resource Conservation and Recovery Act (RCRA) Permit. The HF RCRA Permit, Number WA7890008967, became effective on September 28, 1994 (Ecology 1994). Permit Conditions Il.U. (mapping) and II.V. (marking) of the HF RCRA Permit, Dangerous Waste (OW) Portion, require the mapping and marking of dangerous waste underground pipelines subject to the provisions of the Washington Administrative Code (WAC) Chapter 173-303. Permit Condition Il.U.I. requires the submittal of a report describing the methodology used to generate pipeline maps and to assure their quality. Though not required by the Permit, this report also documents the approach used for the field marking of dangerous waste underground pipelines.

  2. Superfund TIO videos. Set A. Regulatory overview - CERCLA's relationship to other programs: RCRA, Title III, UST, CWA, SDWA. Part 1. Audio-Visual

    International Nuclear Information System (INIS)

    1990-01-01

    The videotape is divided into five sections. Section 1 provides definitions and historical information on both the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The four types of RCRA regulatory programs - Subtitles C, D, I, and J - are described. Treatment, storage, and disposal (TSD) and recycling facilities are also discussed. Section 2 discusses the history behind the Emergency Planning and Community Right-to-Know Act (Title III). The four major provisions of Title III, which are emergency planning, emergency release notification, community right-to-know reporting, and the toxic chemical release inventory are covered. Section 3 outlines the UST program covering notification, record keeping, and the UST Trust Fund. Section 4 outlines the six major provisions of the Clean Water Act (CWA): water quality, pretreatment, prevention of oil and hazardous substance discharges, responses to oil and hazardous substance discharges, discharges of hazardous substances into the ocean, and dredge and fill. Section 5 explains the purpose, regulations, and standards of the Safe Drinking Water Act (SDWA). Specific issues such as underground injection, sole source aquifers, and lead contamination are discussed

  3. Permitting mixed waste treatment, storage and disposal facilities: A mixed bag

    International Nuclear Information System (INIS)

    Ranek, N.L.; Coalgate, J.L.

    1995-01-01

    The Federal Facility Compliance Act of 1992 (FFCAct) requires the U.S. Department of Energy (DOE) to make a comprehensive national inventory of its mixed wastes (i.e., wastes that contain both a hazardous component that meets the Resource Conservation and Recovery Act (RCRA) definition of hazardous waste and a radioactive component consisting of source, special nuclear, or byproduct material regulated under the Atomic Energy Act (AEA)), and of its mixed waste treatment technologies and facilities. It also requires each DOE facility that stores or generates mixed waste to develop a treatment plan that includes, in part, a schedule for constructing units to treat those wastes that can be treated using existing technologies. Inherent in constructing treatment units for mixed wastes is, of course, permitting. This paper identifies Federal regulatory program requirements that are likely to apply to new DOE mixed waste treatment units. The paper concentrates on showing how RCRA permitting requirements interrelate with the permitting or licensing requirements of such other laws as the Atomic Energy Act, the Clean Water Act, and the Clean Air Act. Documentation needed to support permit applications under these laws are compared with RCRA permit application documentation. National Environmental Policy Act (NEPA) documentation requirements are also addressed, and throughout the paper, suggestions are made for managing the permitting process

  4. Thermal desorption treatability test conducted with VAC*TRAX Unit

    International Nuclear Information System (INIS)

    1996-01-01

    In 1992, Congress passed the Federal Facilities Compliance Act, requiring the U.S. Department of Energy (DOE) to treat and dispose of its mixed waste in accordance with Resource Conservation and Recovery Act (RCRA) treatment standards. In response to the need for mixed-waste treatment capacity, where off-site commercial treatment facilities do not exist or cannot be used, the DOE Albuquerque Operations Office (DOE-AL) organized a Treatment Selection Team to match mixed waste with treatment options and develop a strategy for treatment of mixed waste. DOE-AL manages nine sites with mixed-waste inventories. The Treatment Selection Team determined a need to develop mobile treatment units (MTUs) to treat waste at the sites where the wastes are generated. Treatment processes used for mixed wastes must remove the hazardous component (i.e., meet RCRA treatment standards) and contain the radioactive component in a form that will protect the worker, public, and environment. On the basis of the recommendations of the Treatment Selection Team, DOE-AL assigned projects to the sites to bring mixed-waste treatment capacity on-line. The three technologies assigned to the DOE Grand Junction Projects Office (DOE-GJPO) include thermal desorption (TD), evaporative oxidation, and waste water evaporation

  5. A process for treating radioactive water-reactive wastes

    International Nuclear Information System (INIS)

    Dziewinski, J.; Lussiez, G.; Munger, D.

    1995-01-01

    Los Alamos National Laboratory and other locations in the complex of experimental and production facilities operated by the United States Department of Energy (DOE) have generated an appreciable quantity of hazardous and radioactive wastes. The Resource Conservation and Recovery Act (RCRA) enacted by the United States Congress in 1976 and subsequently amended in 1984, 1986, and 1988 requires that every hazardous waste must be rendered nonhazardous before disposal. Many of the wastes generated by the DOE complex are both hazardous and radioactive. These wastes, called mixed wastes, require applying appropriate regulations for radioactive waste disposal and the regulations under RCRA. Mixed wastes must be treated to remove the hazardous waste component before they are disposed as radioactive waste. This paper discusses the development of a treatment process for mixed wastes that exhibit the reactive hazardous characteristic. Specifically, these wastes react readily and violently with water. Wastes such as lithium hydride (LiH), sodium metal, and potassium metal are the primary wastes in this category

  6. Disposal phase experimental program plan

    International Nuclear Information System (INIS)

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes

  7. Gas cooled reactor decommissioning. Packaging of waste for disposal in the United Kingdom deep repository

    International Nuclear Information System (INIS)

    Barlow, S.V.; Wisbey, S.J.; Wood, P.

    1998-01-01

    United Kingdom Nirex Limited has been established to develop and operate a deep underground repository for the disposal of the UK's intermediate and certain low level radioactive waste. The UK has a significant Gas Cooled Reactor (GCR) programme, including both Magnox and AGR (Advanced Gas-cooled Reactor) capacity, amounting to 26 Magnox reactors, 15 AGR reactors as well as research and prototype reactor units such as the Windscale AGR and the Windscale Piles. Some of these units are already undergoing decommissioning and Nirex has estimated that some 15,000 m 3 (conditioned volume) will come forward for disposal from GCR decommissioning before 2060. This volume does not include final stage (Stage 3) decommissioning arisings from commercial reactors since the generating utilities in the UK are proposing to adopt a deferred safe store strategy for these units. Intermediate level wastes arising from GCR decommissioning needs to be packaged in a form suitable for on-site interim storage and eventual deep disposal in the planned repository. In the absence of Conditions for Acceptance for a repository in the UK, the dimensions, key features and minimum performance requirements for waste packages are defined in Waste Package Specifications. These form the basis for all assessments of the suitability of wastes for disposal, including GCR wastes. This paper will describe the nature and characteristics of GCR decommissioning wastes which are intended for disposal in a UK repository. The Nirex Waste Package Specifications and the key technical issues, which have been identified when considering GCR decommissioning waste against the performance requirements within the specifications, are discussed. (author)

  8. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Wickline, Alfred

    2005-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

  9. SACM and the RCRA stabilization initiative: Similarities of principles and applicability

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the corrective action provisions of the Resource Conservation and Recovery Act (RCRA) provide standards for the remediation of environmental media contaminated with hazardous substances or hazardous waste, respectively. In both cases, prior to the US Environmental Protection Agency`s (EPA) development of the two subject reform initiatives, existing formal processes specified the level of site investigation required, the process for reaching a decision on the method of remediation, public participation in the decision process, and enforcement authorities that include orders and schedules of compliance. Traditionally, implementation of these processes has resulted in a great amount of time, effort, and money being expended before actual remediation began. Following criticism from the public and the regulated community, the EPA has proposed streamlining reforms for hazardous waste site cleanup under both CERCLA and RCRA that will begin remediation sooner with lower costs. The purpose of this Information Brief is to discuss the common goals, processes, and strategies of the Superfund Accelerated Cleanup Model (SACM) and the RCRA Stabilization Initiative.

  10. Selective removal/recovery of RCRA metals from waste and process solutions using polymer filtration trademark technology

    International Nuclear Information System (INIS)

    Smith, B.F.

    1997-01-01

    Resource Conservation and Recovery Act (RCRA) metals are found in a number of process and waste streams at many DOE, U.S. Department of Defense, and industrial facilities. RCRA metals consist principally of chromium, mercury, cadmium, lead, and silver. Arsenic and selenium, which form oxyanions, are also considered RCRA elements. Discharge limits for each of these metals are based on toxicity and dictated by state and federal regulations (e.g., drinking water, RCRA, etc.). RCRA metals are used in many current operations, are generated in decontamination and decommissioning (D ampersand D) operations, and are also present in old process wastes that require treatment and stabilization. These metals can exist in solutions, as part of sludges, or as contaminants on soils or solid surfaces, as individual metals or as mixtures with other metals, mixtures with radioactive metals such as actinides (defined as mixed waste), or as mixtures with a variety of inert metals such as calcium and sodium. The authors have successfully completed a preliminary proof-of-principle evaluation of Polymer Filtration trademark (PF) technology for the dissolution of metallic mercury and have also shown that they can remove and concentrate RCRA metals from dilute solutions for a variety of aqueous solution types using PF technology. Another application successfully demonstrated is the dilute metal removal of americium and plutonium from process streams. This application was used to remove the total alpha contamination to below 30 pCi/L for the wastewater treatment plant at TA-50 at Los Alamos National Laboratory (LANL) and from nitric acid distillate in the acid recovery process at TA-55, the Plutonium Facility at LANL (ESP-CP TTP AL16C322). This project will develop and optimize the PF technology for specific DOE process streams containing RCRA metals and coordinate it with the needs of the commercial sector to ensure that technology transfer occurs

  11. Selective removal/recovery of RCRA metals from waste and process solutions using polymer filtration{trademark} technology

    Energy Technology Data Exchange (ETDEWEB)

    Smith, B.F. [Los Alamos National Lab., NM (United States)

    1997-10-01

    Resource Conservation and Recovery Act (RCRA) metals are found in a number of process and waste streams at many DOE, U.S. Department of Defense, and industrial facilities. RCRA metals consist principally of chromium, mercury, cadmium, lead, and silver. Arsenic and selenium, which form oxyanions, are also considered RCRA elements. Discharge limits for each of these metals are based on toxicity and dictated by state and federal regulations (e.g., drinking water, RCRA, etc.). RCRA metals are used in many current operations, are generated in decontamination and decommissioning (D&D) operations, and are also present in old process wastes that require treatment and stabilization. These metals can exist in solutions, as part of sludges, or as contaminants on soils or solid surfaces, as individual metals or as mixtures with other metals, mixtures with radioactive metals such as actinides (defined as mixed waste), or as mixtures with a variety of inert metals such as calcium and sodium. The authors have successfully completed a preliminary proof-of-principle evaluation of Polymer Filtration{trademark} (PF) technology for the dissolution of metallic mercury and have also shown that they can remove and concentrate RCRA metals from dilute solutions for a variety of aqueous solution types using PF technology. Another application successfully demonstrated is the dilute metal removal of americium and plutonium from process streams. This application was used to remove the total alpha contamination to below 30 pCi/L for the wastewater treatment plant at TA-50 at Los Alamos National Laboratory (LANL) and from nitric acid distillate in the acid recovery process at TA-55, the Plutonium Facility at LANL (ESP-CP TTP AL16C322). This project will develop and optimize the PF technology for specific DOE process streams containing RCRA metals and coordinate it with the needs of the commercial sector to ensure that technology transfer occurs.

  12. Hanford land disposal restrictions plan for mixed wastes

    International Nuclear Information System (INIS)

    1990-10-01

    Since the early 1940s, the Hanford Site has been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 (RCRA) and the Atomic Energy Act. The State of Washington Department of Ecology (Ecology), the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) to bring Hanford Site Operations into compliance with dangerous waste regulations. The Tri-Party Agreement was amended to require development of the Hanford Land Disposal Restrictions Plan for Mixed Wastes (this plan) to comply with land disposal restrictions requirements for radioactive mixed waste. The Tri-Party Agreement requires, and the this plan provides, the following sections: Waste Characterization Plan, Storage Report, Treatment Report, Treatment Plan, Waste Minimization Plan, a schedule, depicting the events necessary to achieve full compliance with land disposal restriction requirements, and a process for establishing interim milestones. 34 refs., 28 figs., 35 tabs

  13. Hanford land disposal restrictions plan for mixed wastes

    Energy Technology Data Exchange (ETDEWEB)

    1990-10-01

    Since the early 1940s, the Hanford Site has been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 (RCRA) and the Atomic Energy Act. The State of Washington Department of Ecology (Ecology), the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) to bring Hanford Site Operations into compliance with dangerous waste regulations. The Tri-Party Agreement was amended to require development of the Hanford Land Disposal Restrictions Plan for Mixed Wastes (this plan) to comply with land disposal restrictions requirements for radioactive mixed waste. The Tri-Party Agreement requires, and the this plan provides, the following sections: Waste Characterization Plan, Storage Report, Treatment Report, Treatment Plan, Waste Minimization Plan, a schedule, depicting the events necessary to achieve full compliance with land disposal restriction requirements, and a process for establishing interim milestones. 34 refs., 28 figs., 35 tabs.

  14. Degradation of cementitious materials associated with salstone disposal units

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith, F. G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2014-09-01

    The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed “saltstone”. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of a saltstone disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions.

  15. Closure Plan for Corrective Action Unit 110: Area 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Fitzmaurice, T. M.

    2000-01-01

    This Closure Plan has been prepared for the Area 3 RWMS U-3ax/bl Disposal Unit Corrective Action Unit 110 in accordance with the Federal Facility and Consent Order (Nevada Division of Environmental Protection [NDEP] et al., 1996). The U-3ax/bl is a historic disposal unit within the Area 3 Radioactive Waste Management Site located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit is scheduled for permanent closure under the Resource Conservation and Recovery Act as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10 5 cubic meters (8.12 x 10 6 cubic feet) of waste. NTS nuclear device testing generated approximately 95 percent of the total volume disposed of in U-3ax/bl, the majority of which came from the Waste Consolidation Project (80 percent of the total volume) (Elletson and Johnejack, 1995). Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is continuously in a state of moisture deficit. The U-3ax/bl Disposal Unit will be closed in place by installing a Resource Conservation and Recovery Act equivalent cover. Following cover construction a fence will be installed around the cover to prevent accidental damage to the cover. Post-closure monitoring will consist of site inspections to determine the condition of the engineered cover and cover performance monitoring using Time-Domain Reflectometry arrays to monitor moisture migration in the cover. Any identified maintenance and repair

  16. Closure Plan for Corrective Action Unit 110: Area 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    T. M. Fitzmaurice

    2000-08-01

    This Closure Plan has been prepared for the Area 3 RWMS U-3ax/bl Disposal Unit Corrective Action Unit 110 in accordance with the Federal Facility and Consent Order (Nevada Division of Environmental Protection [NDEP] et al., 1996). The U-3ax/bl is a historic disposal unit within the Area 3 Radioactive Waste Management Site located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit is scheduled for permanent closure under the Resource Conservation and Recovery Act as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (8.12 x 10{sup 6} cubic feet) of waste. NTS nuclear device testing generated approximately 95 percent of the total volume disposed of in U-3ax/bl, the majority of which came from the Waste Consolidation Project (80 percent of the total volume) (Elletson and Johnejack, 1995). Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is continuously in a state of moisture deficit. The U-3ax/bl Disposal Unit will be closed in place by installing a Resource Conservation and Recovery Act equivalent cover. Following cover construction a fence will be installed around the cover to prevent accidental damage to the cover. Post-closure monitoring will consist of site inspections to determine the condition of the engineered cover and cover performance monitoring using Time-Domain Reflectometry arrays to monitor moisture migration in the cover. Any identified maintenance and

  17. The Pinellas Plant RCRA facility investigation - A case study

    International Nuclear Information System (INIS)

    Kilbury, Richard; Keshian, Berg; Farley, Dwain; Meyer, David; Ingle, David; Biedermann, Charles

    1992-01-01

    Under the direction of the U.S. Department of Energy Albuquerque Field Office Environmental Restoration Program, a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) was completed at the Pinellas Plant to fulfill requirements of the Hazardous and Solid Waste Amendments of 1984 (HSWA) permit issued on February 9, 1990 by the U.S. Environmental Protection Agency (EPA). This RFI addressed potential contaminant releases and environmental conditions at 15 solid waste management units (SWMUs). The RFI characterization program began in April 1990 and was completed in May 1991. The scope of RFI data collection activities is presented in the Pinellas Plant RFI Workplan issued in May 1990 and approved by EPA on April 16, 1991. An RFI Report was submitted to EPA on September 1, 1991. This paper presents a summary of RFI results and conclusions. Primary environmental concerns at the Pinellas Plant are emphasized. (author)

  18. Glossary of CERCLA, RCRA and TSCA related terms and acronyms. Environmental Guidance

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    This glossary contains CERCLA, RCRA and TSCA related terms that are most often encountered in the US Department of Energy (DOE) Environmental Restoration and Emergency Preparedness activities. Detailed definitions are included for key terms. The CERCLA definitions included in this glossary are taken from the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as amended and related federal rulemakings. The RCRA definitions included in this glossary are taken from the Resource Conservation and Recovery Act (RCRA) and related federal rulemakings. The TSCA definitions included in this glossary are taken from the Toxic Substances and Control Act (TSCA) and related federal rulemakings. Definitions related to TSCA are limited to those sections in the statute and regulations concerning PCBs and asbestos.Other sources for definitions include additional federal rulemakings, assorted guidance documents prepared by the US Environmental Protection Agency (EPA), guidance and informational documents prepared by the US Department of Energy (DOE), and DOE Orders. The source of each term is noted beside the term. Terms presented in this document reflect revised and new definitions published before July 1, 1993.

  19. Commercial processing and disposal alternatives for very low levels of radioactive waste in the United States

    International Nuclear Information System (INIS)

    Benda, G.A.

    2005-01-01

    The United States has several options available in the commercial processing and disposal of very low levels of radioactive waste. These range from NRC licensed low level radioactive sites for Class A, B and C waste to conditional disposal or free release of very low concentrations of material. Throughout the development of disposal alternatives, the US promoted a graded disposal approach based on risk of the material hazards. The US still promotes this approach and is renewing the emphasis on risk based disposal for very low levels of radioactive waste. One state in the US, Tennessee, has had a long and successful history of disposal of very low levels of radioactive material. This paper describes that approach and the continuing commercial options for safe, long term processing and disposal. (author)

  20. Quarterly report of RCRA groundwater monitoring data for period October 1, 1992--December 31, 1992

    International Nuclear Information System (INIS)

    1993-04-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 CFR 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. Long-term laboratory contracts were approved on October 22, 1991. DataChem Laboratories of Salt Lake City, Utah, performs the hazardous chemicals analyses for the Hanford Site. Analyses for coliform bacteria are performed by Columbia/Biomedical Laboratories and for dioxin by TMS Analytical Services, Inc. International Technology Analytical Services Richland, Washington performs the radiochemical analyses. This quarterly report contains data that were received prior to March 8, 1993. This report may contain not only data from the October through December quarter but also data from earlier sampling events that were not previously reported

  1. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    International Nuclear Information System (INIS)

    2009-01-01

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

  2. Low-level radioactive waste disposal in the United States: An overview of current commercial regulations and concepts

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.

    1993-08-01

    Commercial low-level radioactive waste disposal in the United States is regulated by the US Nuclear Regulatory Commission (NRC) under 10 CFR 61 (1991). This regulation was issued in 1981 after a lengthy and thorough development process that considered the radionuclide concentrations and characteristics associated with commercial low-level radioactive waste streams; alternatives for waste classification; alternative technologies for low-level radioactive waste disposal; and data, modeling, and scenario analyses. The development process also included the publication of both draft and final environmental impact statements. The final regulation describes the general provisions; licenses; performance objectives; technical requirements for land disposal; financial assurances; participation by state governments and Indian tribes; and records, reports, tests, and inspections. This paper provides an overview of, and tutorial on, current commercial low-level radioactive waste disposal regulations in the United States

  3. PORFLOW Simulations Supporting Saltstone Disposal Unit Design Optimization

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hang, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Taylor, G. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-12-10

    SRNL was requested by SRR to perform PORFLOW simulations to support potential cost-saving design modifications to future Saltstone Disposal Units in Z-Area (SRR-CWDA-2015-00120). The design sensitivity cases are defined in a modeling input specification document SRR-CWDA-2015-00133 Rev. 1. A high-level description of PORFLOW modeling and interpretation of results are provided in SRR-CWDA-2015-00169. The present report focuses on underlying technical issues and details of PORFLOW modeling not addressed by the input specification and results interpretation documents. Design checking of PORFLOW modeling is documented in SRNL-L3200-2015-00146.

  4. Characterization of sediment in a leaching trench RCRA (Resource Conservation and Recovery Act) site

    International Nuclear Information System (INIS)

    Zimmerman, M.G.; Kossik, C.D.

    1988-01-01

    Hazardous materials potentially were disposed of into a pair of leaching trenches from 1975 until Resource Conservation and Recovery Act (RCRA) regulations were imposed in 1985. These leaching trenches now are used for disposal of nonhazardous process water. The typical effluent (approximately 3 million gal/d) consisted of water with trace quantities of laboratory, maintenance, and fuel fabrication process chemicals. The largest constituent in the waste stream was uranium in low concentrations. This paper describes the project used to analyze and characterize the sediments in and below the leaching trenches. Two phases of sediment sampling were performed. The first phase consisted of taking samples between the bottom of the trenches and groundwater to locate contamination in the deep sediments under the trenches. To accomplish this sampling, a series of wells were drilled, and samples were obtained for every five feet in depth. The second phase consisted of samples taken at three depths in a series of positions along each trench. Sampling was completed to determine contamination levels in the shallow sediments and loose material washed into the trenches from the process sewer system. The project results were that no measurable contamination was found in the deep sediments. Measurable contamination from metals, such as chromium and nickel, was found in the shallow sediments. The primary contaminant in the shallow sediments was uranium. The concentration of contaminants decreased rapidly to near-background levels at shallow depths below the bottoms of the trenches

  5. Generalized economic model for evaluating disposal costs at a low-level waste disposal facility

    International Nuclear Information System (INIS)

    Baird, R.D.; Rogers, V.C.

    1985-01-01

    An economic model is developed which can be used to evaluate cash flows associated with the development, operations, closure, and long-term maintenance of a proposed Low-Level Radioactive Waste disposal facility and to determine the unit disposal charges and unit surcharges which might result. The model includes the effects of nominal interest rate (rate of return on investment, or cost of capital), inflation rate, waste volume growth rate, site capacity, duration of various phases of the facility history, and the cash flows associated with each phase. The model uses standard discounted cash flow techniques on an after-tax basis to determine that unit disposal charge which is necessary to cover all costs and expenses and to generate an adequate rate of return on investment. It separately considers cash flows associated with post-operational activities to determine the required unit surcharge. The model is applied to three reference facilities to determine the respective unit disposal charges and unit surcharges, with various values of parameters. The sensitivity of the model results are evaluated for the unit disposal charge

  6. Closure plan for Corrective Action Unit 94: Building 650 Leachfield, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-03-01

    The Building 650 Leachfield, Corrective Action Unit (CAU) 94, will be clean closed by removal in accordance with the Resource Conservation and Recover Act (RCRA) operational permit and the Federal Facility Agreement and Consent Order. Historically, laboratory effluent was discharged through pipelines leading from the Radiochemistry Laboratory in Building 650 to a distribution box and a series of pipes dispersed across the leachfield. Effluent from the laboratory contained both hazardous and radioactive constituents. Discharge of hazardous and radioactive waste began in 1965. Discharge of radioactive waste ended in 1979 and hazardous waste discharge ended in 1987. From 1987 to 1993 the leachfield was used for the disposal of non-hazardous waste water. The piping leading to the leachfield was sealed in 1993

  7. Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2008-01-01

    This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of the completed closure activities, to document waste disposal, and to present analytical data confirming that the remediation goals were met. The closure alternatives consisted of closure in place for two of the CASs, and no further action with implementation of best management practices (BMPs) for the remaining five CASs.

  8. Regulatory controls on the hydrogeological characterization of a mixed waste disposal site, Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Ruebelmann, K.L.

    1990-01-01

    Following the detection of chlorinated volatile organic compounds in the groundwater beneath the SDA in the summer of 1987, hydrogeological characterization of the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory (INEL) was required by the Resource Conservation and Recovery Act (RCRA). The waste site, the Subsurface Disposal Area (SDA), is the subject of a RCRA Corrective Action Program. Regulatory requirements for the Corrective Action Program dictate a phased approach to evaluation of the SDA. In the first phase of the program, the SDA is the subject of a RCRA Facility Investigation (RIF), which will obtain information to fully characterize the physical properties of the site, determine the nature and extent of contamination, and identify pathways for migration of contaminants. If the need for corrective measures is identified during the RIF, a Corrective Measures Study (CMS) will be performed as second phase. Information generated during the RIF will be used to aid in the selection and implementation of appropriate corrective measures to correct the release. Following the CMS, the final phase is the implementation of the selected corrective measures. 4 refs., 1 fig

  9. Low-level mixed waste: An RCRA perspective for NRC licensees

    International Nuclear Information System (INIS)

    1990-08-01

    The publication presents an overview of RCRA requirements for commercially-generated low-level mixed waste. It is designed for Nuclear Regulatory Commission (NRC) licensees who may not be familiar with EPA regulations that apply to their waste products

  10. EPA Linked Open Data: Resource Conservation and Recovery Act Handlers (RCRA)

    Data.gov (United States)

    U.S. Environmental Protection Agency — RCRAInfo is EPA’s comprehensive information system that supports the Resource Conservation and Recovery Act (RCRA) of 1976 and the Hazardous and Solid Waste...

  11. Life Cycle Analysis for Treatment and Disposal of PCB Waste at Ashtabula and Fernald

    International Nuclear Information System (INIS)

    Morris, M.I.

    2001-01-01

    This report presents the use of the life cycle analysis (LCA) system developed at Oak Ridge National Laboratory (ORNL) to assist two U.S. Department of Energy (DOE) sites in Ohio--the Ashtabula Environmental Management Project near Cleveland and the Fernald Environmental Management Project near Cincinnati--in assessing treatment and disposal options for polychlorinated biphenyl (PCB)-contaminated low-level radioactive waste (LLW) and mixed waste. We will examine, first, how the LCA process works, then look briefly at the LCA system's ''toolbox,'' and finally, see how the process was applied in analyzing the options available in Ohio. As DOE nuclear weapons facilities carry out planned decontamination and decommissioning (D and D) activities for site closure and progressively package waste streams, remove buildings, and clean up other structures that have served as temporary waste storage locations, it becomes paramount for each waste stream to have a prescribed and proven outlet for disposition. Some of the most problematic waste streams throughout the DOE complex are PCB low-level radioactive wastes (liquid and solid) and PCB low-level Resource Conservation and Recovery Act (RCRA) liquid and solid wastes. Several DOE Ohio Field Office (OH) sites have PCB disposition needs that could have an impact on the critical path of the decommissioning work of these closure sites. The Ashtabula Environmental Management Project (AEMP), an OH closure site, has an urgent problem with disposition of soils contaminated by PCB and low-level waste at the edge of the site. The Fernald Environmental Management Project (FEMP), another OH closure site, has difficulties in timely disposition of its PCB-low-level sludges and its PCB low-level RCRA sludges in order to avoid impacting the critical path of its D and D activities. Evaluation of options for these waste streams is the subject of this report. In the past a few alternatives for disposition of PCB low-level waste and PCB low

  12. Life Cycle Analysis for Treatment and Disposal of PCB Waste at Ashtabula and Fernald

    Energy Technology Data Exchange (ETDEWEB)

    Morris, M.I.

    2001-01-11

    This report presents the use of the life cycle analysis (LCA) system developed at Oak Ridge National Laboratory (ORNL) to assist two U.S. Department of Energy (DOE) sites in Ohio--the Ashtabula Environmental Management Project near Cleveland and the Fernald Environmental Management Project near Cincinnati--in assessing treatment and disposal options for polychlorinated biphenyl (PCB)-contaminated low-level radioactive waste (LLW) and mixed waste. We will examine, first, how the LCA process works, then look briefly at the LCA system's ''toolbox,'' and finally, see how the process was applied in analyzing the options available in Ohio. As DOE nuclear weapons facilities carry out planned decontamination and decommissioning (D&D) activities for site closure and progressively package waste streams, remove buildings, and clean up other structures that have served as temporary waste storage locations, it becomes paramount for each waste stream to have a prescribed and proven outlet for disposition. Some of the most problematic waste streams throughout the DOE complex are PCB low-level radioactive wastes (liquid and solid) and PCB low-level Resource Conservation and Recovery Act (RCRA) liquid and solid wastes. Several DOE Ohio Field Office (OH) sites have PCB disposition needs that could have an impact on the critical path of the decommissioning work of these closure sites. The Ashtabula Environmental Management Project (AEMP), an OH closure site, has an urgent problem with disposition of soils contaminated by PCB and low-level waste at the edge of the site. The Fernald Environmental Management Project (FEMP), another OH closure site, has difficulties in timely disposition of its PCB-low-level sludges and its PCB low-level RCRA sludges in order to avoid impacting the critical path of its D&D activities. Evaluation of options for these waste streams is the subject of this report. In the past a few alternatives for disposition of PCB low-level waste

  13. Identification, classification and management of industrial waste in Kavir steel complex according to the Bazel convention and RCRA

    Directory of Open Access Journals (Sweden)

    Mohammad Hasan Ehrampoush

    2016-06-01

    Full Text Available Introduction: Requiring industries for implementing industrial waste management programs and planning for proper waste disposal is essential in order to achieve sustainable development. Therefore, industrial waste management program was done in Kavir Steel Complex, in Aran va Bidgol region to identify and classify industrial waste and also to present solutions for improving waste management. In this complex, production process is hot rolling steel and the product is rebar. Material and Method: The preset study was conducted in Kavir Steel Complex. Following survey of production process and sources of waste, the type and volume of produced waste were identified and measured during 3 months. Then, the classification of wastes was done according to the Bazel Convention and Resource Conservation and Recovery Act (RCRA, and finally new industrial & health solid waste management program was presented. Result: Considering the volume, industrial waste of production process in Kavir Steel Complex was between 130 to 180 grams per each ton of rebar. Main industrial waste included oxide of steel billet, industrial sludge, used oil and lubricant which were classified according to the RCRA: 8 materials with T code, 1 with C code, 5 with I code and 3 materials with C code. Conclusion: The results revealed that the most amount of industrial waste in Kavir Steel Complex is the waste of steel billet and industrial sludge, and more than 90% of Kavir steel industrial waste were reused and recycled inside or outside of this complex. It is recommended that used oil to be transport and maintain in the safe containers.

  14. Listed waste determination report. Environmental characterization

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    On September 23, 1988, the US Environmental Protection Agency (EPA) published a notice clarifying interim status requirements for the management of radioactive mixed waste thereby subjecting the Idaho National Engineering Laboratory (INEL) and other applicable Department of Energy (DOE) sites to regulation under the Resource Conservation and Recovery Act (RCRA). Therefore, the DOE was required to submit a Part A Permit application for each treatment, storage, and disposal (TSD) unit within the INEL, defining the waste codes and processes to be regulated under RCRA. The September 1990 revised Part A Permit application, that was approved by the State of Idaho identified 101 potential acute and toxic hazardous waste codes (F-, P-, and U- listed wastes according to 40 CFR 261.31 and 40 CFR 261.33) for some TSD units at the Idaho Chemical Processing Plant. Most of these waste were assumed to have been introduced into the High-level Liquid Waste TSD units via laboratory drains connected to the Process Equipment Waste (PEW) evaporator (PEW system). At that time, a detailed and systematic evaluation of hazardous chemical use and disposal practices had not been conducted to determine if F-, P-, or Unlisted waste had been disposed to the PEW system. The purpose of this investigation was to perform a systematic and detailed evaluation of the use and disposal of the 101 F-, P-, and Unlisted chemicals found in the approved September 1990 Part A Permit application. This investigation was aimed at determining which listed wastes, as defined in 40 CFR 261.31 (F-listed) and 261.33 (P & Unlisted) were discharged to the PEW system. Results of this investigation will be used to support revisions to the RCRA Part A Permit application.

  15. Listed waste determination report

    International Nuclear Information System (INIS)

    1993-06-01

    On September 23, 1988, the US Environmental Protection Agency (EPA) published a notice clarifying interim status requirements for the management of radioactive mixed waste thereby subjecting the Idaho National Engineering Laboratory (INEL) and other applicable Department of Energy (DOE) sites to regulation under the Resource Conservation and Recovery Act (RCRA). Therefore, the DOE was required to submit a Part A Permit application for each treatment, storage, and disposal (TSD) unit within the INEL, defining the waste codes and processes to be regulated under RCRA. The September 1990 revised Part A Permit application, that was approved by the State of Idaho identified 101 potential acute and toxic hazardous waste codes (F-, P-, and U- listed wastes according to 40 CFR 261.31 and 40 CFR 261.33) for some TSD units at the Idaho Chemical Processing Plant. Most of these waste were assumed to have been introduced into the High-level Liquid Waste TSD units via laboratory drains connected to the Process Equipment Waste (PEW) evaporator (PEW system). At that time, a detailed and systematic evaluation of hazardous chemical use and disposal practices had not been conducted to determine if F-, P-, or Unlisted waste had been disposed to the PEW system. The purpose of this investigation was to perform a systematic and detailed evaluation of the use and disposal of the 101 F-, P-, and Unlisted chemicals found in the approved September 1990 Part A Permit application. This investigation was aimed at determining which listed wastes, as defined in 40 CFR 261.31 (F-listed) and 261.33 (P ampersand Unlisted) were discharged to the PEW system. Results of this investigation will be used to support revisions to the RCRA Part A Permit application

  16. SENSITIVITY ANALYSIS FOR SALTSTONE DISPOSAL UNIT COLUMN DEGRADATION ANALYSES

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G.

    2014-10-28

    PORFLOW related analyses supporting a Sensitivity Analysis for Saltstone Disposal Unit (SDU) column degradation were performed. Previous analyses, Flach and Taylor 2014, used a model in which the SDU columns degraded in a piecewise manner from the top and bottom simultaneously. The current analyses employs a model in which all pieces of the column degrade at the same time. Information was extracted from the analyses which may be useful in determining the distribution of Tc-99 in the various SDUs throughout time and in determining flow balances for the SDUs.

  17. Impact of the resource conservation and recovery act on energy facility siting

    International Nuclear Information System (INIS)

    Tevepaugh, C.W.

    1982-01-01

    The Resource Conservation and Recovery Act (RCRA) of 1976 is a multifaceted approach to the management of both solid and hazardous waste. The focus of this research is on the RCRA mandated proposed regulations for the siting of hazardous waste disposal facilities. This research is an analysis of the interactions among hazardous waste disposal facilities, energy supply technologies and land use issues. This study addresses the impact of RCRA hazardous waste regulations in a descriptive and exploratory manner. A literature and legislative review, interviews and letters of inquiry were synthesized to identify the relationship between RCRA hazardous waste regulations and the siting of selected energy supply technologies. The results of this synthesis were used to determine if and how RCRA influences national land use issues. It was found that the interaction between RCRA and the siting of hazardous waste disposal facilities required by energy supply technologies will impact national land use issues. All energy supply technologies reviewed generate hazardous waste. The siting of industrial functions such as energy supply facilities and hazardous waste disposal facilities will influence future development patterns. The micro-level impacts from the siting of hazardous waste disposal facilities will produce a ripple effect on land use with successive buffer zones developing around the facilities due to the interactive growth of the land use sectors

  18. Hybrid disposal systems and nitrogen removal in individual sewage disposal systems

    Energy Technology Data Exchange (ETDEWEB)

    Franks, A.L.

    1993-06-01

    The use of individual disposal systems in ground-water basins that have adverse salt balance conditions and/or geologically unsuitable locations, has become a major problem in many areas of the world. There has been much research in design of systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of the treated waste in areas with adverse geologic conditions and systems for the removal of nitrogen and phosphorus prior to percolation to the ground water. This paper outlines the history of development and rationale for design and construction of individual sewage disposal systems and describes the designs and limitations of the hybrid and denitrification units. The disposal systems described include Mounds, Evapotranspiration and Evapotranspiration/Infiltration systems. The denitrification units include those using methanol, sulfur and limestone, gray water and secondary treated wastewater for energy sources.

  19. Development of the geologic waste disposal programme in the United States of America

    International Nuclear Information System (INIS)

    Coffman, F.E.; Ballard, W.W.; Carbiener, W.A.

    1983-01-01

    Although alternative concepts are being studied as future options, over at least the next few decades the United States of America is committed to the disposal of commercially generated high-level and transuranic nuclear waste (HLW and TRU) in mined geologic repositories. A 10,000-year minimum isolation period is sought. Responsibility for the management and disposal of United States nuclear waste, in accordance with standards and regulations established, respectively, by the Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC), resides with the Department of Energy (DOE). The DOE National Waste Terminal Storage (NWTS) Program has been implemented to provide the facilities and develop the requisite technology for the disposal of HLW and TRU. The NWTS Program is highly structured, adequately funded, and realistically scheduled. The timely realization of its objectives is basic to the furtherance of the new national energy policy being defined by President Reagan and the United States Congress. The first NWTS repository is scheduled to be operational as early as 1998. The host-rock formation, selected on the basis of the results of at-depth investigations via exploratory shafts to be sunk in 1983-1985 at three potential sites previously extensively characterized by surface techniques, will be either basalt, volcanic tuff, or domed or bedded salt. Selection of one site in these formations will not necessarily disqualify others. Also, screening studies of granitic formations in the United States for the siting of later, regionally located repositories are currently being conducted. Each NWTS repository will be licensed by the NRC. The first application for a construction authorization will probably be submitted in 1988. The application will be submitted for a site to be selected in 1987

  20. Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, Sandra M.

    1997-01-01

    Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

  1. Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

    International Nuclear Information System (INIS)

    Bell, J.T.; Haas, P.A.; Rudolph, J.C.

    1993-01-01

    The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the development of separation technologies that are necessary for the complete treatment of mixed wastes. The residues from the MSO treatment of the mixed wastes must be processed further to separate the radioactive components, to concentrate and recycle residues, or to convert the residues into forms acceptable for final disposal. This paper is a review of the MSO requirements for separation technologies, the information now available, and the concepts for our development studies

  2. The CAMU Rule: A tool for implementing a protective, cost-effective remedy at the Fernald Environmental Management Project

    International Nuclear Information System (INIS)

    Dupuis-Nouille, E.M.; Goidell, L.C.; Strimbu, M.J.

    1995-01-01

    The Fernald Environmental Management Project (FEMP) is a former uranium processing facility currently under remediation pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act as amended (CERCLA). Contamination at the FEMP consists of low-level radioactivity, hazardous substances, hazardous wastes and/or mixed wastes. Regulations promulgated under the Resource Conservation and Recovery Act as amended (RCRA) are evaluated as applicable or relevant and appropriate requirements (ARARs) for remediation of the FEMP. Historically, joint CERCLA-RCRA guidance dictated that hazardous waste could not be treated, or moved out of the designated area of contiguous contamination (AOC), without triggering land disposal restrictions (LDRs) or minimum technology requirements (MTRs). To avoid invoking these stringent requirements, in situ capping was chosen as the lower cost remedy at many sites, although on-site disposal and/or treatment of hazardous wastes would have been more protective. The Corrective Action Management Units (CAMUs) and Temporary Units (TUs) Final Rule [58 FR 8658, Vol. 58, No. 29, hereinafter the open-quotes CAMU Ruleclose quotes], promulgated on February 16, 1993, provides facilities regulated under RCRA corrective action authority with greater flexibility to move, treat, and dispose of wastes on site without triggering LDRs or MTRs, thereby encouraging application of innovative technologies and more protective remedies. The waste acceptance criteria for the on-site disposal facility is based on site-specific considerations including the mobility of the contaminants through the underlying site geology and the protectiveness of the engineered liners. Application of the open-quotes CAMU Ruleclose quotes allows for disposition in the on-site facility based on these technical considerations rather than on regulatory classifications

  3. Geophysical investigation of the 116-H-1 liquid waste disposal trench, 100-HR-1 operable unit

    International Nuclear Information System (INIS)

    Bergstrom, K.A.; Mitchell, T.H.

    1996-04-01

    A geophysical investigation and data integration were conducted for the 116-H-1 Liquid Waste Disposal Trench, which is located in the 100-HR-1 Operable Unit. The 116-H-1 Liquid Waste Disposal Trench is also known as the 107-H Liquid Waste Disposal Trench, the 107-H Rupture Effluent Trench, and the 107-H Trench (Deford and Einan 1995). The trench was primarily used to hold effluent from the 107-H Retention Basin that had become radioactive from contact with ruptured fuel elements. The effluent may include debris from the ruptured fuel elements (Koop 1964). The 116-H-1 Liquid Waste Disposal Trench was also used to hold water and sludge from the 107-H Retention Basin during the basin's deactivation in 1965

  4. Proposed modifications to the RCRA post-closure permit for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Bear Creek Hydrogeologic Regime (BCHR). These permit conditions define the requirements for RCRA post-closure corrective action groundwater monitoring at the S-3 Ponds, the Oil Landfarm, and the Bear Creek Burial Grounds (units A, C-West, and Walk-in Pits). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for the Bear Creek Valley (BCV) Watershed, (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA post-closure corrective action monitoring program during 1996, and (3) update applicable technical procedures with revised versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP). With these modifications, the Y-12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2.0 provides the technical justification for each proposed permit modification. The proposed changes to permit language are provided in Section 3.0 (S-3 Ponds), Section 4.0 (Oil Landfarm), and Section 5.0 (Bear Creek Burial Grounds). Sections 6.0 and 7.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the PCP Attachments

  5. Proposed modifications to the RCRA post-closure permit for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Bear Creek Hydrogeologic Regime (BCHR). These permit conditions define the requirements for RCRA post-closure corrective action groundwater monitoring at the S-3 Ponds, the Oil Landfarm, and the Bear Creek Burial Grounds (units A, C-West, and Walk-in Pits). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for the Bear Creek Valley (BCV) Watershed, (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA post-closure corrective action monitoring program during 1996, and (3) update applicable technical procedures with revised versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP). With these modifications, the Y-12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2.0 provides the technical justification for each proposed permit modification. The proposed changes to permit language are provided in Section 3.0 (S-3 Ponds), Section 4.0 (Oil Landfarm), and Section 5.0 (Bear Creek Burial Grounds). Sections 6.0 and 7.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the PCP Attachments.

  6. Liners and Leak Detection Systems for Hazardous Waste Land Disposal Units - Federal Register Notice, January 29, 1992

    Science.gov (United States)

    The EPA is amending its current regulations under the Resource Conservation and Recovery Act (RCRA) concerning liner and leachate collection and removal systems for hazardous waste surface impoundments, landfills, and waste piles.

  7. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    Energy Technology Data Exchange (ETDEWEB)

    Wickline, Alfred

    2005-12-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting

  8. Recycling and disposal of FUSRAP materials from the Ashland 2 site at a licensed uranium mill

    International Nuclear Information System (INIS)

    Howard, B.; Conboy, D.; Rehmann, M.; Roberts, H.

    1999-01-01

    During World War II the Manhattan Engineering District (MED) used facilities near Buffalo, N.Y. to extract natural uranium from ores. Some of the byproduct material left from the ores (MED byproduct), containing low levels of uranium, thorium, and radium, was deposited on a disposal site known as Ashland 2, located in Tonawanda, NY. On behalf of the United States Army Corps of Engineers (USACE, or the Corps), ICF Kaiser Engineers (ICFKE) was tasked to provide the best value clean-up results that meet all of the criteria established in the Record of Decision for the site. International Uranium (USA) Corporation (IUC), the operator of the White Mesa Uranium Mill, a Nuclear Regulatory Commission (NRC)-licensed mill near Blanding, Utah, was selected to perform uranium extraction on the excavated materials, therefore giving the best value as it provided beneficial use of the material consistent with the Resource Conservation and Recovery Act (RCRA) intent to encourage recycling and recovery, while also providing the most cost-effective means of disposal. Challenges overcome to complete this project included (1) identifying the best-value location to accept the material; (2) meeting regulatory requirements with IUC obtaining an NRC license amendment to accept and process the material as an alternate feed; (3) excavating and preparing the material for shipment, then shipping the material to the Mill for uranium recovery; and (4) processing the material, followed by disposal of tailings from the process in the Mill's licensed uranium tailings facility. Excavation from Ashland 2 and processing of the Ashland 2 material at the White Mesa Mill resulted in a cleaner environment at Tonawanda, a cost avoidance of up to $16 million, beneficial recovery of source material, and environmentally protective disposal of byproduct material. (author)

  9. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2009-07-31

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed

  10. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2009-01-01

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was

  11. Treatment/Disposal Plan for Drummed Waste from the 300-FF-1 Operable Unit, 618-4 Burial Ground

    International Nuclear Information System (INIS)

    Lerch, J.A.

    1999-01-01

    The objective of this plan is to support selection of a safe, environmentally responsible, and cost-effective treatment and disposal method for drums containing depleted uranium metal chips submerged in oil that have been and will be excavated from the 618-4 Burial Ground. Remediation of the 300-FF-1 Operable Unit, 618-4 Burial Ground was initiated in fiscal year (FY) 1998 as an excavation and removal operation. Routine processes were established to excavate and ship contaminated soil and debris to the Environmental Restoration Disposal Facility (ERDF) for disposal

  12. Safety assessment and licensing issues of low level radioactive waste disposal facilities in the United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Fearnley, I. G. [British Nuclear Fuels Ltd., Sellafield (United Kingdom)

    1997-12-31

    More than 90% of radioactive waste generated in the United Kingdom is classified as low level and is disposed of in near surface repositories. BNFL owns and operates the principal facility for the disposal of this material at Drigg in West Cumbria. In order to fully optimise the use of the site and effectively manage this `national` resource a full understanding and assessment of the risks associated with the performance of the repository to safely contain the disposed waste must be achieved to support the application for the site authorization for disposal. This paper describes the approaches adopted by BNFL to reviewing these risks by the use of systematic Safety and Engineering Assessments supported in turn by experimental programmes and computations models. (author). 6 refs., 1 tab., 4 figs.

  13. Safety assessment and licensing issues of low level radioactive waste disposal facilities in the United Kingdom

    International Nuclear Information System (INIS)

    Fearnley, I. G.

    1997-01-01

    More than 90% of radioactive waste generated in the United Kingdom is classified as low level and is disposed of in near surface repositories. BNFL owns and operates the principal facility for the disposal of this material at Drigg in West Cumbria. In order to fully optimise the use of the site and effectively manage this 'national' resource a full understanding and assessment of the risks associated with the performance of the repository to safely contain the disposed waste must be achieved to support the application for the site authorization for disposal. This paper describes the approaches adopted by BNFL to reviewing these risks by the use of systematic Safety and Engineering Assessments supported in turn by experimental programmes and computations models. (author). 6 refs., 1 tab., 4 figs

  14. Calculations of the radiological impact of disposal of unit activity of selected radionuclides for use in waste management system studies

    International Nuclear Information System (INIS)

    Smith, G.M.

    1985-03-01

    The purpose of the work described is to provide estimates of the radiological impact following disposal of unit activity via each of several options, including shallow burial, engineered trench disposal, disposal in a geologic repository and disposal on the deep ocean bed. Results are presented for a range of important representative radionuclides. No single option is clearly the best from the radiological point of view. However, in conjunction with waste inventory data the results may be used to provide a preliminary view of the relative radiological merits of the various disposal options. (author)

  15. Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?

    International Nuclear Information System (INIS)

    Devgun, J.S.; Larson, G.S.

    1995-01-01

    It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

  16. Development of low-level radioactive waste disposal capacity in the United States -- Progress or stalemate?

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1995-01-01

    It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The US nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW -- industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW -- face the same storage and cost uncertainties. This paper will summarize the current status of US low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

  17. DOE Land Disposal Restrictions Strategy Report for Radioactive Mixed Waste

    International Nuclear Information System (INIS)

    1989-09-01

    This report represents an effort by the Department of Energy (DOE) and its contractors to develop a strategy for achieving radioactive mixed waste (RMW) compliance with the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDR). Preliminary information provided by the Operations Offices has been reviewed to formulate an overall strategy that will enable DOE operations to comply with the Land Disposal Restrictions. The effort has concluded that all DOE Operations Offices are impacted by LDR due to the inability to meet existing and future LDR storage prohibition requirements or treatment standards for RMW. A total of 178 RMW streams subject to LDR are identified in this report. Quantities of RMW impacted by LDR have been estimated at approximately 710,785 cubic meters. DOE must place a high priority on resolving LDR compliance issues. Failure to resolve these issues could result in the curtailment of waste generating operations at DOE facilities. Actions will be required from both DOE (Headquarters and Operations Offices) and EPA in order to achieve DOE complex-wide compliance. Specific recommendations are included. 1 fig., 4 tabs

  18. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    International Nuclear Information System (INIS)

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR section 261.4(a)(4), ''Identification and Listing of Hazardous Waste,'' as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues

  19. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR {section}261.4(a)(4), ``Identification and Listing of Hazardous Waste,`` as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues.

  20. Control of water infiltration into near surface LLW disposal units

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

    1992-10-01

    The project objective is to assess means for controlling waste infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large scale lysimeters (70inch x 45inch x lOinch) at Beltsville, MD and results of the assessment are applicable to disposal of LLW, uranium mill tailings, hazardous waste, and sanitary landfills. Three concepts are under investigation: (1) resistive layer barrier, (2) conductive layer barrier, and bioengineering water management. The resistive layer barrier consists of compacted earth (clay). The conductive layer barrier is a special case of the capillary barrier and it requires a flow layer (e.g. fine sandy loam) over a capillary break. As long as unsaturated conditions am maintained water is conducted by the flow layer to below the waste. This barrier is most efficient at low flow rates and is thus best placed below a resistive layer barrier. Such a combination of the resistive layer over the conductive layer barrier promises to be highly effective provided there is no appreciable subsidence. Bioengineering water management is a surface cover that is designed to accommodate subsidence. It consists of impermeable panels which enhance run-off and limit infiltration. Vegetation is planted in narrow openings between panels to transpire water from below the panels. TWs system has successfully dewatered two lysimeters thus demonstrating that this procedure could be used for remedial action (''drying out'') existing water-logged disposal sites at low cost

  1. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Protection and Technical Services

    2009-09-30

    This permit application provides facility information on the design, processes, and security features associated with the proposed Mixed Waste Disposal Unit. The unit will receive and dispose of onsite and offsite containerized low-level mixed waste (LLMW) that has an approved U.S. Department of Energy nexus.

  2. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site

    International Nuclear Information System (INIS)

    2009-01-01

    This permit application provides facility information on the design, processes, and security features associated with the proposed Mixed Waste Disposal Unit. The unit will receive and dispose of onsite and offsite containerized low-level mixed waste (LLMW) that has an approved U.S. Department of Energy nexus.

  3. RCRA facility investigation for the townsite of Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    Dorries, A.M.; Conrad, R.C.; Nonno, L.M.

    1992-01-01

    During World War II, Los Alamos, New Mexico was established as an ideal location for the secrecy and safety needed for the research and development required to design a nuclear fission bomb. Experiments carried out in the 1940s generated both radioactive and hazardous waste constituents on what is presently part of the Los Alamos townsite. Under the RCRA permit issued to Los alamos national Laboratory in 1990, the Laboratory is scheduled for investigation of its solid waste management units (SWMUs). The existing information on levels of radioactivity on the townsite is principally data from soil samples taken during the last site decontamination in 1976, little information on the presence of hazardous constituents exists today. This paper addresses pathway analysis and a preliminary risk assessment for current residents of the Los Alamos townsite. The estimated dose levels, in mrem per year, show that the previously decontaminated SWMU areas on the Los Alamos townsite will not contribute a radiation dose of any concern to the current residents

  4. New York vs. United States: Federalism and the disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    Weiner, R.D.

    1994-01-01

    Although 97 percent of LLRW is so slightly radioactive that it requires little or no shielding to protect the public, the remaining 3 percent consists of materials that must be shielded for periods ranging from 300 to several thousand years. Some of the material classified as LLRW contains open-quotes open-quote hot spots close-quote, where concentrations of radioactivity may be quite high.close quotes Even aside from such hot spots, LLRW poses a threat to human health. While nuclear power plants generate the bulk of LLRW, a significant quantity of LLRW is generated by industry, and academic and medical institutions. States are allowed to regulate LLRW that is generated by the private sector, as long as the regulations are compatible with, and at least as restrictive as, those of the NRC. However, states may not regulate LLRW generated by NRC-licensed nuclear power plants. The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLR-WPAA, or the Act) attempted to solve the problem of insufficient LLRW disposal capacity in the United States by further shifting responsibility for LLRW disposal to the states. The Act required each state to provide an approved disposal site that could be located either within that state or within a region formed by a compact including that state. In June, 1992, the United States Supreme Court struck down a key provision of the Act that would have forced a state to take title to all LLRW generated within its borders if that state failed to meet a 1996 deadline for providing such a disposal site. This note will examine the constitutional basis for, and the consequences of, that decision. In addition, this note will suggest that the Court's new criterion for determining when a federal statute violates principles of federalism be replaced by a more coherent and workable test resting on a theory of political accountability and on the Guarantee Clause of the United States Constitution

  5. Coal combustion waste management study

    International Nuclear Information System (INIS)

    1993-02-01

    Coal-fired generation accounted for almost 55 percent of the production of electricity in the United States in 1990. Coal combustion generates high volumes of ash and flue gas desulfurization (FGD) wastes, estimated at almost 90 million tons. The amount of ash and flue gas desulfurization wastes generated by coal-fired power plants is expected to increase as a result of future demand growth, and as more plants comply with Title IV of the 1990 Clean Air Act Amendments. Nationwide, on average, over 30 percent of coal combustion wastes is currently recycled for use in various applications; the remaining percentage is ultimately disposed in waste management units. There are a significant number of on-site and off-site waste management units that are utilized by the electric utility industry to store or dispose of coal combustion waste. Table ES-1 summarizes the number of disposal units and estimates of waste contained at these unites by disposal unit operating status (i.e, operating or retired). Further, ICF Resources estimates that up to 120 new or replacement units may need to be constructed to service existing and new coal capacity by the year 2000. The two primary types of waste management units used by the industry are landfills and surface impoundments. Utility wastes have been exempted by Congress from RCRA Subtitle C hazardous waste regulation since 1980. As a result of this exemption, coal combustion wastes are currently being regulated under Subtitle D of RCRA. As provided under Subtitle D, wastes not classified as hazardous under Subtitle C are subject to State regulation. At the same time Congress developed this exemption, also known as the ''Bevill Exclusion,'' it directed EPA to prepare a report on coal combustion wastes and make recommendations on how they should be managed

  6. Annual report of 1991 groundwater monitoring data for the Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin at the Y-12 Plant: Ground water surface elevations

    International Nuclear Information System (INIS)

    Shevenell, L.; Switek, J.

    1992-02-01

    The purpose of this document is to provide a summary and interpretation of hydraulic head measurements obtained from wells surrounding the Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin sites at the US Department of Energy Y-12 Plant in Oak Ridge, Tennessee. Periodic water level observations are presented using hydrographs and water table contour maps based on data obtained from quarterly sampling during calendar year 1991. Generalized, preliminary interpretation of results are presented. The two sites covered by this report have interim status under the provisions of the Resource Conservation and Recovery Act (RCRA). A subset of the wells at each rate are used for groundwater monitoring purposes under the requirements of RCRA. A discussion of the up-gradient and down-gradient directions for each of the sites is included

  7. ORGDP RCRA/PCB

    International Nuclear Information System (INIS)

    Rodgers, T.

    1986-01-01

    A dual purpose solid/liquid incinerator is currently being constructed at the Oak Ridge Gaseous Diffusion Plant [ORGDP (K-25)] to destroy uranium contaminated, hazardous organic wastes in compliance with the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). These wastes are generated by the gaseous diffusion plants in Oak Ridge, TN; Paducah, KY; and Portsmouth, OH. In addition, waste will also be received from the Y-12 Plant, Oak Ridge National Laboratory (ORNL), and the Feed Materials Production Center (FMPC). Destruction of PCBs and hazardous liquid organic wastes will be accomplished in a rotary kiln incinerator with an afterburner. This system was selected after a study of various alternatives which are covered in Report No. X-OE-141. Incineration was chosen because it is dependable, permanent, detoxifies organics, and reduces volume. The rotary kiln incinerator was selected because it can thermally destroy organic constituents of liquids, solids, and sludges to produce an organically inert ash. The incineration system, off-gas treatment system, and related instrumentation and controls are being provided by International Waste Energy Systems (IWES) which is responsible for design, construction, startup, and performance testing

  8. Verification of Sulfate Attack Penetration Rates for Saltstone Disposal Unit Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-05-12

    Recent Special Analysis modeling of Saltstone Disposal Units consider sulfate attack on concrete and utilize degradation rates estimated from Cementitious Barriers Partnership software simulations. This study provides an independent verification of those simulation results using an alternative analysis method and an independent characterization data source. The sulfate penetration depths estimated herein are similar to the best-estimate values in SRNL-STI-2013-00118 Rev. 2 and well below the nominal values subsequently used to define Saltstone Special Analysis base cases.

  9. Institutional aspects of siting nuclear waste disposal facilities in the United States

    International Nuclear Information System (INIS)

    Stewart, John Cameron.; Prichard, Clark. W.

    1987-01-01

    This chapter deals with the institutional issues associated with the disposal of nuclear waste in the United States of America. These include socio-economic, financial, land use and especially, political factors. Institutional issues must, however, be resolved, as well as the technological problems of engineering and geology. The general issues are first examined, then the organisation and financing, land use, community acceptance, transport problems and finally, local economic impacts. (UK)

  10. Self-assembled monolayers on mosoporous supports (SAMMS) for RCRA metal removal

    Energy Technology Data Exchange (ETDEWEB)

    Feng, Xiangdong; Liu, Jun; Fryxell, G. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-10-01

    The Mixed Waste Focus Area has declared mercury removal and stabilization as the first and fourth priorities among 30 prioritized deficiencies. Resource Conservation and Recovery Act (RCRA) metal and mercury removal has also been identified as a high priority at DOE sites such as Albuquerque, Idaho Falls, Oak Ridge, Hanford, Rocky Flats, and Savannah River. Under this task, a proprietary new technology, Self-Assembled Monolayers on Mesoporous Supports (SAMMS), for RCRA metal ion removal from aqueous wastewater and mercury removal from organic wastes such as vacuum pump oils is being developed at Pacific Northwest National Laboratory (PNNL). The six key features of the SAMMS technology are (1) large surface area (>900 m{sup 2}/g) of the mesoporous oxides (SiO{sub 2}, ZrO{sub 2}, TiO{sub 2}) ensures high capacity for metal loading (more than 1 g Hg/g SAMMS); (2) molecular recognition of the interfacial functional groups ensures the high affinity and selectivity for heavy metals without interference from other abundant cations (such as calcium and iron) in wastewater; (3) suitability for removal of mercury from both aqueous wastes and organic wastes; (4) the Hg-laden SAMMS not only pass TCLP tests, but also have good long-term durability as a waste form because the covalent binding between mercury and SAMMS has good resistance to ion exchange, oxidation, and hydrolysis; (5) the uniform and small pore size (2 to 40 nm) of the mesoporous silica prevents bacteria (>2000 nm) from solubilizing the bound mercury; and (6) SAMMS can also be used for RCRA metal removal from gaseous mercury waste, sludge, sediment, and soil.

  11. Record of Decision Remedial Alternative Selection for the Gunsite 113 Access Road (631-24G) Operable Unit: Final Action

    International Nuclear Information System (INIS)

    Palmer, E.

    1997-01-01

    This decision document presents the selected remedial action for the Gunsite 113 Access Road Unit located at the Savannah River Site near Aiken, SC. The selected action was developed in accordance with CERCLA, as amended, and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). The selected remedy satisfies both CERCLA and RCRA 3004(U) requirements. This decision is based ont he Administrative Record File for this specific RCRA/CERCLA Unit

  12. The disposal of orphan wastes using the greater confinement disposal concept

    International Nuclear Information System (INIS)

    Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H.; Dickman, P.T.

    1991-01-01

    In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ''home'' for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ''special-case'' or ''orphan'' wastes. This paper describes an ongoing project sponsored by the DOE's Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs

  13. Remedial investigation work plan for Bear Creek Valley Operable Unit 2 (Rust Spoil Area, SY-200 Yard, Spoil Area 1) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-05-01

    The enactment of the Resource Conservation and Recovery Act (RCRA) in 1976 and the Hazardous and Solid Waste Amendments (HSWA) to RCRA in 1984 created management requirements for hazardous waste facilities. The facilities within the Oak Ridge Reservation (ORR) were in the process of meeting the RCRA requirements when ORR was placed on the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) National Priorities List (NPL) on November 21, 1989. Under RCRA, the actions typically follow the RCRA Facility Assessment (RFA)/RCRA Facility Investigation (RFI)/Corrective Measures Study (CMS)/Corrective Measures implementation process. Under CERCLA the actions follow the PA/SI/Remedial Investigation (RI)/Feasibility Study (FS)/Remedial Design/Remedial Action process. The development of this document will incorporate requirements under both RCRA and CERCLA into an RI work plan for the characterization of Bear Creek Valley (BCV) Operable Unit (OU) 2

  14. Land disposal restriction (LDR) waste management strategy at Rocky Flats

    International Nuclear Information System (INIS)

    Tyler, R.W.; Anderson, S.A.; Rising, T.L.

    1993-01-01

    The Rocky Flats Plant (RFP) is a government-owned, contractor-operated facility which is a part of the nationwide DOE nuclear weapons production complex. Rocky Flats has accumulated (and will continue to generate) a substantial quantity of mixed waste subject to regulation under the land disposal restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). These waste streams include low level mixed waste and transuranic mixed waste which are LDR primarily due to solvent and heavy metal contamination. DOE and EPA have entered into a Federal Facility Compliance Agreement (FFCA) which requires actions to be taken to ensure the accurate identification, safe storage and minimization of LDR mixed wastes prior to their ultimate treatment and/or disposal. As required by the FFCA, DOE has prepared a Comprehensive Treatment and Management Plant (CTMP) which describes the strategy and commitments for bringing LDR wastes at RFP into compliance with applicable regulations. This strategy includes waste characterization and reclassification, utilization of existing commercial and DOE treatment capacity, as well as, the development and implementation of treatment systems (and other management systems) for the purpose of achieving LDR regulatory compliance and ultimate waste disposal. This paper will give an overview of this strategy including a description of the major waste streams being addressed, the regulatory drivers, and plans and status of ongoing treatment systems technology development and implementation efforts

  15. RCRA corrective action for underground storage tanks -- Subtitle C for Subtitle I

    International Nuclear Information System (INIS)

    1995-08-01

    The purpose of this report is to provide guidance to DOE and DOE contractor personnel responsible for planning and implementation of corrective measures addressing cleanup of releases of hazardous materials or regulated substances from underground storage tanks regulated under RCRA Subtitle C or Subtitle I

  16. RCRA, a state perspective: the buck should stop with us

    Energy Technology Data Exchange (ETDEWEB)

    McCall, III, M N

    1977-11-01

    The states must carry the ball of realizing the Resource Conservation and Recovery Act (RCRA); state agencies and the EPA can work together, though they don't always agree; adequate funding is absolutely necessary. The states' perspective of their role is threefold-regulation, assistance, and leadership, with maximum input into implementation. A National Governors' Association committee on waste management was established. Neither RCRA itself nor supporting committee reports allow definition of open dumps and sanitary landfills with other than traditional meaning. Conducting the open dump inventory should be the responsibility of the states, with financial support from EPA. The existence of state nonimportation laws should not preclude that state from receiving money for a hazardous waste program. The criteria for defining hazardous wastes must be realistic if an unmanageable list is to be avoided. State solid waste management agencies must provide aid to local government and private industry. The state-not EPA- is the best level of government to carry out an effective solid waste program. The Federal program should concentrate on resource and energy conservation, research and development, demonstration projects, establishing markets for recycled materials, and education and training programs. Planning should be coordinated through state agencies.

  17. Development of a unit cell model for interim performance assessment of vitrified low level waste disposal

    International Nuclear Information System (INIS)

    Kline, N.W.

    1995-09-01

    The unit cell modeling approach has been developed and used in analysis of some design options for a vitrified low level waste disposal facility. The unit cell modeling approach is likely to be useful in interim performance assessment for the facility. The present unit cell model will probably need to be refitted in terms of some model parameters for the latter purpose. Two present disposal facility concepts differ in the length of a capillary barrier proposed to limit effective recharge through the top of the facility. Results of the study summarized herein suggest design of a capillary barrier which can reduce a recharge rate of 0.1 cm/yr by one or two orders of magnitude seems feasible for both concepts. A benchmark comparison of the unit cell model against a full facility model shows comparable predictive accuracy in less than one percent of the computer time. Results suggest that model parameters include capillary barrier performance, inter-canister spacing, rate of moisture withdrawal due to glass corrosion, contaminant inventory, and the well interceptor factor. It is also important that variations of waste form hydraulic parameters suggest that transport through the waste form is dominated by diffusion

  18. Food waste disposal units in UK households: the need for policy intervention.

    Science.gov (United States)

    Iacovidou, Eleni; Ohandja, Dieudonne-Guy; Voulvoulis, Nikolaos

    2012-04-15

    The EU Landfill Directive requires Member States to reduce the amount of biodegradable waste disposed of to landfill. This has been a key driver for the establishment of new waste management options, particularly in the UK, which in the past relied heavily on landfill for the disposal of municipal solid waste (MSW). MSW in the UK is managed by Local Authorities, some of which in a less conventional way have been encouraging the installation and use of household food waste disposal units (FWDs) as an option to divert food waste from landfill. This study aimed to evaluate the additional burden to water industry operations in the UK associated with this option, compared with the benefits and related savings from the subsequent reductions in MSW collection and disposal. A simple economic analysis was undertaken for different FWD uptake scenarios, using the Anglian Region as a case study. Results demonstrated that the significant savings from waste collection arising from a large-scale uptake of FWDs would outweigh the costs associated with the impacts to the water industry. However, in the case of a low uptake, such savings would not be enough to cover the increased costs associated with the wastewater provision. As a result, this study highlights the need for policy intervention in terms of regulating the use of FWDs, either promoting them as an alternative to landfill to increase savings from waste management, or banning them as a threat to wastewater operations to reduce potential costs to the water industry. Copyright © 2012 Elsevier B.V. All rights reserved.

  19. Performance test results of noninvasive characterization of RCRA surrogate waste by prompt gamma neutron activation analysis

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Propp, W.A.

    1997-11-01

    A performance evaluation to determine the feasibility of using prompt gamma neutron activation analysis (PGNAA) for noninvasive, quantitative assay of mixed waste containers was sponsored by DOE's Office of Technology Development (OTD), the Mixed Waste Focus Area (MWFA), and the Idaho National Engineering and Environmental Laboratory (INEEL). The evaluation was conducted using a surrogate waste, based on Portland cement, that was spiked with three RCRA metals, mercury, cadmium, and lead. The results indicate that PGNAA has potential as a process monitor. However, further development is required to improve its sensitivity to meet regulatory requirements for determination of these RCRA metals

  20. Remedial investigation work plan for Bear Creek Valley Operable Unit 4 (shallow groundwater in Bear Creek Valley) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1992-12-01

    The enactment of the Resource Conservation and Recovery Act (RCRA) in 1976 and the Hazardous and Solid Waste Amendments (HSWA) to RCRA in 1984 created management requirements for hazardous waste fadities. The facilities within the Oak Ridge Reservation (ORR) were in the process of meeting the RCRA requirements when ORR was placed on the Comprehensive Environmental Response, Compensation, and Liability Act (CERCIA) National Priorities List (NPL) on November 21, 1989. Under RCRA, the actions typically follow the RCRA Facility Assessment (RIFA)/RCRA Facility Investigation (RFI)/Coffective Measures Study (CMS)/Corrective Measures Implementation process. Under CERCLA, the actions follow the Pre at sign ary Assessment/Site Investigation (PA/Sl) Remedial Investigation Feasibility Study (RI/FS)/Remedial Design/Remedial Action process. The development of this document will incorporate requirements under both RCRA and CERCIA into an RI Work Plan for the lint phase of characterization of Bear Creek Valley (BCV) Operable Unit (OU) 4

  1. Results of RCRA groundwater quality assessment at the 216-B-3 Pond Facility

    International Nuclear Information System (INIS)

    Barnett, D.B.; Teel, S.S.

    1997-06-01

    This document describes a groundwater quality assessment of the 216-B-3 pond system, a Resources Conservation and Recovery act of 1976 (RCRA) waste facility. In 1990, sampling and chemical analysis of groundwater underlying the facility indicated that the contamination indicator parameters, total organic halogens (TOX), and total organic carbon (TOC) had exceeded established limits in two wells. This discovery placed the facility into RCRA groundwater assessment status and subsequently led to a more detailed hydrochemical analysis of groundwater underlying the facility. Comprehensive chemical analyses of groundwater samples from 1994 through 1996 revealed one compound, tris (2-chloroethyl) phosphate (TRIS2CH), that may have contributed to elevated TOX concentrations. No compound was identified as a contributor to TOC. Detailed evaluations of TOX, TOC, and TRIS2CH and comparison of occurrences of these parameters led to conclusions that (1) with few exceptions, these constituents occur at low concentrations below or near limits of quantitation; (2) it is problematic whether the low concentrations of TRIS2CH represent a contaminant originating from the facility or if it is a product of well construction; and (3) given the low and diminishing concentration of TOX, TOC, and TRIS2CH, no further investigation into the occurrent of these constituents is justified. Continued groundwater monitoring should include an immediate recalculation of background critical means of upgradient/downgradient comparisons and a return to seminannual groundwater monitoring under a RCRA indicator parameter evaluation program

  2. Closure Report (CR) for Corrective Action Unit (CAU) 91: Area 3 U-3fi Injection Well with Errata Sheet and Certification, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Navarro Nevada Environmental Services

    2010-08-10

    The closure report for CAU 91 has no Use Restriction Form or drawing/map included in the document to describe the use restricted area, however, Section 3.3.3 states that the site will be fenced and signage placed indicating the area as a Resource Conservation and Recovery Act (RCRA) Unit. The drawing that was placed in the FFACO indicating the use restricted area lists the coordinates for the RCRA Unit in Nevada State Plan Coordinates - North American Datum of 1983. In the ensuing years the reporting of coordinates has been standardized so that all coordinates are reported in the same manner, which is: NAD 27 UTM Zone 11 N, meters. This Errata Sheet updates the coordinate reporting to the currently accepted method and includes an aerial photo showing the RCRA Unit with the coordinates listed showing the use restricted area.

  3. Degradation Of Cementitious Materials Associated With Saltstone Disposal Units

    International Nuclear Information System (INIS)

    Flach, G. P; Smith, F. G. III

    2013-01-01

    The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed ''saltstone''. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of an SDF disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions. The nominal value (NV) is an intermediate result that is more probable than the conservative estimate

  4. Degradation Of Cementitious Materials Associated With Saltstone Disposal Units

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. P; Smith, F. G. III

    2013-03-19

    The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed “saltstone”. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of an SDF disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions. The nominal value (NV) is an intermediate result that is more probable than the conservative

  5. Annual Hanford Site environmental permitting status report

    International Nuclear Information System (INIS)

    Sonnichsen, J.C.

    1998-01-01

    The information contained and/or referenced in this Annual Hanford Site Environmental Permitting Status Report (Status Report) addresses the State Environmental Policy Act (SEPA) of 1971 and Condition II.W. of the Resource Conservation and Recovery Act (RCRA) of 1976 Permit, Dangerous Waste Portion (DW Portion). Condition II.W. of the RCRA Permit specifies the Permittees are responsible for all other applicable federal, state, and local permits for the development and operation of the Hanford Facility. Condition II.W. of the RCRA Permit specifies that the Permittees are to use their best efforts to obtain such permits. For the purposes of permit condition, 'best efforts' means submittal of documentation and/or approval(s) in accordance with schedules specified in applicable regulations, or as determined through negotiations with the applicable regulatory agencies. This Status Report includes information on all existing and anticipated environmental permitting. Environmental permitting required by RCRA, the Hazardous and Solid Waste Amendments (HSWA) of 1984, and non-RCRA permitting (solid waste handling, Clean Air Act Amendments of 1990, Clean Water Act Amendments of 1987, Washington State waste discharge, and onsite sewage system) is addressed. Information on RCRA and non-RCRA is current as of July 31, 1998. For the purposes of RCRA and the State of Washington Hazardous Waste Management Act of 1976 [as administered through the Dangerous Waste Regulations, Washington Active Code (WAC) 173-303], the Hanford Facility is considered a single facility. As such, the Hanford Facility has been issued one US Environmental Protection Agency (EPA)/State Identification Number (WA7890008967). This EPA/State identification number encompasses over 60 treatment, storage, and/or disposal (TSD) units. The Washington State Department of Ecology (Ecology) has been delegated authority by the EPA to administer the RCRA, including mixed waste authority. The RCRA permitting approach for

  6. Treatability study of aqueous, land disposal restricted mixed wastes

    International Nuclear Information System (INIS)

    Haefner, D.R.

    1992-12-01

    Treatment studies have been completed on two aqueous waste streams at the Mixed Waste Storage Facility that are classified as land disposal restricted. Both wastes had mercury and lead as characteristic hazardous constituents. Samples from one of these wastes, composed of mercury and lead sulfide particles along with dissolved mercury and lead, was successfully treated by decanting, filtering, and ion exchanging. The effluent water had an average level of 0.003 and 0.025 mg/L of mercury and lead, respectively. These values are well below the targeted RCRA limits of 0.2 mg/L mercury and 5.0 mg/L lead. An acidic stream, containing the same hazardous metals, was also successfully treated using a treatment process of precipitation, filtering, and then ion exchange. Treatment of another waste was not completely successful, presumably because of the interference of a chelating agent

  7. Remedial investigation work plan for Bear Creek Valley Operable Unit 2 (Rust Spoil Area, SY-200 Yard, Spoil Area 1) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The enactment of the Resource Conservation and Recovery Act (RCRA) in 1976 and the Hazardous and Solid Waste Amendments (HSWA) to RCRA in 1984 created management requirements for hazardous waste facilities. The facilities within the Oak Ridge Reservation (ORR) were in the process of meeting the RCRA requirements when ORR was placed on the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) National Priorities List (NPL) on November 21, 1989. Under RCRA, the actions typically follow the RCRA Facility Assessment (RFA)/RCRA Facility Investigation (RFI)/Corrective Measures Study (CMS)/Corrective Measures implementation process. Under CERCLA the actions follow the PA/SI/Remedial Investigation (RI)/Feasibility Study (FS)/Remedial Design/Remedial Action process. The development of this document will incorporate requirements under both RCRA and CERCLA into an RI work plan for the characterization of Bear Creek Valley (BCV) Operable Unit (OU) 2.

  8. Regulatory approaches in the United States of America for safe management and disposal of long-lived radionuclides

    International Nuclear Information System (INIS)

    Greeves, J.T.; Bell, M.J.; Nelson, R.A.

    1998-01-01

    Regulation of the safe management and disposal of commercial, man-made, long-lived radioactive wastes in the United States is the responsibility of the US Nuclear Regulatory Commission (NRC). In some instances, state regulatory authorities have entered into agreements with the NRC to exercise regulatory authority over management and disposal of low-level radioactive wastes and uranium mill tailings within their borders. The legal and regulatory framework employed to achieve safe management and disposal of long-lived radioactive wastes in the US regulatory system is quite detailed, and in many cases the requirements are considerably prescriptive. The NRC has undertaken an initiative to move in the direction of adopting risk-informed, performance-based and risk-informed, less-prescriptive regulations. The current status and future direction of the legal and regulatory framework for management and disposal of commercial long-lived radioactive waste in the US is described. (author)

  9. B Plant treatment, storage, and disposal (TSD) units inspection plan

    International Nuclear Information System (INIS)

    Beam, T.G.

    1996-01-01

    This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ''Dangerous Waste Regulations'' (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements

  10. A sensitivity analysis of hazardous waste disposal site climatic and soil design parameters using HELP3

    International Nuclear Information System (INIS)

    Adelman, D.D.; Stansbury, J.

    1997-01-01

    The Resource Conservation and Recovery Act (RCRA) Subtitle C, Comprehensive Environmental Response, Compensation, And Liability Act (CERCLA), and subsequent amendments have formed a comprehensive framework to deal with hazardous wastes on the national level. Key to this waste management is guidance on design (e.g., cover and bottom leachate control systems) of hazardous waste landfills. The objective of this research was to investigate the sensitivity of leachate volume at hazardous waste disposal sites to climatic, soil cover, and vegetative cover (Leaf Area Index) conditions. The computer model HELP3 which has the capability to simulate double bottom liner systems as called for in hazardous waste disposal sites was used in the analysis. HELP3 was used to model 54 combinations of climatic conditions, disposal site soil surface curve numbers, and leaf area index values to investigate how sensitive disposal site leachate volume was to these three variables. Results showed that leachate volume from the bottom double liner system was not sensitive to these parameters. However, the cover liner system leachate volume was quite sensitive to climatic conditions and less sensitive to Leaf Area Index and curve number values. Since humid locations had considerably more cover liner system leachate volume than and locations, different design standards may be appropriate for humid conditions than for and conditions

  11. Remedial investigation report on Bear Creek Valley Operable Unit 2 (Rust Spoil Area, Spoil Area 1, and SY-200 Yard) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 1, Main text

    International Nuclear Information System (INIS)

    1994-08-01

    The enactment of the Resource Conservation and Recovery Act (RCRA) in 1976 and the Hazardous and Solid Waste Amendments (HSWA) to RCRA in 1984 created management requirements for hazardous waste facilities. The facilities within the Oak Ridge Reservation (ORR) were in the process of meeting the RCRA requirements when the ORR was placed on the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) National Priorities List (NPL) on November 21, 1989. Under RCRA, the actions typically follow the RCRA Facility Assessment/RCRA Facility Investigation (RFI)/Corrective Measures Study (CMS)/Corrective Measures Implementation process. Under CERCLA, the actions follow the preliminary assessment/site investigation/Remedial Investigation (RI)/Feasibility Study (FS)/Remedial Design/Remedial Action process. This document incorporates requirements under both RCRA and CERCLA in the form of an RI report for the characterization of Bear Creek Valley (BCV) Operable Unit (OU) 2

  12. Management challenges in remediating a mixed waste site at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Riddle, S.P.; Wilson, R.C.; Branscom, K.S.

    1992-07-01

    Martin Marietta Energy Systems, Inc., manages the Oak Ridge National Laboratory (ORNL) for the US Department of Energy (DOE). Since ORNL's beginning in the 1940's, a variety of solid and liquid low-level radioactive waste (LLW), hazardous waste, and mixed waste has been generated. The solid wastes have been disposed of on site, primarily in shallow trenches called solid waste storage areas (SWSAs). SWSA 6, opened in 1969, is the only operational disposal site at ORNL for solid LLW. In 1984, SWSA 6 was closed for three months when it was discovered that wastes regulated by the Resource Conservation and Recovery Act (RCRA) were being inadvertently disposed of there. SWSA 6 was then added to ORNL's Part A RCRA permit, administrative controls were modified to exclude RCRA regulated wastes from being disposed of at SWSA 6, and a RCRA closure plan was prepared. This paper describes the regulatory challenges of integrating RCRA,- the Comprehensive Environmental Response, Compensation, and Liability Act; and the National Environmental Policy Act into a cohesive remediation strategy while managing the project with multiple DOE contractors and integrating the regulatory approval cycle with the DOE budget cycle. The paper does not dwell on the recommended alternative but presents instead a case study of how some difficult challenges, unique to DOE and other federal facilities, were handled

  13. Low-level radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Ozaki, Calvin B.; Kerr, Thomas A.; Williams, R. Eric

    1991-01-01

    Two national systems comprise the low-level radioactive waste management system in the United States of America. The U.S. Nuclear Regulatory Commission regulates low-level radioactive waste produced in the public sector (commercial waste), and the U.S. Department of Energy manages low-level radioactive waste produced by government-sponsored programs. The primary distinction between the two national systems is the source of regulatory control. This paper discusses two issues critical to the success of each system: the site selection process used by the commercial low-level waste disposal system, and the evaluation process used to determine configuration of the DOE waste management system. The two national systems take different approaches to reach the same goals, which are increased social responsibility, protection of public health and safety, and protection of the environment

  14. 76 FR 76158 - Agency Information Collection Activities; Proposed Collection; Comment Request; RCRA Expanded...

    Science.gov (United States)

    2011-12-06

    ... contents of the docket, and to access those documents in the public docket that are available..., including through the use of appropriate automated electronic, mechanical, or other technological collection... as State, local, or Tribal governments. Title: RCRA Expanded Public Participation. ICR numbers: EPA...

  15. Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Corrective Action Unit (CAU) 543: Liquid Disposal Units is listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO) which was agreed to by the state of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). CAU 543 sites are located in Areas 6 and 15 of the Nevada Test Site (NTS), which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven Corrective Action Sites (CASs) (Figure 1): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; and CAS 15-23-03, Contaminated Sump, Piping. All Area 15 CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm, which operated from 1963 to 1981 and was used to support animal experiments involving the uptake of radionuclides. Each of the Area 15 CASs, except CAS 15-23-01, is associated with the disposal of waste effluent from Building 15-06, which was the primary location of the various tests and experiments conducted onsite. Waste effluent disposal from Building 15-06 involved piping, sumps, outfalls, a septic tank with leachfield, underground storage tanks, and an aboveground storage tank (AST). CAS 15-23-01 was associated with decontamination activities of farm equipment potentially contaminated with radiological constituents, pesticides, and herbicides. While the building structures were removed before the investigation took place, all the original tanks, sumps, piping, and concrete building pads remain in place. The Area 6 CAS is located at the Decontamination Facility in Area 6, a facility which operated from 1971 to 2001 and was used to decontaminate vehicles, equipment, clothing, and other materials that had become contaminated during nuclear testing activities. The CAS includes the effluent collection and distribution systems for Buildings

  16. Impacts of hazardous waste regulation on low-level waste management

    International Nuclear Information System (INIS)

    Sharples, F.E.; Eyman, L.D.

    1986-01-01

    The Hazardous and Solid Waste Amendments of 1984 have greatly expanded the universe of what, and who, is regulated under Resource Conservation and Recovery Act (RCRA). Handling requirements for hazardous waste are becoming increasingly more stringent, particularly where land disposal is concerned. DOE needs to begin actively pursuing strategies directed at keeping the management of LLW clearly separated from wastes that are legitimately regulated under RCRA. Such strategies would include instituting systemwide changes in internal management practices, establishing improved location standards for LLW disposal, and negotiating interagency compromise agreements to obtain variances from RCRA requirements where necessary and appropriate

  17. Control of water infiltration into near surface low-level waste disposal units. Final report on field experiments at a humid region site, Beltsville, Maryland

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

    1997-09-01

    This study''s objective was to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work was carried out in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (70 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration were investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management

  18. Calendar year 1996 annual groundwater monitoring report for the Chestnut Ridge Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-02-01

    This annual monitoring report contains groundwater and surface water monitoring data obtained in the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime) during calendar year (CY) 1996. The Chestnut Ridge Regime encompasses a section of Chestnut Ridge west of Scarboro Road and east of an unnamed drainage feature southwest of the US Department of Energy (DOE) Oak Ridge Y-12 Plant (unless otherwise noted, directions are in reference to the Y-12 Plant administrative grid). The Chestnut Ridge Regime contains several sites used for management of hazardous and nonhazardous wastes associated with plant operations. Groundwater and surface water quality monitoring associated with these waste management sites is performed under the auspices of the Y-12 Plant Groundwater Protection Program (GWPP). Included in this annual monitoring report are the groundwater monitoring data obtained in compliance with the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit for the Chestnut Ridge Regime (post-closure permit) issued by the Tennessee Department of Environment and Conservation (TDEC) in June 1996. Besides the signed certification statement and the RCRA facility information summarized below, condition II.C.6 of the post-closure permit requires annual reporting of groundwater monitoring activities, inclusive of the analytical data and results of applicable data evaluations, performed at three RCRA hazardous waste treatment, storage, or disposal (TSD) units: the Chestnut Ridge Sediment Disposal Basin (Sediment Disposal Basin), the Chestnut Ridge Security Pits (Security Pits), and Kerr Hollow Quarry

  19. High level waste transport and disposal cost calculations for the United Kingdom

    International Nuclear Information System (INIS)

    Nattress, P.C.; Ward, R.D.

    1992-01-01

    Commercial nuclear power has been generated in the United Kingdom since 1962, and throughout that time fuel has been reprocessed giving rise to high level waste. This has been managed by storing fission products and related wastes as highly active liquor, and more recently by a program of vitrification and storage of the glass blocks produced. Government policy is that vitrified high level waste should be stored for at least 50 years, which has the technical advantage of allowing the heat output rate of the waste to fall, making disposal easier and cheaper. Thus, there is no immediate requirement to develop a deep geological repository in the UK, but the nuclear companies do have a requirement to make financial provision out of current revenues for high level waste disposal at a future repository. In 1991 the interested organizations undertook a new calculation of costs for such provisions, which is described here. The preliminary work for the calculation included the assumption of host geology characteristics, a compatible repository concept including overpacking, and a range of possible nuclear programs. These have differing numbers of power plants, and differing mixes of high level waste from reprocessing and spent fuel for direct disposal. An algorithm was then developed so that the cost of high level waste disposal could be calculated for any required case within a stated envelope of parameters. An Example Case was then considered in detail leading to the conclusion that a repository to meet the needs of a constant UK nuclear economy up to the middle of the next century would have a cash cost of UK Pounds 1194M (US$2011M). By simple division the cost to a kWh of electricity is UK Pounds 0.00027 (0.45 US mil). (author)

  20. RCRA Assessment Plan for Single-Shell Tank Waste Management Area TX-TY

    Energy Technology Data Exchange (ETDEWEB)

    Horton, Duane G.

    2007-03-26

    WMA TX-TY contains underground, single-shell tanks that were used to store liquid waste that contained chemicals and radionuclides. Most of the liquid has been removed, and the remaining waste is regulated under the RCRA as modi¬fied in 40 CFR Part 265, Subpart F and Washington State’s Hazardous Waste Management Act . WMA TX-TY was placed in assessment monitoring in 1993 because of elevated specific conductance. A groundwater quality assessment plan was written in 1993 describing the monitoring activities to be used in deciding whether WMA TX-TY had affected groundwater. That plan was updated in 2001 for continued RCRA groundwater quality assessment as required by 40 CFR 265.93 (d)(7). This document further updates the assessment plan for WMA TX-TY by including (1) information obtained from ten new wells installed at the WMA after 1999 and (2) information from routine quarterly groundwater monitoring during the last five years. Also, this plan describes activities for continuing the groundwater assessment at WMA TX TY.

  1. Record of Decision for the Ford Building Waste Unit (643-11G) Operable Unit; FINAL

    International Nuclear Information System (INIS)

    Fraley, S.

    2002-01-01

    This decision document presents the selected remedial for the Ford Building Waste Unit (FBWU), in Aiken, South Carolina, which was chosen in accordance with CERCLA, as amended by SARA, and, to the extent practical, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). This decision is based on the Administrative Record File for this specific RCRA/CERCLA site

  2. Significance of water fluxes in a deep arid-region vadose zone to waste disposal strategies

    International Nuclear Information System (INIS)

    Johnejack, K.R.; Blout, D.O.; Sully, M.J.; Emer, D.F.; Hammermeister, D.P.; Dever, L.G.; O'Neill, L.J.; Tyler, S.W.; Chapman, J.

    1994-01-01

    Recently collected subsurface site characterization data have led to the development of a conceptual model of water movement beneath the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) that differs significantly from the conceptual model of water movement inherent in Resource Conservation and Recovery Act (RCRA) regulations. At the Area 5 RWMS, water fluxes in approximately the upper 75 m (250 ft) of the vadose zone point in the upward direction (rather than downward) which effectively isolates this region from the deep (approximately 250 m (820 ft)) uppermost aquifer. Standard RCRA approaches for detection and containment (groundwater monitoring and double liners/leachate collection/leak detection systems) are not able to fulfill their intended function in this rather unique hydrogeologic environment. In order to better fulfill the waste detection and containment intentions of RCRA for mixed waste disposal at the Area 5 RWMS, the Department of Energy, Nevada Operations Office (DOE/NV) is preparing a single petition for both a waiver from groundwater monitoring and an exemption from double liners with leachate collection/leak detection. DOE/NV proposes in this petition that the containment function of liners and leachate collection is better accomplished by the natural hydrogeologic processes operating in the upper vadose zone; and the detection function of groundwater monitoring and the leak detection system in liners is better fulfilled by an alternative vadose zone monitoring system. In addition, an alternative point of compliance is proposed that will aid in early detection, as well as limit the extent of potential contamination before detection. Finally, special cell design features and operation practices will be implemented to limit leachate formation, especially while the cell is open to the atmosphere during waste emplacement

  3. Special Focus Areas for Hazardous Waste Cleanups under the Resource Conservation and Recovery Act (RCRA)

    Science.gov (United States)

    In order to manage the new and changing needs of the RCRA Corrective Action Program, EPA is constantly exploring program enhancements, alternate exposure pathways, and new technologies available to protect human health and environment.

  4. CY2003 RCRA GROUNDWATER MONITORING WELL SUMMARY REPORT

    International Nuclear Information System (INIS)

    MARTINEZ, C.R.

    2003-01-01

    This report describes the calendar year (CY) 2003 field activities associated with the installation of two new groundwater monitoring wells in the A-AX Waste Management Area (WMA) and four groundwater monitoring wells in WMA C in the 200 East Area of the Hanford Nuclear Reservation. All six wells were installed by Fluor Hanford Inc. (FH) for CH2M Hill Hanford Group, Inc. (CHG) in support of Draft Hanford Facility Agreement and Consent Order (Tri-Party Agreement) M-24-00 milestones and ''Resource Conservation and Recovery Act of 1976'' (RCRA) groundwater monitoring requirements. Drilling data for the six wells are summarized in Table 1

  5. Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    International Nuclear Information System (INIS)

    Evans, S.K.

    2002-01-01

    This Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about sampling design, required analyses, and sample collection and handling procedures, is to be used in conjunction with the Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System

  6. Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

    Energy Technology Data Exchange (ETDEWEB)

    Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

    2013-07-29

    Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  7. Regulatory aspects of underground disposal of radioactive waste in the United Kingdom

    International Nuclear Information System (INIS)

    Hookway, B.R.

    1980-01-01

    Government policy towards radioactive waste management in the United Kingdom of Great Britain and Northern Ireland is based on the system of dose limitations laid down by ICRP as interpreted by the National Radiological Protection Board for use in the United Kingdom. The paper describes the legislative and administrative arrangements by which this policy is enforced, including the work of the principal inspectorates, the Nuclear Installations Inspectorate and the Radiochemical Inspectorate together with the latter's equivalents in Scotland and Northern Ireland. It is concluded that the present legislation, including that relating to planning and the setting up of public inquiries, is sufficiently all-embracing to ensure both strict control of the disposal of all the radioactive waste currently arising or which will arise in the future and a high degree of public involvement in the necessary decisions. (author)

  8. Application for Permit to Operate a Class II Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-03-31

    The Nevada Test Site (NTS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NTS and National Security Technologies LLC (NSTec) is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The site will be used for the disposal of refuse, rubbish, garbage, sewage sludge, pathological waste, Asbestos-Containing Material (ACM), industrial solid waste, hydrocarbon-burdened soil, hydrocarbon-burdened demolition and construction waste, and other inert waste (hereafter called permissible waste). Waste containing free liquids or regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA) will not be accepted for disposal at the site. Waste regulated under the Toxic Substance Control Act (TSCA), excluding Polychlorinated Biphenyl [PCB], Bulk Product Waste (see Section 6.2.5) and ACM (see Section 6.2.2.2) will not be accepted for disposal at the site. The disposal site will be used as the sole depository of permissible waste which is: (1) Generated by entities covered under the U.S. Environmental Protection Agency (EPA) Hazardous Waste Generator Identification Number for the NTS; (2) Generated at sites identified in the Federal Facilities Agreement and Consent Order (FFACO); (3) Sensitive records and media, including documents, vugraphs, computer disks, typewriter ribbons, magnetic tapes, etc., generated by NNSA/NSO or its contractors; (4) ACM generated by NNSA/NSO or its contractors according to Section 6.2.2.2, as necessary; (5) Hydrocarbon-burdened soil and solid waste from areas covered under the EPA Hazardous Waste Generator Identification Number for the NTS; (6) Other waste on a case-by-case concurrence by

  9. Closure Report for Corrective Action Unit 425: Area 9 Main Lake Construction Debris Disposal Area, Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    K. B. Campbell

    2003-03-01

    Corrective Action Unit (CAU) 425 is located on the Tonopah Test Range, approximately 386 kilometers (240 miles) northwest of Las Vegas, Nevada. CAU 425 is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) and is comprised of one Corrective Action Site (CAS). CAS 09-08-001-TA09 consisted of a large pile of concrete rubble from the original Hard Target and construction debris associated with the Tornado Rocket Sled Tests. CAU 425 was closed in accordance with the FFACO and the Nevada Division of Environmental Protection-approved Streamlined Approach for Environmental Restoration Plan for CAU 425: Area 9 Main Lake Construction Debris Disposal Area, Tonopah Test Range, Nevada (U.S. Department of Energy, Nevada Operations Office, 2002). CAU 425 was closed by implementing the following corrective actions: The approved corrective action for this unit was clean closure. Closure activities included: (1) Removal of all the debris from the site. (2) Weighing each load of debris leaving the job site. (3) Transporting the debris to the U.S. Air Force Construction Landfill for disposal. (4) Placing the radioactive material in a U.S. Department of Transportation approved container for proper transport and disposal. (5) Transporting the radioactive material to the Nevada Test Site for disposal. (6) Regrading the job site to its approximate original contours/elevation.

  10. Cleanups In My Community (CIMC) - RCRA and Base Realignment and Closure (BRAC) Federal Facilities, National Layer

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data layer provides access to Resource Conservation and Recovery Act (RCRA) Base Realignment and Closure (BRAC) sites as part of the CIMC web service. The...

  11. Remedial investigation/feasibility study work plan for the 100-BC-5 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-07-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The Tri-Party Agreement requires that the cleanup programs at the Hanford Site integrate the requirements of CERCLA, RCRA, and Washington State's dangerous waste (the state's RCRA-equivalent) program. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-BC-5 operable unit. The 100-B/C Area consists of the 100-BC-5 groundwater operable unit and four source operable units. The 100-BC-5 operable unit includes all contamination found in the aquifer soils and water beneath the 100-B/C Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination

  12. Disposal of radioactive wastes. Chapter 11

    International Nuclear Information System (INIS)

    Skitt, J.

    1979-01-01

    An account is given of the history and present position of legislation in the United Kingdom on the disposal of radioactive wastes. The sections are headed: introduction and definitions; history; the Radioactive Substances Act 1960; disposal of solid radioactive wastes through Local Authority services; function of Local Authorities; exemptions; national radioactive waste disposal service; incidents involving radioactivity. (U.K.)

  13. HANFORD TANK FARM RESOURCE CONSERVATION and RECOVERY ACT (RCRA) CORRECTIVE ACTION PROGRAM

    International Nuclear Information System (INIS)

    KRISTOFZSKI, J.G.

    2007-01-01

    As a consequence of producing special nuclear material for the nation's defense, large amounts of extremely hazardous radioactive waste was created at the US Department of Energy's (DOE) Hanford Site in south central Washington State. A little over 50 million gallons of this waste is now stored in 177 large, underground tanks on Hanford's Central Plateau in tank farms regulated under the Atomic Energy Act and the Resource, Conservation, and Recovery Act (RCRA). Over 60 tanks and associated infrastructure have released or are presumed to have released waste in the vadose zone. In 1998, DOE's Office of River Protection established the Hanford Tank Farm RCRA Corrective Action Program (RCAP) to: (1) characterize the distribution and extent of the existing vadose zone contamination; (2) determine how the contamination will move in the future; (3) estimate the impacts of this contamination on groundwater and other media; (4) develop and implement mitigative measures; and (5) develop corrective measures to be implemented as part of the final closure of the tank farm facilities. Since its creation, RCAP has made major advances in each of these areas, which will be discussed in this paper

  14. Food waste disposal units in UK households: The need for policy intervention

    International Nuclear Information System (INIS)

    Iacovidou, Eleni; Ohandja, Dieudonne-Guy; Voulvoulis, Nikolaos

    2012-01-01

    The EU Landfill Directive requires Member States to reduce the amount of biodegradable waste disposed of to landfill. This has been a key driver for the establishment of new waste management options, particularly in the UK, which in the past relied heavily on landfill for the disposal of municipal solid waste (MSW). MSW in the UK is managed by Local Authorities, some of which in a less conventional way have been encouraging the installation and use of household food waste disposal units (FWDs) as an option to divert food waste from landfill. This study aimed to evaluate the additional burden to water industry operations in the UK associated with this option, compared with the benefits and related savings from the subsequent reductions in MSW collection and disposal. A simple economic analysis was undertaken for different FWD uptake scenarios, using the Anglian Region as a case study. Results demonstrated that the significant savings from waste collection arising from a large-scale uptake of FWDs would outweigh the costs associated with the impacts to the water industry. However, in the case of a low uptake, such savings would not be enough to cover the increased costs associated with the wastewater provision. As a result, this study highlights the need for policy intervention in terms of regulating the use of FWDs, either promoting them as an alternative to landfill to increase savings from waste management, or banning them as a threat to wastewater operations to reduce potential costs to the water industry. - Highlights: ► FWDs can be a less conventional way for diverting food waste from landfill. ► We compared water industry costs to savings from MSW collection and treatment. ► A large-scale uptake of FWDs would outweigh the costs to the water industry. ► At a low uptake, MSW collection savings are not enough to cover these costs. ► Findings highlight the need for policy intervention, regulating the use of FWDs.

  15. Savannah River Site RCRA/CERCLA/NEPA integrated investigation case study

    International Nuclear Information System (INIS)

    Clark, D.R.; Thomas, R.; Wilson, M.P.

    1992-01-01

    The Savannah River Site (SRS) is a US Department of Energy facility placed on the Superfund National Priority List in 1989. Numerous past disposal facilities and contaminated areas are undergoing the integrated regulatory remediation process detailed in the draft SRS Federal Facility Agreement. This paper will discuss the integration of these requirements by highlighting the investigation of the D-Area Burning/Rubble Pits, a typical waste unit at SRS

  16. Low-impact sampling under an active solid low-level radioactive waste disposal unit using horizontal drilling technology

    International Nuclear Information System (INIS)

    Puglisi, C.V.; Vold, E.L.

    1995-01-01

    The purpose of this project was to determine the performance of the solid low-level radioactive waste (LLRW) disposal units located on a mesa top at TA-54, Area G, Los Alamos National Laboratory (LANL), Los Alamos, NM, and to provide in-situ (vadose zone) site characterization information to Area G's Performance Assessment. The vadose zone beneath an active disposal unit (DU 37), was accessed by utilizing low-impact, air-rotary horizontal drilling technology. Core samples were pulled, via wire-line core method, in 3 horizontal holes fanning out below DU 37 at approximately 5 foot intervals depending on recovery percentage. Samples were surveyed and prepared in-field following Environmental Restoration (ER) guidelines. Samples were transferred from the field to the CST-9 Radvan for initial radiological screening. Following screening, samples were delivered to CST-3 analytical lab for analyses including moisture content, 23 inorganics, 60 volatile organic compounds (VOC's), 68 semivolatile organic compounds (SVOC's), tritium, lead 210, radium 226 ampersand 228, cesium 137, isotopic plutonium, americium 241, strontium 90, isotopic uranium, and isotopic thorium. Other analyses included matric potential, alpha spectroscopy, gamma spectroscopy, and gross alpha/beta. The overall results of the analysis identified only tritium as having migrated from the DU. Am-241, Eu-152, and Pu-238 were possibly identified above background but the results are not definitive. Of all organics analysed for, only ethyl acetate was tentatively identified slightly above background. All inorganics were found to be well below regulatory limits. Based on the results of the above mentioned analyses, it was determined that Area G's disposal units are performing well and no significant liquid phase migration of contaminants has occurred

  17. A study of concrete for the tumulus disposal units in low-level radioactive waste management

    International Nuclear Information System (INIS)

    Lee, J.H.; Roy, D.M.; Licastro, P.H.; Scheetz, B.E.

    1991-01-01

    The tumulus disposal concept can provide a major means for the disposal of low-level radioactive waste (LLRW) provided the concrete structures of the tumulus disposal units are designed and fabricated for long term durability. As an initial phase of the study, a detailed characterization and testing of the component materials for the tumulus concrete have been evaluated. Key properties of hardened concrete that are important in assuring and predicting the long term durability, which have been evaluated, or are being evaluated, include: water permeability; chloride permeability; sulfate resistance; porosity and pore structure; freeze-thaw resistance; leaching and dissolution; alkali-aggregate reaction; and strength. Those properties were evaluated on samples from field concrete cylinders provided by Martin Marietta Energy Systems (MMES), or samples prepared in the laboratory, or both. The proposed concrete mix design showed an excellent resistance to repeated freeze-thaw cycles, and a very low permeability to chloride. An accelerated test method was used to evaluate alkali-aggregate reactivity in concrete for samples containing representative coarse and fine aggregates proposed for the tumulus concrete, and also conducted for samples cored from the field concrete cylinders

  18. Control of water infiltration into near-surface, low-level waste-disposal units in humid regions

    International Nuclear Information System (INIS)

    O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

    1994-01-01

    This study's objective is to assess means for controlling water infiltration through waste-disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste-disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

  19. 1997 Hanford site report on land disposal restrictions for mixed waste

    Energy Technology Data Exchange (ETDEWEB)

    Black, D.G.

    1997-04-07

    The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones.

  20. 1997 Hanford site report on land disposal restrictions for mixed waste

    International Nuclear Information System (INIS)

    Black, D.G.

    1997-01-01

    The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones

  1. Results and analysis of saltstone cores taken from saltstone disposal unit cell 2A

    Energy Technology Data Exchange (ETDEWEB)

    Reigel, M. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-03-01

    As part of an ongoing Performance Assessment (PA) Maintenance Plan, Savannah River Remediation (SRR) has developed a sampling and analyses strategy to facilitate the comparison of field-emplaced samples (i.e., saltstone placed and cured in a Saltstone Disposal Unit (SDU)) with samples prepared and cured in the laboratory. The primary objectives of the Sampling and Analyses Plan (SAP) are; (1) to demonstrate a correlation between the measured properties of laboratory-prepared, simulant samples (termed Sample Set 3), and the field-emplaced saltstone samples (termed Sample Set 9), and (2) to validate property values assumed for the Saltstone Disposal Facility (SDF) PA modeling. The analysis and property data for Sample Set 9 (i.e. six core samples extracted from SDU Cell 2A (SDU2A)) are documented in this report, and where applicable, the results are compared to the results for Sample Set 3. Relevant properties to demonstrate the aforementioned objectives include bulk density, porosity, saturated hydraulic conductivity (SHC), and radionuclide leaching behavior.

  2. Draft postclosure permit application for Bear Creek Hydrogeologic Regime at the Oak Ridge Y-12 Plant Oil Landform Hazardous Waste Disposal Unit

    International Nuclear Information System (INIS)

    1991-08-01

    The Oil Landfarm Hazardous-Waste Disposal Unit (HWDU) is located approximately one and one-half miles west of the Department of Energy's (DOE) Y-12 Plant in Oak Ridge, Tennessee. The Oil Landfarm HWDU consists of three disposal plots and along with the Bear Creek Burial Grounds and the S-3 Site comprise the Bear Creek Valley Waste Disposal Area (BCVWDA). The facility was used for the biological degradation of waste oil and machine coolants via landfarming, a process involving the application of waste oils and coolants to nutrient-adjusted soil during the dry months of the year (April to October). The Oil Landfarm HWDU has been closed as a hazardous-waste disposal unit and therefore will be subject to post-closure care. The closure plan for the Oil Landfarm HWDU is provided in Appendix A.1. A post-closure plan for the Oil Landfarm HWDU is presented in Appendix A.2. The purpose of this plan is to identify and describe the activities that will be performed during the post-closure care period. This plan will be implemented and will continue throughout the post-closure care period

  3. RCRA corrective action ampersand CERCLA remedial action reference guide

    International Nuclear Information System (INIS)

    1994-07-01

    This reference guide provides a side-by-side comparison of RCRA corrective action and CERCLA Remedial Action, focusing on the statutory and regulatory requirements under each program, criterial and other factors that govern a site's progress, and the ways in which authorities or requirements under each program overlap and/or differ. Topics include the following: Intent of regulation; administration; types of sites and/or facilities; definition of site and/or facility; constituents of concern; exclusions; provisions for short-term remedies; triggers for initial site investigation; short term response actions; site investigations; remedial investigations; remedial alternatives; clean up criterial; final remedy; implementing remedy; on-site waste management; completion of remedial process

  4. A review of state regulations that exceed those of the federal Resource Conservation and Recovery Act (RCRA)

    International Nuclear Information System (INIS)

    Coutant, C.C.; Heckman, C.L.

    1988-04-01

    This report identifies and provides information on state hazardous waste management programs and regulations in states where the US Department of Energy (DOE) has facilities. The objective is to describe for the DOE defense program and its contractors how state requirements are more stringent than the federal regulations under the Resource Conservation and Recovery Act (RCRA). DOE defense programs are located in 13 of the 50 states. Most of these states have regulations that are essentially equivalent to the federal RCRA requirements as they existed prior to the 1984 amendments, but their regulations are, in most instances, more stringment than the federal requirements. Differences are both substantive and procedural, and they are summarized and tabulated herein. All but three of these 13 states have been granted Final Authorization from the US Environmental Protection Agency (EPA) to operate their own hazardous waste management program in accord with the federal RCRA program prior to the 1984 amendments; two of the three others have some stage of Interim Authorization. EPA currently administers all of the provisions of the 1984 amendments, including requirements for corrective action under Sect. 3004(u). Two states, Colorado and Tennessee, have been granted revisions to their Final Authorizations delegating responsibility for the hazardous wastes. Responsible state agencies (with appropriate telephone numbers) are indicated, as are the relevant laws and current regulatory statutes

  5. Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2006-01-01

    Corrective Action Unit (CAU) 543, Liquid Disposal Units, is listed in Appendix III of the Federal Facility Agreement and Consent Order of 1996. CAU 543 consists of seven Corrective Action Sites (CASs) located in Areas 6 and 15 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven CASs: (sm b ullet) CAS 06-07-01, Decon Pad (sm b ullet) CAS 15-01-03, Aboveground Storage Tank (sm b ullet) CAS 15-04-01, Septic Tank (sm b ullet) CAS 15-05-01, Leachfield (sm b ullet) CAS 15-08-01, Liquid Manure Tank (sm b ullet) CAS 15-23-01, Underground Radioactive Material Area (sm b ullet) CAS 15-23-03, Contaminated Sump, Piping From January 24, 2005 through April 14, 2005, CAU 543 site characterization activities were conducted, and are reported in Appendix A of the CAU 543 Corrective Action Decision Document (CADD) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2005). The recommended corrective action as stated in the approved CADD is No Further Action for five of the CAU 543 CASs, and Closure In Place for the remaining two CASs

  6. Disposal leachates treatment

    Energy Technology Data Exchange (ETDEWEB)

    Coulomb, I.; Renaud, P. (SITA, 75 - Paris (France)); Courant, P. (FD Conseil, 78 - Gargenville (France)); Manem, J.; Mandra, V.; Trouve, E. (Lyonnaise des Eaux-Dumez, 78 - Le Pecq (France))

    1993-12-01

    Disposal leachates are complex and variable effluents. The use of a bioreactor with membranes, coupled with a reverse osmosis unit, gives a new solution to the technical burying centers. Two examples are explained here.

  7. Feasibility study for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-02-01

    In July 1990, the US Environmental Protection Agency (EPA) directed the Department of Energy Oak Ridge Operations to comply with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements for the remediation of the United Nuclear Corporation (UNC) Disposal Site located at the Y-12 Plant, Oak Ridge, Tennessee. EPA, Waste Management Branch, had approved a closure plan in December 1989 for the UNC Disposal Site. This feasibility study (FS) is a fully satisfy the National Oil and Hazardous Substances Contingency Plan (NCP) requirements for support of the selection of a remedial response for closure of the UNC Disposal Site. For two years the UNC Disposal Site accepted and disposed of waste from the decommissioning of a UNC uranium recovery facility in Wood River Junction, Rhode Island. Between June 1982 and November 1984, the UNC Disposal Site received 11,000 55-gal drums of sludge fixed in cement, 18,000 drums of contaminated soil, and 288 wooden boxes of contaminated building and process demolition materials. The FS assembles a wide range of remedial technologies so the most appropriate actions could be selected to remediate potential contamination to below MCLs and/or to below the maximum level of acceptable risk. Technologies were evaluated based on technical effectiveness, ease of implementation, and costs. Applicable technologies were then selected for alternative development. 33 refs., 9 figs., 27 tabs

  8. Evaluation of groundwater monitoring results at the Hanford Site 200 Area Treated Effluent Disposal Facility

    International Nuclear Information System (INIS)

    Barnett, D.B.

    1998-09-01

    The Hanford Site 200 Area Treated Effluent Disposal Facility (TEDF) has operated since June 1995. Groundwater monitoring has been conducted quarterly in the three wells surrounding the facility since 1992, with contributing data from nearby B Pond System wells. Cumulative hydrologic and geochemical information from the TEDF well network and other surrounding wells indicate no discernable effects of TEDF operations on the uppermost aquifer in the vicinity of the TEDF. The lateral consistency and impermeable nature of the Ringold Formation lower mud unit, and the contrasts in hydraulic conductivity between this unit and the vadose zone sediments of the Hanford formation suggest that TEDF effluent is spreading laterally with negligible mounding or downward movement into the uppermost aquifer. Hydrographs of TEDF wells show that TEDF operations have had no detectable effects on hydraulic heads in the uppermost aquifer, but show a continuing decay of the hydraulic mound generated by past operations at the B Pond System. Comparison of groundwater geochemistry from TEDF wells and other, nearby RCRA wells suggests that groundwater beneath TEDF is unique; different from both effluent entering TEDF and groundwater in the B Pond area. Tritium concentrations, major ionic proportions, and lower-than-background concentrations of other species suggest that groundwater in the uppermost aquifer beneath the TEDF bears characteristics of water in the upper basalt confined aquifer system. This report recommends retaining the current groundwater well network at the TEDF, but with a reduction of sampling/analysis frequency and some modifications to the list of constituents sought

  9. Costs of the final disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Drasdo, P.

    2001-01-01

    The study on the costs of radioactive waste disposal covers the topic of national concepts for the countries Germany, France, United Kingdom, Sweden, Switzerland and Unites States of America. The introduction into the topic of radioactive waste disposal is concerned with the classification of radioactive wastes, the safety of final repositories and the different concepts of final disposal. The used methods of data acquisition and data processing are described. The study compares the national final disposal concepts in order to identify the reasons for the differences in capital costs and annuity costs in the respective countries. The final chapter is concerned with the optimum timing for the start-up of operation of final repositories

  10. Data quality objectives for two risk assessments at Hanford

    International Nuclear Information System (INIS)

    Lane, N.K.; Clark, S.W.; Tranbarger, R.K.; Roeck, F.V.

    1996-01-01

    The opportunity for innovative thinking prevails at the US Department of Energy's Hanford Site in southeastern Washington state. Two projects, in particular, challenged risk assessment staff. They are: (1) a combined Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)/Resource Conservation and Recovery Act (RCRA) risk assessment, and (2) developing a risk assessment for a mixed-waste disposal facility. The combined CERCLA/RCRA risk assessment involved establishing data quality objectives (DQO) either to meet clean closure for a RCRA treatment, storage and/or disposal facility (TSD) or (if the former was not possible) to conform to goals established for industrial land use for Hanford Past-Practice Strategy (HPPS) sites. Radionuclide analysis was reduced by 60 percent through the DQO process

  11. Disposal of fly ash

    International Nuclear Information System (INIS)

    Singh, B.; Foley, C.

    1991-01-01

    Theoretical arguments and pilot plant results have shown that the transport of fly-furnace ash from the power station to the disposal area as a high concentration slurry is technically viable and economically attractive. Further, lack of free water, when transported as a high concentration slurry, offers significant advantages in environmental management and rehabilitation of the disposal site. This paper gives a basis for the above observations and discusses the plans to exploit the above advantages at the Stanwell Power Station. (4 x 350 MWe). This will be operated by the Queensland Electricity Commission. The first unit is to come into operation in 1992 and other units are to follow progressively on a yearly basis

  12. Quarterly report of RCRA groundwater monitoring data for period April 1, 1993 through June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Jungers, D.K.

    1993-10-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs. This report contains data from Hanford Site groundwater monitoring projects. Westinghouse Hanford Company (WHC) manages the RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Project management, specifying data needs, performing quality control (QC) oversight, managing data, and preparing project sampling schedules are all parts of this responsibility. Pacific Northwest Laboratory (PNL) administers the contract for analytical services and provides groundwater sampling services to WHC for the RCRA groundwater monitoring program. This quarterly report contains data received between May 24 and August 20, 1993, which are the cutoff dates for this reporting period. This report may contain not only data from samples collected during the April through June quarter but also data from earlier sampling events that were not previously reported.

  13. Proposed plan for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-03-01

    The US Department of Energy (DOE) in compliance with Section 117(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, is releasing the proposed plan for remedial action at the United Nuclear Corporation (UNC) Disposal Site located at the DOE Oak Ridge Operations (ORO) Y-12 Plant, Oak Ridge, Tennessee. The purpose of this document is to present and solicit for comment to the public and all interested parties the ''preferred plan'' to remediate the UNC Disposal Site. However, comments on all alternatives are invited

  14. Development of a high integrity container for storage, transportation, and disposal of radioactive wastes from Three Mile Island unit II

    International Nuclear Information System (INIS)

    Holzworth, R.E.; Chapman, R.L.; Burton, H.M.; Bixby, W.W.

    1981-01-01

    The EPICOR II ion exchange system used to decontaminate approximately 1900 m 3 of contaminated water in the Auxiliary and Fuel Handling Building (AFHB) generated 50 highly loaded and 22 lesser loaded organic resin liners. The 22 lesser loaded resins were shipped to a commercial disposal site, but the highly loaded liners have been stored on the island since their generation. One highly loaded liner, or prefilter, was shipped to Battelle Columbus Laboratories (BCL) in May, 1981 as part of the United States Department of Energy (DOE) Three Mile Island Information and Examination Program. The prefilter is being characterized to determine the behavior of the waste form with respect to time and the internal environment and to provide an information base for use in management and regulatory decisions relative to the storage, processing, and disposal of these wastes. Due to the unique characteristics of these wastes, the US DOE is sponsoring programs, such as the BCL Sorbent Experiments Program, to evaluate their characteristics and to provide a High Integrity Container (HIC) Development Program which would improve waste suitability for disposal at a land burial facility. This paper addresses regulatory considerations, establishment of design criteria, proposed design concepts, system demonstration, and status of the HIC Development Program for storage, transportation, and disposal of high specific activity, low level radioactive wastes from Three Mile Island Unit II as typified by EPICOR II ion exchange media and liners

  15. Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada: Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2004-05-03

    The general purpose of this Corrective Action Investigation Plan is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technically viable corrective action alternatives (CAAs) for Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. Located in Areas 6 and 15 on the NTS, CAU 543 is comprised of a total of seven corrective action sites (CASs), one in Area 6 and six in Area 15. The CAS in Area 6 consists of a Decontamination Facility and its components which are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency Farm and are related to waste disposal activities at the farm. Sources of possible contamination at Area 6 include potentially contaminated process waste effluent discharged through a process waste system, a sanitary waste stream generated within buildings of the Decon Facility, and radiologically contaminated materials stored within a portion of the facility yard. At Area 15, sources of potential contamination are associated with the dairy operations and the animal tests and experiments involving radionuclide uptake. Identified contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, petroleum hydrocarbons, pesticides, herbicides, polychlorinated biphenyls, metals, and radionuclides. Three corrective action closure alternatives - No Further Action, Close in Place, or Clean Closure - will be recommended for CAU 543 based on an evaluation of all the data quality objective-related data. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document.

  16. Plans and Progress on Hanford MLLW Treatment and Disposal

    International Nuclear Information System (INIS)

    McDonald, K. M.; Blackford, L. T.; Nester, D. E.; Connolly, R. R.; McKenney, D. E.; Moy, S. K.

    2003-01-01

    Mixed low-level waste (MLLW) contains both low-level radioactive materials and low-level hazardous chemicals. The hazardous component of mixed waste has characteristics identified by any or all of the following statutes: the Resource Conservation and Recovery Act of 1976 (RCRA), as amended; the Toxic Substances Control Act of 1976; and Washington State dangerous waste regulations. The Fluor Hanford Waste Management Project (WMP) is responsible for storing, treating, and disposing of solid MLLW, which includes organic and inorganic solids, organics and inorganic lab packs, debris, lead, mercury, long-length equipment, spent melters, and remote-handled (RH) and oversized MLLW. Hanford has 7,000 cubic meters, or about 25%, of the MLLW in storage at U.S. Department of Energy (DOE) sites. Hanford plans to receive 57,000 cubic meters from on-site generators, or about 50% of DOE's newly generated MLLW. In addition, the Hanford Environment Restoration Program and off-site generators having approved Federal Facility Consent Agreement site treatment plans will most likely send 200 cubic meters of waste to be treated and returned to the generators. Volumes of off-site waste receipts will be affected when the MLLW Record of Decision is issued as part of the process for the Hanford Site Solid Waste Environmental Impact Statement (EIS). The WMP objective relative to MLLW is to treat and dispose of ∼8000 cubic meters of existing inventory and newly-generated waste by September 30, 2006

  17. Regulatory issues for Waste Isolation Pilot Plant long-term compliance with U.S. Environmental Protection Agency 40 CFR 191B and 268

    International Nuclear Information System (INIS)

    Anderson, D.R.; Marietta, M.G.; Higgins, P.J. Jr.

    1993-10-01

    Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with long-term regulations of the United States Environmental Protection Agency (EPA), specifically the Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191), and the Land Disposal Restrictions (40 CFR 268) of the Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act (RCRA). Sandia National Laboratories (SNL) is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This paper provides background information on the regulations, describes the SNL WIPP PA Departments approach to developing a defensible technical basis for consistent compliance evaluations, and summarizes the major observations and conclusions drawn from the 1991 and 1992 PAs

  18. Transuranic Storage Area (TSA)-3 container storage unit RCRA closure plan

    International Nuclear Information System (INIS)

    Barry, G.A.; Lodman, D.L.; Spry, M.J.; Poor, K.J.

    1992-11-01

    This document describes the proposed plan for closure of the Transuranic Storage Area (TSA)-3 container storage unit at the Idaho National Engineering Laboratory in accordance with the Resource Conservation and Recovery Act closure requirements. The location, size, capacity, history, and current status of the unit are described. The unit will be closed by decontaminating structures and equipment that may have contacted waste. Sufficient sampling and documentation of all activities will be performed to demonstrate clean closure. A tentative schedule is provided in the form of a milestone chart

  19. Corrective Action Investigation Plan for Corrective Action Unit 410: Waste Disposal Trenches, Tonopah Test Range, Nevada, Revision No.:0

    International Nuclear Information System (INIS)

    2002-01-01

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 410 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 410 is located on the Tonopah Test Range (TTR), which is included in the Nevada Test and Training Range (formerly the Nellis Air Force Range) approximately 140 miles northwest of Las Vegas, Nevada. This CAU is comprised of five Corrective Action Sites (CASs): TA-19-002-TAB2, Debris Mound; TA-21-003-TANL, Disposal Trench; TA-21-002-TAAL, Disposal Trench; 09-21-001-TA09, Disposal Trenches; 03-19-001, Waste Disposal Site. This CAU is being investigated because contaminants may be present in concentrations that could potentially pose a threat to human health and/or the environment, and waste may have been disposed of with out appropriate controls. Four out of five of these CASs are the result of weapons testing and disposal activities at the TTR, and they are grouped together for site closure based on the similarity of the sites (waste disposal sites and trenches). The fifth CAS, CAS 03-19-001, is a hydrocarbon spill related to activities in the area. This site is grouped with this CAU because of the location (TTR). Based on historical documentation and process know-ledge, vertical and lateral migration routes are possible for all CASs. Migration of contaminants may have occurred through transport by infiltration of precipitation through surface soil which serves as a driving force for downward migration of contaminants. Land-use scenarios limit future use of these CASs to industrial activities. The suspected contaminants of potential concern which have been identified are volatile organic compounds; semivolatile organic compounds; high explosives; radiological constituents including depleted uranium

  20. 200 West Groundwater Aggregate Area management study report

    International Nuclear Information System (INIS)

    1993-01-01

    This report presents the results of an aggregate area management study (AAMS) for the 200 West Groundwater Aggregate Area in the 200 Areas of the US Department of Energy (DOE) Hanford Site in Washington State. This scoping level study provides the basis for initiating Remedial Investigation/Feasibility Study (RI/FS) activities under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) or Resource Conservation and Recovery Act (RCRA), Facility Investigations (Rlq) and Corrective Measures Studies (CMS) under RCRA. This report also integrates select RCRA treatment, storage or disposal (TSD) closure activities with CERCLA and RCRA past practice investigations

  1. 200 North Aggregate Area source AAMS report

    International Nuclear Information System (INIS)

    1993-06-01

    This report presents the results of an aggregate area management study (AAMS) for the 200 North Aggregate Area in the 200 Areas of the US Department of Energy (DOE) Hanford Site in Washington State. This scoping level study provides the basis for initiating Remedial Investigation/Feasibility Study (RI/FS) activities under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) or Resource Conservation and Recovery Act (RCRA) Facility Investigations (RFI) and Corrective Measures Studies (CMS) under RCRA. This report also integrates select RCRA treatment, storage, or disposal (TSD) closure activities with CERCLA and RCRA past practice investigations

  2. PUREX source Aggregate Area management study report

    International Nuclear Information System (INIS)

    1993-03-01

    This report presents the results of an aggregate area management study (AAMS) for the PUREX Plant Aggregate Area in the 200 Areas of the US Department of Energy (DOE)Hanford Site in Washington State. This scoping level study provides the basis for initiating Remedial Investigation/Feasibility Study (RI/FS) activities under the comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) or Resource Conservation and Recovery Act (RCRA) Facility Investigations (RFI) and Corrective Measures Studies (CMS) under RCRA. This report also integrates select RCRA treatment, storage, or disposal (TSD) closure activities with CERCLA and RCRA past-practice investigations

  3. 200 North Aggregate Area source AAMS report

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This report presents the results of an aggregate area management study (AAMS) for the 200 North Aggregate Area in the 200 Areas of the US Department of Energy (DOE) Hanford Site in Washington State. This scoping level study provides the basis for initiating Remedial Investigation/Feasibility Study (RI/FS) activities under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) or Resource Conservation and Recovery Act (RCRA) Facility Investigations (RFI) and Corrective Measures Studies (CMS) under RCRA. This report also integrates select RCRA treatment, storage, or disposal (TSD) closure activities with CERCLA and RCRA past practice investigations.

  4. ORGDP RCRA/PCB incinerator facility

    International Nuclear Information System (INIS)

    Rogers, T.

    1987-01-01

    A dual purpose solid/liquid incinerator is currently being constructed at the Oak Ridge Gaseous Diffusion Plant [ORGDP (K-25)] to destroy uranium contaminated, hazardous organic wastes in compliance with the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). These wastes are generated by the gaseous diffusion plants in Oak Ridge, TN; Paducah, KY; and Portsmouth, OH. In addition, waste will also be received from the Y-12 Plant, Oak Ridge National Laboratory (ORNL), and the Feed Materials Production Center (FMPC). Destruction of PCBs and hazardous liquid organic wastes will be accomplished in a rotary kiln incinerator with an afterburner. This system was selected faster a study of various alternatives. Incineration was chosen because it is dependable, permanent, detoxifies organics, and reduces volume. The rotary kiln incinerator was selected because it can thermally destroy organic constituents of liquids, solids, and sludges to produce an organically inert ash. In addition to the incineration off-gas treatment system, the facility includes a tank farm, drum storage buildings, a solids preparation area, a control room, and a data management system. The incineration system, off-gas treatment system, and related instrumentation and controls are being provided by International Waste Energy Systems (IWES) which is responsible for design, construction, startup, and performances testing

  5. Plumbing and Sewage Disposal.

    Science.gov (United States)

    Sutliff, Ronald D.; And Others

    This self-study course is designed to familiarize Marine enlisted personnel with the principles of plumbing and sewage disposal used by Marine Hygiene Equipment Operators to perform their mission. The course contains three study units. Each study unit begins with a general objective, which is a statement of what the student should learn from the…

  6. Geologic and hydrologic considerations for various concepts of high-level radioactive waste disposal in conterminous United States

    International Nuclear Information System (INIS)

    Ekren, E.B.; Dinwiddie, G.A.; Mytton, J.W.; Thordarson, W.; Weir, J.E. Jr.; Hinrichs, E.N.; Schroder, L.J.

    1974-01-01

    The purpose of this investigation is to evaluate and identify which geohydrologic environments in conterminous United States are best suited for various concepts or methods of underground disposal of high-level radioactive wastes and to establish geologic and hydrologic criteria that are pertinent to high-level waste disposal. The unproven methods of disposal include (1) a very deep drill hole (30,000 to 50,000 ft or 9,140 to 15,240 m), (2) a matrix of (an array of multiple) drill holes (1,000 to 20,000 ft or 305 to 6,100 m), (3) a mined chamber (1,000 to 10,000 ft or 305 to 3,050 m), (4) a cavity with separate manmade structures (1,000 to 10,000 ft or 305 to 3,050 m), and (5) an exploded cavity (2,000 to 20,000 ft or 610 to 6,100 m). Areas considered to be unsuitable for waste disposal are those where seismic risk is high, where possible sea-level rise would inundate potential sites, where high topographic relief coincides with high frequency of faults, where there are unfavorable ground-water conditions, and where no suitable rocks are known to be present to depths of 20,000 feet (6,100 m) or more, and where these strata either contain large volumes of ground water or have high oil and gas potential

  7. Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2007-07-01

    Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report.

  8. Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report

  9. Coal combustion waste management at landfills and surface impoundments 1994-2004.

    Energy Technology Data Exchange (ETDEWEB)

    Elcock, D.; Ranek, N. L.; Environmental Science Division

    2006-09-08

    On May 22, 2000, as required by Congress in its 1980 Amendments to the Resource Conservation and Recovery Act (RCRA), the U.S. Environmental Protection Agency (EPA) issued a Regulatory Determination on Wastes from the Combustion of Fossil Fuels. On the basis of information contained in its 1999 Report to Congress: Wastes from the Combustion of Fossil Fuels, the EPA concluded that coal combustion wastes (CCWs), also known as coal combustion by-products (CCBs), did not warrant regulation under Subtitle C of RCRA, and it retained the existing hazardous waste exemption for these materials under RCRA Section 3001(b)(3)(C). However, the EPA also determined that national regulations under Subtitle D of RCRA were warranted for CCWs that are disposed of in landfills or surface impoundments. The EPA made this determination in part on the basis of its findings that 'present disposal practices are such that, in 1995, these wastes were being managed in 40 percent to 70 percent of landfills and surface impoundments without reasonable controls in place, particularly in the area of groundwater monitoring; and while there have been substantive improvements in state regulatory programs, we have also identified gaps in State oversight' (EPA 2000). The 1999 Report to Congress (RTC), however, may not have reflected the changes in CCW disposal practices that occurred since the cutoff date (1995) of its database and subsequent developments. The U.S. Department of Energy (DOE) and the EPA discussed this issue and decided to conduct a joint DOE/EPA study to collect new information on the recent CCW management practices by the power industry. It was agreed that such information would provide a perspective on the chronological adoption of control measures in CCW units based on State regulations. A team of experts from the EPA, industry, and DOE (with support from Argonne National Laboratory) was established to develop a mutually acceptable approach for collecting and analyzing data

  10. Corrective Action Investigation Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Grant Evenson

    2006-01-01

    Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139

  11. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the period October 2000-July 2001

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 2000--July 2001 monitoring period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in July 2001. There has been no subsidence at any of the markers since monitoring began eight years ago. Precipitation for the period October 2000 through July 2001 was 9.42 centimeters (cm) (3.71 inches [in]) (U.S. National Weather Service, 2001). The prior year annual rainfall (January 2000 through December 2000) was 10.44 cm (4.1 1 in.). The recorded average annual rainfall for this site from 1972 to January 2000 is 14.91 cm (5.87 in.). The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that may be indicative of moisture movement at a point located directly beneath each trench. All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the trenches

  12. Characterization and remediation of a mixed waste-contaminated site at Kirtland Air Force Base, New Mexico

    International Nuclear Information System (INIS)

    Johnston, J.W.; Thacker, M.S.; DeWitt, C.B.

    1997-01-01

    In the area of environmental restoration, one of the most challenging problems is the task of remediating mixed waste-contaminated sites. This paper discusses a successful Interim Corrective Measure (ICM) performed at a mixed waste-contaminated site on Kirtland Air Force Base (AFB) in Albuquerque, New Mexico. The site, known as RW-68, Cratering Area and Radium Dump/Slag Piles, was used during the late 1940s and early 1950s for the destruction and incineration of captured World War II aircraft. It contained 19 slag piles totaling approximately 150 tons of slag, ash, refractory brick, and metal debris. The piles were contaminated with radium-226 and RCRA-characteristic levels of heavy metals. Therefore, the piles were considered mixed waste. To eliminate the threat to human health and the environment, an ICM of removal, segregation, stabilization, and disposal was conducted from October through December 1996. Approximately 120 cubic yards (cu yds) of mixed waste, 188 cu yds of low-level radioactive-contaminated soil, 1 cu yd of low-level radioactive-contaminated debris, 5 cu yds of RCRA-characteristic hazardous waste, and 45 tons of nonhazardous debris were stabilized and disposed of during the ICM. To render the RCRA metals and radionuclides insoluble, stabilization was performed on the mixed and RCRA-characteristic waste streams. All stabilized material was subjected to TCLP analysis to verify it no longer exhibited RCRA-characteristic properties. Radiological and geophysical surveys were conducted concurrently with site remediation activities. These surveys provided real-time documentation of site conditions during each phase of the ICM and confirmed successful cleanup of the site. The three radioactive waste streams, stabilized mixed waste, low-level radioactive-contaminated soil, and low-level radioactive-contaminated debris, were disposed of at the Envirocare low-level radioactive disposal facility

  13. Concrete characterization for the 300 Area Solvent Evaporator Closure Site

    International Nuclear Information System (INIS)

    Prignano, A.L.

    1995-01-01

    This report summarizes the sampling activities undertaken and the analytical results obtained in a concrete sampling and analyses study performed for the 300 Area Solvent Evaporator (300 ASE) closure site. The 300 ASE is identified as a Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) unit that will be closed in accordance with the applicable laws and regulations. No constituents of concern were found in concentrations indicating contamination of the concrete by 300 ASE operations

  14. Foreign experience in alpha-contaminated waste disposal

    International Nuclear Information System (INIS)

    Lakey, P.

    1982-01-01

    The European presentations provided some useful comparisons with the situation int he United States regarding the transuranic (TRU) waste limit. First, in Europe, there appears to be a more moderate view on intrusion compared to the preoccupation in United States with this issue. Second, and superficially, in the United Kingdom and France, the working limit for near-surface disposal is greater than 10 nCi/g and more like 100 nCi/g. Looking beneath the superficial, however, the important difference is that their limits are working limits; they are not cast in bronze like the 10 nCi/g US value is not perceived to be. Europeans seem to have a more flexible and practical view of the issue and have reserved for its solution a rather large middle ground that appears to be lacking in the US position. For example, the United Kingdom is moving actively toward a version of greater confinement disposal or engineered disposal at a greater depth (with plutonium numbers like 10 4 nCi/g projected) and then moving on to the modified mine with limits like 10 5 nCi/g. From the French presentations, limits like 10 3 nCi/g were discussed. As we debate the TRU limit issue, what we seem to hear is an argument between the advocates of a generic limit of perhaps 100 nCi/g and the arguments for site-specific limits. This debate clouds perhaps the more basic issue of the need for a middle ground disposal approach between the extremes of a room trash limit and geologic disposal

  15. Final disposal options for mercury/uranium mixed wastes from the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    Gorin, A.H.; Leckey, J.H.; Nulf, L.E.

    1994-01-01

    Laboratory testing was completed on chemical stabilization and physical encapsulation methods that are applicable (to comply with federal and state regulations) to the final disposal of both hazardous and mixed hazardous elemental mercury waste that is in either of the following categories: (1) waste generated during decontamination and decommissioning (D and D) activities on mercury-contaminated buildings, such as Building 9201-4 at the Oak Ridge Y-12 Plant, or (2) waste stored and regulated under either the Federal Facilities Compliance Agreement or the Federal Facilities Compliance Act. Methods were used that produced copper-mercury, zinc-mercury, and sulfur-mercury materials at room temperature by dry mixing techniques. Toxicity Characteristic Leaching Procedure (TCLP) results for mercury on batches of both the copper-mercury and the sulfur-mercury amalgams consistently produced leachates with less than the 0.2-mg/L Resource Conservation and Recovery Act (RCRA) regulatory limit for mercury. The results clearly showed that the reaction of mercury with sulfur at room temperature produces black mercuric sulfide, a material that is well suited for land disposal. The results also showed that the copper-mercury and zinc-mercury amalgams had major adverse properties that make them undesirable for land disposal. In particular, they reacted readily in air to form oxides and liberate elemental mercury. Another major finding of this study is that sulfur polymer cement is potentially useful as a physical encapsulating agent for mercuric sulfide. This material provides a barrier in addition to the chemical stabilization that further prevents mercury, in the form of mercuric sulfide, from migrating into the environment

  16. Unreviewed Disposal Question Evaluation: Waste Disposal in Engineered Trenches 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-12-12

    Revision 0 of this UDQE addressed the proposal to place Engineered Trench #3 (ET#3) in the footprint designated for Slit Trench #12 (ST#12) and operate using ST#12 disposal limits. Similarly, Revision 1 evaluates whether ET#4 can be located in and operated to Slit Trench #13 (ST#13) disposal limits. Both evaluations conclude that the proposed operations result in an acceptably small risk of exceeding a SOF of 1.0 and approve these actions from a performance assessment (PA) perspective. Because ET#3 will be placed in the location previously designated for ST#12, Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore, new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  17. Issues in radioactive mixed waste compliance with RCRA [Resource Conservation and Recovery Act]: Some examples from ongoing operations at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Eaton, D.L.; Smith, T.H.; Clements, T.L. Jr.; Hodge, V.

    1990-01-01

    Radioactive mixed waste is subject to regulation under both the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). The regulation of such waste is the responsibility of the Environmental Protection Agency (EPA) and either the Nuclear Regulatory Commission (NRC) or the Department of Energy (DOE), depending on whether the waste is commercially generated or defense-related. The recent application of the RCRA regulations to ongoing operations at the DOE's Idaho National Engineering Laboratory (INEL) are described in greater detail. 8 refs., 2 figs

  18. Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order; TOPICAL

    International Nuclear Information System (INIS)

    Evans, S.K.

    2002-01-01

    This Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA- 731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about the project description, project organization, and quality assurance and quality control procedures, is to be used in conjunction with the Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System. This Quality Assurance Project Plan specifies the procedures for obtaining the data of known quality required by the closure activities for the TRA-731 caustic and acid storage tank system

  19. Control and tracking arrangements for solid low-level waste disposals to the UK Drigg disposal site

    International Nuclear Information System (INIS)

    Elgie, K.G.; Grimwood, P.D.

    1993-01-01

    The Drigg disposal site has been the principal disposal site for solid low-level radioactive wastes (LLW) in the United Kingdom since 1959. It is situated on the Cumbrian coast, some six kilometers to the south of the Sellafield nuclear reprocessing site. The Drigg site receives LLW from a wide range of sources including nuclear power generation, nuclear fuel cycle activities, defense activities, isotope manufacture, universities, hospitals, general industry and clean-up of contaminated sites. This LLW has been disposed of in a series of trenches cut into the underlying clay layer of the site, and, since 1988, also into concrete lined vault. The total volume of LLW disposed of at Drigg is at present in the order of 800,000m 3 , with disposals currently approximately 25,000m 3 per year. British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site. To meet operational and regulatory requirements, BNFL needs to ensure the acceptability of the disposed waste and be able to track it from its arising point to its specific disposal location. This paper describes the system that has been developed to meet these requirements

  20. RCRA and Operational Monitoring (ROM). Multi-Year Program Plan and Fiscal Year 95 Work Plan WBS 1.5.3

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-17

    This document contains information concerning the RCRA and Operational Monitoring Program at Hanford Reservation. Information presented includes: Schedules for ground water monitoring activities, program cost baseline, program technical baseline, and a program milestone list.

  1. Modularized system for disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    Mallory, C.W.; DiSibio, R.

    1985-01-01

    A modularized system for the disposal of low-level radioactive waste is presented that attempts to overcome the past problems with shallow land burial and gain public acceptance. All waste received at the disposal site is packaged into reinforced concrete modules which are filled with grout, covered and sealed. The hexagonal shape modules are placed in a closely packed array in a disposal unit. The structural stability provided by the modules allow a protective cover constructed of natural materials to be installed, and the disposal units are decommissioned as they are filled. The modules are designed to be recoverable in the event remedial action is necessary. The cost of disposal with a facility of this type is comparable to current prices of shallow land burial facilities. The system is intended to address the needs of generators, regulators, communities, elected officials, licensees and future generations

  2. Quantification of Food Waste Disposal in the United States: A Meta-Analysis.

    Science.gov (United States)

    Thyberg, Krista L; Tonjes, David J; Gurevitch, Jessica

    2015-12-15

    Food waste has major consequences for social, nutritional, economic, and environmental issues, and yet the amount of food waste disposed in the U.S. has not been accurately quantified. We introduce the transparent and repeatable methods of meta-analysis and systematic reviewing to determine how much food is discarded in the U.S., and to determine if specific factors drive increased disposal. The aggregate proportion of food waste in U.S. municipal solid waste from 1995 to 2013 was found to be 0.147 (95% CI 0.137-0.157) of total disposed waste, which is lower than that estimated by U.S. Environmental Protection Agency for the same period (0.176). The proportion of food waste increased significantly with time, with the western U.S. region having consistently and significantly higher proportions of food waste than other regions. There were no significant differences in food waste between rural and urban samples, or between commercial/institutional and residential samples. The aggregate disposal rate for food waste was 0.615 pounds (0.279 kg) (95% CI 0.565-0.664) of food waste disposed per person per day, which equates to over 35.5 million tons (32.2 million tonnes) of food waste disposed annually in the U.S.

  3. Transuranic Storage Area (TSA)-2 container storage unit RCRA closure plan

    International Nuclear Information System (INIS)

    Lodman, D.W.; Spry, M.J.; Nolte, E.P.; Barry, G.A.

    1992-11-01

    This document describes the proposed plans for closure of the Transuranic Storage Area (TSA)-2 container storage unit at the Idaho National Engineering Laboratory in accordance with the Resource Conservation and Recovery Act closure requirements. The location, size, capacity, history, and current status of the unit are described. Future plans for the unit include incorporating the earthen-covered portion of the TSA-2 pad into a TSA retrieval enclosure along with the TSA-1 and TSAR pads, and closure of the portion of the TSA-2 pad under the Air Support Weather Shield (ASWS-2). This plan addresses closure of the ASWS-2 by decontaminating structures and equipment that may have contacted the waste. Sufficient sampling and documentation of all closure activities will be performed to demonstrate clean closure. A tentative schedule is provided in the form of a milestone chart

  4. Opportunities for Cost Effective Disposal of Radioactively Contaminated Solid Waste on the Oak Ridge Reservation, Oak Ridge, TN - 13045

    International Nuclear Information System (INIS)

    DeMonia, Brian; Dunning, Don; Hampshire John

    2013-01-01

    Department of Energy (DOE) requirements for the release of non-real property, including solid waste, containing low levels of residual radioactive materials are specified in DOE Order 458.1 and associated guidance. Authorized limits have been approved under the requirements of DOE Order 5400.5, predecessor to DOE Order 458.1, to permit disposal of solid waste containing low levels of residual radioactive materials at solid waste landfills located within the DOE Oak Ridge Reservation (ORR). Specifically, volumetric concentration limits for disposal of solid waste at Industrial Landfill V and at Construction/Demolition Landfill VII were established in 2003 and 2007, respectively, based on the requirements in effect at that time, which included: an evaluation to ensure that radiation doses to the public would not exceed 25 mrem/year and would be as low as reasonably achievable (ALARA), with a goal of a few mrem/year or less (in fact, these authorized limits actually were derived to meet a dose constraint of 1 mrem/year); an evaluation of compliance with groundwater protection requirements; and reasonable assurance that the proposed disposal is not likely to result in a future requirement for remediation of the landfill. Prior to approval as DOE authorized limits, these volumetric concentration limits were coordinated with the Tennessee Department of Environment and Conservation (TDEC) and documented in a Memorandum of Understanding (MOU) between the TDEC Division of Radiological Health and the TDEC Division of Solid Waste Management. These limits apply to the disposal of soil and debris waste generated from construction, maintenance, environmental restoration, and decontamination and decommissioning (D and D) activities on the DOE Oak Ridge Reservation. The approved site-specific authorized limits were incorporated in the URS/CH2M Oak Ridge LLC (UCOR) waste profile system that authorizes disposal of special wastes at either of the RCRA Subtitle D landfills. However, a

  5. Opportunities for Cost Effective Disposal of Radioactively Contaminated Solid Waste on the Oak Ridge Reservation, Oak Ridge, TN - 13045

    Energy Technology Data Exchange (ETDEWEB)

    DeMonia, Brian [Department of Energy, P.O. Box 2001, Oak Ridge, Tennessee 37831 (United States); Dunning, Don [Argonne National Laboratory, P.O. Box 6974, Oak Ridge, Tennessee 37831-6974 (United States); Hampshire John [UCOR, PO Box 4699, MS-7593, Oak Ridge, Tennessee 37831 (United States)

    2013-07-01

    Department of Energy (DOE) requirements for the release of non-real property, including solid waste, containing low levels of residual radioactive materials are specified in DOE Order 458.1 and associated guidance. Authorized limits have been approved under the requirements of DOE Order 5400.5, predecessor to DOE Order 458.1, to permit disposal of solid waste containing low levels of residual radioactive materials at solid waste landfills located within the DOE Oak Ridge Reservation (ORR). Specifically, volumetric concentration limits for disposal of solid waste at Industrial Landfill V and at Construction/Demolition Landfill VII were established in 2003 and 2007, respectively, based on the requirements in effect at that time, which included: an evaluation to ensure that radiation doses to the public would not exceed 25 mrem/year and would be as low as reasonably achievable (ALARA), with a goal of a few mrem/year or less (in fact, these authorized limits actually were derived to meet a dose constraint of 1 mrem/year); an evaluation of compliance with groundwater protection requirements; and reasonable assurance that the proposed disposal is not likely to result in a future requirement for remediation of the landfill. Prior to approval as DOE authorized limits, these volumetric concentration limits were coordinated with the Tennessee Department of Environment and Conservation (TDEC) and documented in a Memorandum of Understanding (MOU) between the TDEC Division of Radiological Health and the TDEC Division of Solid Waste Management. These limits apply to the disposal of soil and debris waste generated from construction, maintenance, environmental restoration, and decontamination and decommissioning (D and D) activities on the DOE Oak Ridge Reservation. The approved site-specific authorized limits were incorporated in the URS/CH2M Oak Ridge LLC (UCOR) waste profile system that authorizes disposal of special wastes at either of the RCRA Subtitle D landfills. However, a

  6. High-level waste processing and disposal

    International Nuclear Information System (INIS)

    Crandall, J.L.; Krause, H.; Sombret, C.; Uematsu, K.

    1984-01-01

    The national high-level waste disposal plans for France, the Federal Republic of Germany, Japan, and the United States are covered. Three conclusions are reached. The first conclusion is that an excellent technology already exists for high-level waste disposal. With appropriate packaging, spent fuel seems to be an acceptable waste form. Borosilicate glass reprocessing waste forms are well understood, in production in France, and scheduled for production in the next few years in a number of other countries. For final disposal, a number of candidate geological repository sites have been identified and several demonstration sites opened. The second conclusion is that adequate financing and a legal basis for waste disposal are in place in most countries. Costs of high-level waste disposal will probably add about 5 to 10% to the costs of nuclear electric power. The third conclusion is less optimistic. Political problems remain formidable in highly conservative regulations, in qualifying a final disposal site, and in securing acceptable transport routes

  7. Disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-11-15

    A discussion on the disposal of radioactive wastes was held in Vienna on 20 September 1960. The three scientists who participated in the discussion were Mr. Harry Brynielsson (Sweden), Head of the Swedish Atomic Energy Company; Mr. H. J. Dunster (United Kingdom), Health Physics Adviser to the United Kingdom Atomic Energy Authority; and Mr. Leslie Silverman (United States), Professor of Harvard University, and Chairman of the US AEC Advisory Committee on Reactor Safeguards, as well as consultant on air cleaning

  8. RCRA Facility Investigation/Remedial Investigation Report with Baseline Risk Assessment for the Fire Department Hose Training Facility (904-113G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-04-01

    This report documents the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation/Baseline Risk Assessment (RFI/RI/BRA) for the Fire Department Hose Training Facility (FDTF) (904-113G).

  9. Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Alfred Wickline

    2007-01-01

    Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval

  10. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    International Nuclear Information System (INIS)

    ROGERS, P.M.

    2000-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted

  11. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, P.M.

    2000-06-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.

  12. The disposal of radioactive waste on land

    Energy Technology Data Exchange (ETDEWEB)

    None

    1957-09-01

    A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

  13. Corrective Action Investigation Plan for Corrective Action Unit 542: Disposal Holes, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Laura Pastor

    2006-01-01

    Corrective Action Unit (CAU) 542 is located in Areas 3, 8, 9, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 542 is comprised of eight corrective action sites (CASs): (1) 03-20-07, ''UD-3a Disposal Hole''; (2) 03-20-09, ''UD-3b Disposal Hole''; (3) 03-20-10, ''UD-3c Disposal Hole''; (4) 03-20-11, ''UD-3d Disposal Hole''; (5) 06-20-03, ''UD-6 and UD-6s Disposal Holes''; (6) 08-20-01, ''U-8d PS No.1A Injection Well Surface Release''; (7) 09-20-03, ''U-9itsy30 PS No.1A Injection Well Surface Release''; and (8) 20-20-02, ''U-20av PS No.1A Injection Well Surface Release''. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 30, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 542. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 542 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Conduct geophysical surveys to

  14. A historical context of municipal solid waste management in the United States.

    Science.gov (United States)

    Louis, Garrick E

    2004-08-01

    Municipal solid waste management (MSWM) in the United States is a system comprised of regulatory, administrative, market, technology, and social subcomponents, and can only be understood in the context of its historical evolution. American cities lacked organized public works for street cleaning, refuse collection, water treatment, and human waste removal until the early 1800s. Recurrent epidemics forced efforts to improve public health and the environment. The belief in anticontagionism led to the construction of water treatment and sewerage works during the nineteenth century, by sanitary engineers working for regional public health authorities. This infrastructure was capital intensive and required regional institutions to finance and administer it. By the time attention turned to solid waste management in the 1880s, funding was not available for a regional infrastructure. Thus, solid waste management was established as a local responsibility, centred on nearby municipal dumps. George Waring of New York City organized solid waste management around engineering unit operations; including street sweeping, refuse collection, transportation, resource recovery and disposal. This approach was adopted nationwide, and was managed by City Departments of Sanitation. Innovations such as the introduction of trucks, motorized street sweepers, incineration, and sanitary landfill were developed in the following decades. The Resource Conservation and Recovery Act of 1976 (RCRA), is the defining legislation for MSWM practice in America today. It forced the closure of open dumps nationwide, and required regional planning for MSWM. The closure of municipal dumps caused a 'garbage crisis' in the late 1980s and early 1990s. Private companies assumed an expanded role in MSWM through regional facilities that required the transportation of MSW across state lines. These transboundary movements of MSW created the issue of flow control, in which the US Supreme Court affirmed the protection

  15. Final disposal of high levels waste and spent nuclear fuel

    International Nuclear Information System (INIS)

    Gelin, R.

    1984-05-01

    Foreign and international activities on the final disposal of high-level waste and spent nuclear fuel have been reviewed. A considerable research effort is devoted to development of acceptable disposal options. The different technical concepts presently under study are described in the report. Numerous studies have been made in many countries of the potential risks to future generations from radioactive wastes in underground disposal repositories. In the report the safety assessment studies and existing performance criteria for geological disposal are briefly discussed. The studies that are being made in Canada, the United States, France and Switzerland are the most interesting for Sweden as these countries also are considering disposal into crystalline rocks. The overall time-tables in different countries for realisation of the final disposal are rather similar. Normally actual large-scale disposal operations for high-level wastes are not foreseen until after year 2000. In the United States the Congress recently passed the important Nuclear Waste Policy Act. It gives a rather firm timetable for site-selection and construction of nuclear waste disposal facilities. According to this act the first repository for disposal of commercial high-level waste must be in operation not later than in January 1998. (Author)

  16. Deep underground disposal of radioactive waste in the United Kingdom

    International Nuclear Information System (INIS)

    Mathieson, J.

    1995-01-01

    The UK Government's radioactive waste disposal policy is for intermediate-level waste, and low-level waste as necessary, to be buried in a deep underground repository, and Nirex is the company, owned by the nuclear industry, charged with developing that deep facility. The Company's current focus is on surface-based geological investigations to determine the suitability of a potential repository site near Sellafield, Cumbria, in north-west England. Nirex's next step is to construct a deep underground laboratory (rock characterization facility, or RCF). Subject to a successful outcome from these investigations, Nirex will submit a planning application for the 650m deep repository at the end of this decade; this will be the subject of a further public inquiry. The timetable for the project assumes that a deep repository, capable of taking 400,000m 3 of waste, will be available by about 2010. In 1994, the UK Government began reviewing the future of the nuclear power industry and, as a separate exercise, radioactive waste management and disposal policy. Both reviews involved widespread consultations. The radwaste review has concentrated on three aspects: general policies; legal aspects of disposal (including safety requirements); and the principles of site selection and the protection of human health. Preliminary conclusions of the main radwaste review were published in August 1994. These confirmed that government continued to favor disposal rather than extended surface storage of waste. The final outcome of the review, including institutional aspects, is expected in the Spring of 1995

  17. Chemical technology of the systems, partitioning and separation, disposal

    International Nuclear Information System (INIS)

    Volk, V.I.

    1997-01-01

    A reactor-accelerator reprocessing complex is described. The complex comprises an electronuclear transmutation installation and chemical and technological support units for maintenance of the steady-state of the blanket, separation of short-lived transmutation products to be disposed of from other components of the blanket, chemical conversion to relevant stable species of products to be disposed of for interim storage and disposal

  18. Overview of commercial low-level radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Smith, P.

    1994-01-01

    Disposal of commercial low-level radioactive waste (LLW) is a critical part of the national infrastructure needed to maintain the health of American businesses, universities, and hospitals. Currently only 19 States (located in the Northwest and Southeast) have access to operating disposal facilities; all other States are storing their LLW until they open new disposal facilities on their own or in concert with other States through regional compact agreements. In response to recommendations from the National Governors Association, Congress assigned the burden for LLW disposal to all States, first in 1980 through Public Law 96-573, the open-quotes Low-level Radioactive Waste Policy Actclose quotes, and again in 1986 through Public Law 99-240, the open-quotes Low-Level Radioactive Waste Policy Amendments Act of 1985close quotes. As directed by Congress, the Department of Energy provides technical assistance to States and compact regions with this task. After almost 14 years, nine compact regions have been ratified by Congress; California, Texas, North Carolina, and Nebraska have submitted license applications; California has issued an operating license; and the number of operating disposal facilities has decreased from three to two

  19. Greater confinement disposal program at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.; Towler, O.A.; Peterson, D.L.; Johnson, G.M.; Helton, B.D.

    1984-01-01

    The first facility to demonstrate Greater Confinement Disposal (GCD) in a humid environment in the United States has been built and is operating at the Savannah River Plant. GCD practices of waste segregation, packaging, emplacement below the root zone, and waste stabilization are being used in the demonstration. Activity concentrations to select wastes for GCD are based on a study of SRP burial records, and are equal to or less than those for Class B waste in 10CFR61. The first disposal units to be constructed are 9-foot diameter, thirty-foot deep boreholes which will be used to dispose of wastes from production reactors, tritiated wastes, and selected wastes from off-site. In 1984 an engineered GCD trench will be constructed for disposal of boxed wastes and large bulky items. 2 figures, 1 table

  20. Resource Conservation and Recovery Act (RCRA) Characterization of Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Nichols, D.M.

    1998-01-01

    As a result of the end of the Cold War and the Nonproliferation treaty, the United States is left with quantifies of spent nuclear fuel. The final disposition of the spent nuclear fuel is yet to be determined. However, one issue that plagues the holders of this material is 'if this material is no longer required and must be disposed, how will it be classified under current U.S. environmental laws and regulations?' This paper provides one site's position on the characterization of the spent nuclear fuel as a non-hazardous solid waste

  1. RCRA closure plan for the Bear Creek Burial Grounds B Area and Walk- In Pits at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-01-01

    In June 1987, the RCRA Closure/Postclosure Plan for the Bear Creek Burial Grounds (BCBG) was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval. TDEC modified and issued the plan approved on September 30, 1987. Subsequently, this plan was modified again and approved as Y/TS-395, Revised RCRA Closure Plan for the Bear Creek Burial Grounds (February 29, 1988). Y/TS-395 was initially intended to apply to A Area, C-West, B Area, and the Walk-In Pits of BCBG. However, a concept was developed to include the B Area (non-RCRA regulated) in the Walk-In Pits so that both areas would be closed under one cap. This approach included a tremendous amount of site preparation with an underlying stabilization base of 16 ft of sand for blast protection. The plan was presented to the state of Tennessee on March 8, 1990, and the Department of Energy was requested to review other unique alternatives to close the site. This amended closure plan goes further to include inspection and maintenance criteria along with other details

  2. An example of system integration for RCRA policy analysis

    International Nuclear Information System (INIS)

    Tonn, B.; Goeltz, R.; Schmidt, K.

    1991-01-01

    This paper describes the synthesis of various computer technologies and software systems used on a project to estimate the costs of remediating Solid Waste Management Units (SWMUs) that fall under the corrective action provisions of the Resource Conservation and Recovery Act (RCRA). The project used two databases collected by Research Triangle Institute (RTI) that contain information on SWMUs and a PC-based software system called CORA that develops cost estimates for remediating SWMUs. The project team developed rules to categorize every SWMU in the databases by the kinds of technologies required to clean them up. These results were input into CORA, which estimated costs associated with the technologies. Early on, several computing challenges presented themselves. First, the databases have several hundred thousand records each. Second, the categorization rules could not be written to cover all combinations of variables. Third, CORA is run interactively and the analysis plan called for running CORA tens of thousands of times. Fourth, large data transfers needed to take place between RTI and Oak Ridge National Laboratory. Solutions to these problems required systems integration. SWMU categorization was streamlined by using INTERNET as was the data transfer. SAS was used to create files used by a program called SuperKey that was used to run CORA. Because the analysis plan required the generation of hundreds of thousands of cost estimates, memory management software was needed to allow the portable IBM P70 to do the job. During the course of the project, several other software packages were used, including: SAS System for Personal Computers (SAS/PC), DBase III, LOTUS 1-2-3, PIZAZZ PLUS, LOTUS Freelance Plus, and Word Perfect. Only the comprehensive use of all available hardware and software resources allowed this project to be completed within the time and budget constraints. 5 refs., 3 figs., 3 tabs

  3. Design and operational experience of low level radioactive waste disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Grimwood, P. D.

    1997-01-01

    Low level radioactive wastes have been disposed of at the Drigg near-surface disposal site for over 30 years. These are carried out under a disposal authorization granted by the UK Environment Agency. This is augmented by a three tier comprehensive system of waste controls developed by BNFL involving wasteform specification, consignor and waste stream qualification and waste consignment verification. Until 1988 wastes were disposed of into trench facilities. However, based on a series of integrated optioneering studies, new arrangements have since been brought into operation. Central to these is a wasteform specification based principally on high force compaction of wastes, grouting within 20 m 3 steel overpack containers to essentially eliminate associated voidage and subsequent disposal in concrete lined vaults. These arrangements ensure efficient utilisation of the Drigg site capacity and a cost-effective disposal concept which meets both national and international standards. (author). 7 figs

  4. Performance assessment for a hypothetical low-level waste disposal facility

    International Nuclear Information System (INIS)

    Smith, C.S.; Rohe, M.J.; Ritter, P.D.

    1997-01-01

    Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study

  5. Performance assessment for a hypothetical low-level waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Smith, C.S.; Rohe, M.J.; Ritter, P.D. [and others

    1997-01-01

    Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

  6. Addendum to the RCRA Assessment Report for Single-Shell Tank Waste Management Area S-SX at the Hanford Site

    International Nuclear Information System (INIS)

    Chou, C.J.; Johnson, V.G.

    1999-01-01

    The initial Resource Conservation and Recovery Act (RCRA) groundwater quality assessment report for Waste Management Area S-SX (PNNL-11810) was issued in January 1998. The report stated a plan for conducting continued assessment would be developed after addressing Washington State Department of Ecology (Ecology) comments on initial findings in PNNL-11810. Comments from Ecology were received by US Department of Energy, Richland Operations Office (DOE-RL) on September 24, 1998. Shortly thereafter, Ecology and DOE began dispute resolution and related negotiations about tank farm vadose issues. This led to proposed new Tri-Party Agreement milestones covering a RCRA Facility Investigation-Corrective Measures Study (RFI/CMS) of the four single-shell tank farm waste management areas that were in assessment status (Waste Management Areas B-BX-BY, S-SX, T and TX-TY). The RCRA Facility Investigation includes both subsurface (vadose zone and groundwater) and surface (waste handling facilities and grounds) characterization. Many of the Ecology comments on PNNL-11810 are more appropriate for, and in many cases are superseded by, the RFI/CMS at Waste Management Area S-SX. The proposed Tri-Party Agreement milestone changes that specify the scope and schedule for the RFI/CMS work plans (Tri-Party Agreement change number M-45-98-0) were issued for public comment in February 1999. The Tri-Party Agreement narrative indicates the ongoing groundwater assessments will be integrated with the RFI/CMS work plans. This addendum documents the disposition of the Ecology comments on PNNL-11810 and identifies which comments were more appropriate for the RFI/CMS work plan

  7. Addendum to the RCRA Assessment Report for Single-Shell Tank Waste Management Area S-SX at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Chou, C.J.; Johnson, V.G.

    1999-10-07

    The initial Resource Conservation and Recovery Act (RCRA) groundwater quality assessment report for Waste Management Area S-SX (PNNL-11810) was issued in January 1998. The report stated a plan for conducting continued assessment would be developed after addressing Washington State Department of Ecology (Ecology) comments on initial findings in PNNL-11810. Comments from Ecology were received by US Department of Energy, Richland Operations Office (DOE-RL) on September 24, 1998. Shortly thereafter, Ecology and DOE began dispute resolution and related negotiations about tank farm vadose issues. This led to proposed new Tri-Party Agreement milestones covering a RCRA Facility Investigation-Corrective Measures Study (RFI/CMS) of the four single-shell tank farm waste management areas that were in assessment status (Waste Management Areas B-BX-BY, S-SX, T and TX-TY). The RCRA Facility Investigation includes both subsurface (vadose zone and groundwater) and surface (waste handling facilities and grounds) characterization. Many of the Ecology comments on PNNL-11810 are more appropriate for, and in many cases are superseded by, the RFI/CMS at Waste Management Area S-SX. The proposed Tri-Party Agreement milestone changes that specify the scope and schedule for the RFI/CMS work plans (Tri-Party Agreement change number M-45-98-0) were issued for public comment in February 1999. The Tri-Party Agreement narrative indicates the ongoing groundwater assessments will be integrated with the RFI/CMS work plans. This addendum documents the disposition of the Ecology comments on PNNL-11810 and identifies which comments were more appropriate for the RFI/CMS work plan.

  8. Performance Demonstration Program Plan for RCRA Constituent Analysis of Solidified Wastes

    International Nuclear Information System (INIS)

    2006-01-01

    The Performance Demonstration Program (PDP) for Resource Conservation and Recovery Act (RCRA) constituents distributes test samples for analysis of volatile organic compounds (VOCs), semivolatile organic compounds (SVOCs), and metals in solid matrices. Each distribution of test samples is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD; DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department. The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the RCRA PDP. Participating laboratories demonstrate acceptable performance by successfully analyzing single-blind performance evaluation samples (subsequently referred to as PDP samples) according to the criteria established in this plan. PDP samples are used as an independent means to assess laboratory performance regarding compliance with the WAP quality assurance objectives (QAOs). The concentrations of analytes in the PDP samples address levels of regulatory concern and encompass the range of concentrations anticipated in waste characterization samples. The WIPP requires analyses of homogeneous solid wastes to demonstrate compliance with regulatory requirements. These analyses must be performed by laboratories that demonstrate acceptable performance in this PDP. These analyses are referred to as WIPP analyses, and the samples on which they are performed are referred to as WIPP samples. Participating laboratories must analyze PDP samples using the same procedures used for WIPP samples.

  9. Data Summary Report for 116-N-1 and 116-N-3 Facility Soil Sampling to Support Remedial Design

    International Nuclear Information System (INIS)

    Ludowise, J. D.

    1999-01-01

    The 116-N-1 (1301-N) and 116-N-3 (1325-N) liquid waste disposal facilities (LWDFs) are to be remediated beginning in July 2000. Each LWDF consists of a crib and a trench. Under the proposed remedial action (DOE-RL 1998b), pipelines and above ground structures would be removed. Clean overburden material would be excavated and stockpiled. Contaminated soils would be excavated, treated (if required to meet Resource Conservation and Recovery Act of 1976 [RCRA] land disposal restrictions), and finally disposed at the Environmental Restoration Disposal Facility (ERDF). The sites would then be backfilled, graded, and revegetated. The purpose of this report is to summarize results of the sampling effort and discuss how they apply to the conceptual model of the sites and the planned remedial action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 and closure action under RCRA

  10. HLW disposal dilemma

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.

    2003-01-01

    The radioactive waste is an inevitable residue from the use of radioactive materials in industry, research and medicine, and from the operation of generating electricity nuclear power stations. The management and disposal of such waste is therefore an issue relevant to almost all countries. Undoubtedly the biggest issue concerning radioactive waste management is that of high level waste. The long-lived nature of some types of radioactive wastes and the associated safety implications of disposal plans have raised concern amongst those who may be affected by such facilities. For these reasons the subject of radioactive waste management has taken on a high profile in many countries. Not one Member State in the European Union can say that their high level waste will be disposed of at a specific site. Nobody can say 'that is where it is going to go'. Now, there is a very broad consensus on the concept of geological disposal. The experts have little, if any doubt that we could safely dispose of the high level wastes. Large sectors of the public continue to oppose to most proposals concerning the siting of repositories. Given this, it is increasingly difficult to get political support, or even political decisions, on such sites. The failure to advance to the next step in the waste management process reinforces the public's initial suspicion and resistance. In turn, this makes the political decisions even harder. In turn, this makes the political decisions even harder. The management of spent fuel from nuclear power plant became a crucial issue, as the cooling pond of the Romanian NPP is reaching saturation. During the autumn of 2000, the plant owner proceeded with an international tendering process for the supply of a dry storage system to be implemented at the Cernavoda station to store the spent fuel from Unit 1 and eventually from Unit 2 for a minimum period of 50 years. The facility is now in operation. As concern the disposal of the spent fuel, the 'wait and see

  11. POST-CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 92: AREA 6 DECON PAD FACILITY, NEVADA. TEST SITE NEVADA, FOR THE PERIOD JANUARY 2004 - DECEMBER 2004

    International Nuclear Information System (INIS)

    BECHTEL NEVADA

    2005-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility, Nevada Test Site, Nevada. CAU 92 was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection, 1995) and the Federal Facility Agreement and Consent Order of 1996 on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02, Decontamination Pond (RCRA), requires post-closure inspections. CAS 06-04-01, Decon Pad Oil/Water Separator, is located inside the fence at the Building 6-605 compound. This report covers the annual period January 2004 through December 2004

  12. Disposal of radioactive wastes arising in the United Kingdom from the peaceful uses of atomic energy

    CERN Document Server

    Bryant, P M

    1971-01-01

    This paper describes United Kingdom policy in relation to radioactive waste and summarises the relevant legislation ad methods of control. Data are given on the amounts of radioactivity discharged as waste from establishments of the United Kingdom Atomic Energy Authority, the nuclear power stations operated by the Electricity Generating Boards and other users of radioactive materials. Studies of the behaviour of radioactivity in the environment are reported with particular reference to food chains and other potential sources of irradiation of the public. The results of environmental monitoring are presented and estimates are made of radiation doses received by individual members of the public and larger population groups as a result of waste disposal. It is concluded that the doses received are all within the appropriate limits recommended by the International Commission on Radiological Protection, and in most cases are trivial.

  13. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the Period October 1999-October 2000

    Energy Technology Data Exchange (ETDEWEB)

    D. F. Emer

    2001-03-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 1999-October 2000 period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in August 2000. There has been no subsidence at any of the markers since monitoring began seven years ago. The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that maybe indicative of moisture movement at a point located directly beneath each trench. Precipitation for the period October 1999 through October 2000 was 10.44 centimeters (cm) (4.11 inches [in.]) (U.S. National Weather Service, 2000). The prior year annual rainfall (January 1999 through December 1999) was 10.13cm (3.99 in.). The highest 30-day cumulative rainfall occurred on March 8, 2000, with a total of 6.63 cm (2.61 in.). The heaviest daily precipitation occurred on February 23,2000, with a total of 1.70 cm (0.67 in.) falling in that 24-hour period. The recorded average annual rainfall for this site, from 1972 to January 1999, is 15.06 cm (5.93 in.). All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the

  14. Unit cell modeling in support of interim performance assessment for low level tank waste disposal

    International Nuclear Information System (INIS)

    Kline, N.W.

    1996-01-01

    A unit cell model is used to simulate the base analysis case and related sensitivity cases for the interim performance assessment of low level tank waste disposal. Simulation case results are summarized in terms of fractional contaminant release rates to the vadose zone and to the water table at the unconfined aquifer. Results suggest that the crushed glass water conditioning layer at the top of the facility and the chemical retardation pad at the bottom of the facility can be important components of the facility. Results also suggest that the release rates to the water table are dominated by the release rate from the waste form

  15. DUSTMS-D: DISPOSAL UNIT SOURCE TERM - MULTIPLE SPECIES - DISTRIBUTED FAILURE DATA INPUT GUIDE.

    Energy Technology Data Exchange (ETDEWEB)

    SULLIVAN, T.M.

    2006-01-01

    Performance assessment of a low-level waste (LLW) disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the source term). The focus of this work is to develop a methodology for calculating the source term. In general, the source term is influenced by the radionuclide inventory, the wasteforms and containers used to dispose of the inventory, and the physical processes that lead to release from the facility (fluid flow, container degradation, wasteform leaching, and radionuclide transport). Many of these physical processes are influenced by the design of the disposal facility (e.g., how the engineered barriers control infiltration of water). The complexity of the problem and the absence of appropriate data prevent development of an entirely mechanistic representation of radionuclide release from a disposal facility. Typically, a number of assumptions, based on knowledge of the disposal system, are used to simplify the problem. This has been done and the resulting models have been incorporated into the computer code DUST-MS (Disposal Unit Source Term-Multiple Species). The DUST-MS computer code is designed to model water flow, container degradation, release of contaminants from the wasteform to the contacting solution and transport through the subsurface media. Water flow through the facility over time is modeled using tabular input. Container degradation models include three types of failure rates: (a) instantaneous (all containers in a control volume fail at once), (b) uniformly distributed failures (containers fail at a linear rate between a specified starting and ending time), and (c) gaussian failure rates (containers fail at a rate determined by a mean failure time, standard deviation and gaussian distribution). Wasteform release models include four release mechanisms: (a) rinse with partitioning (inventory is released instantly upon container failure subject to equilibrium partitioning (sorption) with

  16. 100-D Ponds closure plan. Revision 1

    International Nuclear Information System (INIS)

    Petersen, S.W.

    1997-09-01

    The 100-D Ponds is a Treatment, Storage, and Disposal (TSD) unit on the Hanford Facility that received both dangerous and nonregulated waste. This Closure Plan (Rev. 1) for the 100-D Ponds TSD unit consists of a RCRA Part A Dangerous Waste Permit Application (Rev. 3), a RCRA Closure Plan, and supporting information contained in the appendices to the plan. The closure plan consists of eight chapters containing facility description, process information, waste characteristics, and groundwater monitoring data. There are also chapters containing the closure strategy and performance standards. The strategy for the closure of the 100-D Ponds TSD unit is clean closure. Appendices A and B of the closure plan demonstrate that soil and groundwater beneath 100-D Ponds are below cleanup limits. All dangerous wastes or dangerous waste constituents or residues associated with the operation of the ponds have been removed, therefore, human health and the environment are protected. Discharges to the 100-D Ponds, which are located in the 100-DR-1 operable unit, were discontinued in June 1994. Contaminated sediment was removed from the ponds in August 1996. Subsequent sampling and analysis demonstrated that there is no contamination remaining in the ponds, therefore, this closure plan is a demonstration of clean closure

  17. X-231B technology demonstration for in situ treatment of contaminated soil: Technology evaluation and screening

    International Nuclear Information System (INIS)

    Siegrist, R.L.; Morris, M.I.; Donaldson, T.L.; Palumbo, A.V.; Herbes, S.E.; Jenkins, R.A.; Morrissey, C.M.; Harris, M.T.

    1993-08-01

    The Portsmouth Gaseous Diffusion Plant (Ports) is located approximately 70 miles south of Columbus in southern Ohio. Among the several waste management units on the facility, the X-231B unit consists of two adjacent oil biodegradation plots. The plots encompass ∼ 0.8 acres and were reportedly used from 1976 to 1983 for the treatment and disposal of waste oils and degreasing solvents, some containing uranium-235 and technetium-99. The X-231B unit is a regulated solid waste management unit (SWMU) under the Resource Conservation and Recovery Act (RCRA). The X-231B unit is also a designated SWMU located within Quadrant I of the site as defined in an ongoing RCRA Facilities Investigation and Corrective Measures Study (RFI/CMS). Before implementing one or more Technology Demonstration Project must be completed. The principal goal of this project was to elect and successfully demonstrate one ore more technologies for effective treatment of the contaminated soils associated with the X-231B unit at PORTS. The project was divided into two major phases. Phase 1 involved a technology evaluation and screening process. The second phase (i.e., Phase 2) was to involve field demonstration, testing and evaluation of the technology(s) selected during Phase 1. This report presents the methods, results, and conclusions of the technology evaluation and screening portion of the project

  18. Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1995

    International Nuclear Information System (INIS)

    Hartman, M.J.

    1996-02-01

    This report presents the annual hydrogeologic evaluation of 19 Resource Conservation and Recovery Act of 1976 facilities and 1 nonhazardous waste facility at the US Department of Energy's Hanford Site. Although most of the facilities no longer receive dangerous waste, a few facilities continue to receive dangerous waste constituents for treatment, storage, or disposal. The 19 Resource Conservation and Recovery Act facilities comprise 29 waste management units. Nine of the units are monitored under groundwater quality assessment status because of elevated levels of contamination indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration profiles, rate, and extent of migration are evaluated. Groundwater is monitored at the other 20 units to detect leakage, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1994 and September 1995. Groundwater quality is described for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides

  19. Annual report for RCRA groundwater monitoring projects at Hanford site facilities for 1994

    International Nuclear Information System (INIS)

    1995-02-01

    This report presents the annual hydrogeologic evaluation of 19 Resource Conservation and Recovery Act of 1976 facilities and 1 nonhazardous waste facility at the U.S. Department of Energy's Hanford Site. Although most of the facilities no longer receive dangerous waste, a few facilities continue to receive dangerous waste constituents for treatment, storage, or disposal. The 19 Resource Conservation and Recovery Act facilities comprise 29 waste management units. Nine of the units are monitored under groundwater quality assessment status because of elevated levels of contamination indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration profiles, rate, and extent of migration are evaluated. Groundwater is monitored at the other 20 units to detect leakage, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1993 and September 1994. Groundwater quality is described for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides

  20. Nuclear waste disposal in subseabed geologic formatons: the Seabed Disposal Program

    International Nuclear Information System (INIS)

    Anderson, D.R.

    1979-05-01

    The goal of the Seabed Disposal Program is to assess the technical and environmental feasibility of using geologic formations under the sea floor for the disposal of processed high-level radioactive wastes or repackaged spent reactor fuel. Studies are focused on the abyssal hill regions of the sea floors in the middle of tectonic plates and under massive surface current gyres. The red-clay sediments here are from 50 to 100 meters thick, are continuously depositional (without periods of erosion), and have been geologically and climatologically stable for millions of years. Mineral deposits and biological activity are minimal, and bottom currents are weak and variable. Five years of research have revealed no technological reason why nuclear waste disposal in these areas would be impractical. However, scientific assessment is not complete. Also, legal political, and sociological factors may well become the governing elements in such use of international waters. These factors are being examined as part of the work of the Seabed Working Group, an international adjunct of the Seabed Program, with members from France, England, Japan, Canada, and the United States

  1. Nuclear waste disposal in subseabed geologic formatons: the Seabed Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, D.R.

    1979-05-01

    The goal of the Seabed Disposal Program is to assess the technical and environmental feasibility of using geologic formations under the sea floor for the disposal of processed high-level radioactive wastes or repackaged spent reactor fuel. Studies are focused on the abyssal hill regions of the sea floors in the middle of tectonic plates and under massive surface current gyres. The red-clay sediments here are from 50 to 100 meters thick, are continuously depositional (without periods of erosion), and have been geologically and climatologically stable for millions of years. Mineral deposits and biological activity are minimal, and bottom currents are weak and variable. Five years of research have revealed no technological reason why nuclear waste disposal in these areas would be impractical. However, scientific assessment is not complete. Also, legal political, and sociological factors may well become the governing elements in such use of international waters. These factors are being examined as part of the work of the Seabed Working Group, an international adjunct of the Seabed Program, with members from France, England, Japan, Canada, and the United States.

  2. Solid waste landfills under the Resource Conservation and Recovery Act Subtitle D

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This document provides guidance for meeting: (1) Guidelines for the Land Disposal of Solid Waste (40 CFR 241); (2) Criteria for Classification of Solid Waste Disposal Facilities and Practices (40 CFR 257); and (3) Criteria for Municipal Solid Waste Landfills (MSWLFs) (40 CFR Part 258). Revisions to 40 CFR 257 and a new Part 258 were published in the Federal Register (56 FR 50978, 10/9/91). The Guidelines for the Land Disposal of Solid Waste set requirements and recommended procedures to ensure that the design, construction, and operation of land disposal sites is done in a manner that will protect human health and the environment. These regulations are applicable to MSWLFs and non-MSWLFs (e.g., landfills used only for the disposal of demolition debris, commercial waste, and/or industrial waste). These guidelines are not applicable to the, land disposal of hazardous, agricultural, and/or mining wastes. These criteria are to be used under the Resource Conservation and Recovery Act (RCRA) in determining which solid waste disposal facilities pose a reasonable possibility of adversely affecting human health or the environment. Facilities failing to satisfy these criteria will be considered to be open dumps which are prohibited under Section 4005 of RCRA. The Criteria for MSWLFs are applicable only to MSWLFs, including those MSWLFs in which sewage sludge is co-disposed with household waste. Based on specific criteria, certain MSWLFs are exempt from some, or all, of the regulations of 40 CFR 258. MSWLFs that fail to satisfy the criteria specified in 40 CFR 258 are also considered open dumps for the purposes of Section 4005 of RCRA. Through the use of a series of interrelated flow diagrams, this guidance document directs the reader to each design, operation, maintenance, and closure activity that must be performed for MSWLFs and non-MSWLFs.

  3. New land disposal restrictions on contaminated soil and debris, and newly identified toxicity characteristic organics

    International Nuclear Information System (INIS)

    Fortune, William B.; Schumann, Jean C.; Fallon, William E.; Badden, Janet W.; Smith, Edward H.

    1992-01-01

    The applicability of the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDR) program to radioactive mixed wastes (RMW) has been clarified through U.S. Environmental Protection Agency (EPA) and U.S. Department of Energy (DOE) rulemakings and notices. However, a number of waste management concerns involving RMW and RMW-contaminated soil and debris continue to exist with respect to achieving compliance with LDR provisions and treatment standards. Consequently, DOE has become increasingly proactive in its participation in the LDR rulemaking process and in the identification of LDR compliance issues associated with its RMW inventories. Both data and recommendations from across the DOE complex were collected and transmitted to EPA in response to proposed requirements that would implement LDR for contaminated soil and debris, and certain newly identified toxicity characteristic (TC) organics. Much of this information focused on concerns related to the application of proposed regulatory approaches to RMW streams. Highlights from the information included in these DOE responses are presented. (author)

  4. High-level nuclear waste disposal

    International Nuclear Information System (INIS)

    Burkholder, H.C.

    1985-01-01

    The meeting was timely because many countries had begun their site selection processes and their engineering designs were becoming well-defined. The technology of nuclear waste disposal was maturing, and the institutional issues arising from the implementation of that technology were being confronted. Accordingly, the program was structured to consider both the technical and institutional aspects of the subject. The meeting started with a review of the status of the disposal programs in eight countries and three international nuclear waste management organizations. These invited presentations allowed listeners to understand the similarities and differences among the various national approaches to solving this very international problem. Then seven invited presentations describing nuclear waste disposal from different perspectives were made. These included: legal and judicial, electric utility, state governor, ethical, and technical perspectives. These invited presentations uncovered several issues that may need to be resolved before high-level nuclear wastes can be emplaced in a geologic repository in the United States. Finally, there were sixty-six contributed technical presentations organized in ten sessions around six general topics: site characterization and selection, repository design and in-situ testing, package design and testing, disposal system performance, disposal and storage system cost, and disposal in the overall waste management system context. These contributed presentations provided listeners with the results of recent applied RandD in each of the subject areas

  5. Hungary. Closure issues for centralized waste treatment and disposal facility in Puspokszilagy, Hungary

    International Nuclear Information System (INIS)

    2001-01-01

    The facility was commissioned in 1976. At the time that its mission was formulated, the facility was designed to collect, transport, treat as necessary and dispose all radioactive waste originating from institutional use of radioactivity. The facility is government owned and presently operated by the Budapest branch of the State Public Health and Medical Officer Services. The disposal site is located on the ridge of a hill near Puspokszilagy village approximately 40 km Northeast of Budapest. The disposal units are located in Quaternary layers of silt and clay sequences. Annual average precipitation is approximately 650-700 mm. The facility is a typical shallow land, near surface engineered type disposal unit. There are concrete trenches and shallow wells for waste disposal purposes

  6. Salt disposal of heat-generating nuclear waste

    International Nuclear Information System (INIS)

    Leigh, Christi D.; Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United

  7. Salt disposal of heat-generating nuclear waste.

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from

  8. Long-term, low-level radwaste volume-reduction strategies. Volume 4. Waste disposal costs. Final report

    International Nuclear Information System (INIS)

    Sutherland, A.A.; Adam, J.A.; Rogers, V.C.; Merrell, G.B.

    1984-11-01

    Volume 4 establishes pricing levels at new shallow land burial grounds. The following conclusions can be drawn from the analyses described in the preceding chapters: Application of volume reduction techniques by utilities can have a significant impact on the volumes of wastes going to low-level radioactive waste disposal sites. Using the relative waste stream volumes in NRC81 and the maximum volume reduction ratios provided by Burns and Roe, Inc., it was calculated that if all utilities use maximum volume reduction the rate of waste receipt at disposal sites will be reduced by 40 percent. When a disposal site receives a lower volume of waste its total cost of operation does not decrease by the same proportion. Therefore the average cost for a unit volume of waste received goes up. Whether the disposal site operator knows in advance that he will receive a smaller amount of waste has little influence on the average unit cost ($/ft) of the waste disposed. For the pricing algorithm postulated, the average disposal cost to utilities that volume reduce is relatively independent of whether all utilities practice volume reduction or only a few volume reduce. The general effect of volume reduction by utilities is to reduce their average disposal site costs by a factor of between 1.5 to 2.5. This factor is generally independent of the size of the disposal site. The largest absolute savings in disposal site costs when utilities volume reduce occurs when small disposal sites are involved. This results from the fact that unit costs are higher at small sites. Including in the pricing algorithm a factor that penalizes waste generators who contribute larger amounts of the mobile nuclides 3 H, 14 C, 99 Tc, and 129 I, which may be the subject of site inventory limits, lowers unit disposal costs for utility wastes that contain only small amounts of the nuclides and raises unit costs for other utility wastes

  9. Regionalization as a strategy for management of low-level and mixed wastes in the DOE system

    International Nuclear Information System (INIS)

    Bradford, J.D.; Garcia, E.C.; Gillins, R.L.

    1988-01-01

    The Department of Energy has been routinely performing low-level waste volume reduction and/or stabilization treatment at various sites for some time. In general, treatment is performed on waste generated onsite. Disposal is also usually performed onsite since most DOE sites have their own LLW disposal facilities. The DOE initiated studies to evaluate strategies for treatment, storage, and disposal of hazardous and mixed wastes covered in the Resource Conservation and Recovery Act (RCRA) and to ensure that DOE sites are in compliance with RCRA. These studies recommend regionalization as the most cost-effective solution to the treatment and disposal of hazardous and mixed wastes. The DOE's Defense Low-Level Waste Management Program conducted an additional survey of DOE sites to evaluate the status of one specific treatment method, incineration, at these sites. This study included facilities currently in use or intended for treatment of low-level and mixed wastes. A summary of the findings is presented in this paper

  10. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    International Nuclear Information System (INIS)

    2010-01-01

    The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

  11. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-10-04

    The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

  12. Lessons learned from international siting experiences of LLW Disposal facilities

    International Nuclear Information System (INIS)

    McCabe, G.H.

    1990-01-01

    This paper reports that the United States can gain insight into successfully siting low-level radioactive waste (LLW) disposal facilities by studying the process in other nations. Siting experiences in France and Sweden are compared to experiences in the United States. Three factors appear to making siting of LLW disposal facilities easier in France and Sweden than in the United States. First, the level of public trust in the government and the entities responsible for siting, developing, and operating a LLW disposal facility is much greater in France and Sweden than in the United States. Second, France and Sweden are much more dependent on nuclear power than is the United States. Third, French and Swedish citizens do not have the same access to the siting process (i.e., legal means to intervene) as do U.S. citizens. To compensate for these three factors, public officials responsible for siting a facility may need to better listen to the concerns of public interest groups and citizen advisory committees and amend their siting process accordingly and better share power and control with the public. If these two techniques are implemented earnestly by the states, siting efforts may be increasingly more successful in the United States

  13. Corrective Action Investigation Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    Grant Evenson

    2006-04-01

    Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139.

  14. An analysis of the CERCLA response program and the RCRA corrective action program in determining cleanup strategies for federal facilities which have been proposed for listing on the National Priorities List

    International Nuclear Information System (INIS)

    Baker, P.; Vinson, R.

    1994-01-01

    This document was prepared as an issue paper for the Department of Energy to serve in the decision-making process for environmental restoration activities. The paper compares cleanup requirements under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and those currently proposed under Subpart S of the Resource Conservation and Recovery Act (RCRA). The history and regulatory framework for both laws is discussed, and the process for environmental restoration actions under both regulatory programs is compared and contrasted. Contaminants regulated under CERCLA and RCRA differ significantly in that radioactive contaminants are subject to Environmental Protection Agency jurisdiction only under CERCLA. The DOE has the jurisdiction to implement radioactive waste management and cleanup levels under the Atomic Energy Act (AEA) at nuclear weapons facilities. For sites with significant amounts of contaminants which are radioactive only, cleanup under RCRA can present significant advantages, since the DOE can then manage restoration activities under its own authority. There are, conversely several significant advantages for a remedial action being conducted at a CERCLA site recognized on the National Priorities List (NPL). Other provisions in the CERCLA remediation and the RCRA corrective action process offer both advantages and disadvantages related to DOE environmental restoration programs. This paper presents a discussion of significant issues which should be considered in such negotiations

  15. Ecological effects of contaminants in McCoy Branch, 1989-1990

    Energy Technology Data Exchange (ETDEWEB)

    Ryon, M.G. (ed.)

    1992-01-01

    The 1984 Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act (RCRA) required assessment of all current and former solid waste management units. Such a RCRA Facility Investigation (RFI) was required of the Y-12 Plant for their Filled Coal Ash Pond on McCoy Branch. Because the disposal of coal ash in the ash pond, McCoy Branch, and Rogers Quarry was not consistent with the Tennessee Water Quality Act, several remediation steps were implemented or planned for McCoy Branch to address disposal problems. The McCoy Branch RFI plan included provisions for biological monitoring of the McCoy Branch watershed. The objectives of the biological monitoring were to: (1) document changes in biological quality of McCoy Branch after completion of a pipeline and after termination of all discharges to Rogers Quarry, (2) provide guidance on the need for additional remediation, and (3) evaluate the effectiveness of implemented remedial actions. The data from the biological monitoring program will also determine if the classified uses, as identified by the State of Tennessee, of McCoy Branch are being protected and maintained. This report discusses results from toxicity monitoring of snails fish community assessment, and a Benthic macroinvertebrate community assessment.

  16. Institutional aspects of siting nuclear waste disposal facilities in the United States

    International Nuclear Information System (INIS)

    Stewart, J.C.; Prichard, W.C.

    1987-01-01

    This paper has dealt with the institutional issues associated with disposal of nuclear waste in the US. The authors believe that these institutional problems must be resolved, no matter how technologically well suited a site may be for disposal, before site selection may take place. The authors have also pointed out that the geography of the US, with its large arid regions of very low population density, contributes to the institutional acceptability of nuclear waste disposal. Economic factors, especially in sparsely populated areas where the uranium mining and milling industry has caused operation, also weigh on the acceptability of nuclear waste to local communities. This acceptability will be highest where there are existing nuclear facilities and/or facilities which are closed - thus creating unemployment especially where alternative economic opportunities are few

  17. Co-disposal of mixed waste materials

    International Nuclear Information System (INIS)

    Phillips, S.J.; Alexander, R.G.; Crane, P.J.; England, J.L.; Kemp, C.J.; Stewart, W.E.

    1993-08-01

    Co-disposal of process waste streams with hazardous and radioactive materials in landfills results in large, use-efficiencies waste minimization and considerable cost savings. Wasterock, produced from nuclear and chemical process waste streams, is segregated, treated, tested to ensure regulatory compliance, and then is placed in mixed waste landfills, burial trenches, or existing environmental restoration sites. Large geotechnical unit operations are used to pretreat, stabilize, transport, and emplace wasterock into landfill or equivalent subsurface structures. Prototype system components currently are being developed for demonstration of co-disposal

  18. Expanded public notice: Washington State notice of intent for corrective action management unit, Hanford Environmental Restoration Disposal

    International Nuclear Information System (INIS)

    1994-01-01

    This document is to serve notice of the intent to operate an Environmental Restoration Disposal Facility (ERDF), adjacent to the 200 West Area of the Hanford Facility, Richland, Washington, as a Corrective Action Management Unit (CAMU), in accordance with 40 Code of Federal Regulation (CFR) 264.552. The ERDF CAMU will serve as a management unit for the majority of waste (primarily soil) excavated during remediation of waste management sites on the Hanford Facility. Only waste that originates from the Hanford Facility can be accepted in this ERDF CAMU. The waste is expected to consist of dangerous waste, radioactive waste, and mixed waste. Mixed waste contains radioactive and dangerous components. The primary features of the ERDF could include the following: one or more trenches, rail and tractor/trailer container handling capability, railroads, an inventory control system, a decontamination building, and operational offices

  19. Radwaste treatment and disposal

    International Nuclear Information System (INIS)

    Ehn, L.; Breza, M.; Pekar, A.

    2000-01-01

    In this lecture is given the basic information, that is concerning on the RAW treatment and long term disposal of the treated RAW in repository at Mochovce. Then here is given the basic technical and technological information, that is concerning bituminization, plant, the vitrification unit, center for the RAW-treatment (BSC) and repository at Mochovce. (authors)

  20. Waste disposal experts meet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-01-15

    Problems connected with the disposal into the sea of radioactive wastes from peaceful uses of atomic energy are being examined by a panel of experts, convened by the International Atomic Energy Agency. These experts from eight different countries held a first meeting at IAEA headquarters in Vienna from 4-9 December 1958, under the chairmanship of Dr. Harry Brynielsson, Director General of the Swedish Atomic Energy Company. The countries represented are: Canada, Czechoslovakia, France, Japan, Netherlands, United Kingdom and United States. The group will meet again in 1959. (author)

  1. Optimization of uranium mill tailings disposal practices

    International Nuclear Information System (INIS)

    Richardson, Allan C.B.; Rowe, William D.

    1984-01-01

    So far as we have been to discern, no uranium mill tailings pile has yet been properly stabilized for long-term disposal. And although considerable effort is now being directed at developing practical solutions and at establishing standards for permanent disposal, the difficulties in application are diverse. They arise from the variety of environments in which milling is conducted, the significant costs associated with disposing of the large volumes of materials involved, the diverse nature of the hazards to be protected against, and uncertainties in both performance of controls and in how to determine societal responsibilities for management of the long term hazards to human populations from uranium tailings. There are 24 uranium tailings piles in the United States which no longer have responsible owners, and must now be disposed of by the U.S. Government in order to protect public health

  2. Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

    International Nuclear Information System (INIS)

    Connolly, M.J.; Sayer, D.L.

    1993-11-01

    EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

  3. US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

    International Nuclear Information System (INIS)

    Roach, J.A.; Gombert, D.

    1996-01-01

    The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE's mixed waste problems

  4. 25 CFR 700.727 - Impoundment and disposal of unauthorized livestock.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 2 2010-04-01 2010-04-01 false Impoundment and disposal of unauthorized livestock. 700... RELOCATION PROCEDURES New Lands Grazing § 700.727 Impoundment and disposal of unauthorized livestock. Unauthorized livestock within any range unit of the New Lands which are not removed therefrom within the...

  5. 25 CFR 168.16 - Impoundment and disposal of unauthorized livestock.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Impoundment and disposal of unauthorized livestock. 168... REGULATIONS FOR THE HOPI PARTITIONED LANDS AREA § 168.16 Impoundment and disposal of unauthorized livestock. Unauthorized livestock within any range unit of the Hopi Partitioned Lands which are not removed therefrom...

  6. Characterization of Vadose Zone Sediment: Uncontaminated RCRA Borehole Core Samples and Composite Samples

    International Nuclear Information System (INIS)

    Serne, R. Jeffrey; Bjornstad, Bruce N.; Schaef, Herbert T.; Williams, Bruce A.; Lanigan, David C.; Horton, Duane G.; Clayton, Ray E.; Mitroshkov, Alexandre V.; Legore, Virginia L.; O'Hara, Matthew J.; Brown, Christopher F.; Parker, Kent E.; Kutnyakov, Igor V.; Serne, Jennifer N.; Last, George V.; Smith, Steven C.; Lindenmeier, Clark W.; Zachara, John M.; Burke, Deborah Sd.

    2001-01-01

    The overall goal of the of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., is to define risks from past and future single-shell tank farm activities. To meet this goal, CH2M HILL Hanford Group, Inc. asked scientists from Pacific Northwest National Laboratory to perform detailed analyses on vadose zone sediment from within the S-SX Waste Management Area. This report is the first in a series of four reports to present the results of these analyses. Specifically, this report contains all the geologic, geochemical, and selected physical characterization data collected on vadose zone sediment recovered from RCRA borehole bore samples and composite samples. Intact cores from two RCRA boreholes (299-W22-48 and 299-W22-50) near the SX Tank Farm and four, large-quantity grab samples from outcrop sediment on and off the Hanford Site were sampled to better understand the fate of contaminants in the vadose zone beneath underground storage tanks at the Hanford Site. Borehole and outcrop samples analyzed for this report are located outside the tank farms, and therefore may be considered standard or background samples from which to compare contaminated sediments within the tank farms themselves. This report presents our interpretation of the physical, chemical, and mineralogical properties of the uncontaminated vadose zone sediments, and variations in the vertical distribution of these properties. The information presented in this report is intended to support preparation of the S-SX Field Investigation Report to be prepared by CH2M Hill Hanford Group, Inc. as well as future remediation actions at the S-SX Tank Farm

  7. Development of a treatability variance guidance document for US DOE mixed-waste streams

    International Nuclear Information System (INIS)

    Scheuer, N.; Spikula, R.; Harms, T.

    1990-03-01

    In response to the US Department of Energy's (DOE's) anticipated need for variances from the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs), a treatability variance guidance document was prepared. The guidance manual is for use by DOE facilities and operations offices. The manual was prepared as a part of an ongoing effort by DOE-EH to provide guidance for the operations offices and facilities to comply with the RCRA (LDRs). A treatability variance is an alternative treatment standard granted by EPA for a restricted waste. Such a variance is not an exemption from the requirements of the LDRs, but rather is an alternative treatment standard that must be met before land disposal. The manual, Guidance For Obtaining Variance From the Treatment Standards of the RCRA Land Disposal Restrictions (1), leads the reader through the process of evaluating whether a variance from the treatment standard is a viable approach and through the data-gathering and data-evaluation processes required to develop a petition requesting a variance. The DOE review and coordination process is also described and model language for use in petitions for DOE radioactive mixed waste (RMW) is provided. The guidance manual focuses on RMW streams, however the manual also is applicable to nonmixed, hazardous waste streams. 4 refs

  8. Control of water infiltration into near surface LLW disposal units - Progress report on field experiments at a humid region site, Beltsville, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    O' Donnell, Edward [U.S. Nuclear Regulatory Commission, Washington, DC (United States); Ridky, Robert W [University of Maryland, College Park, MD (United States); Schulz, Robert K [University of California, Berkeley, CA (United States)

    1992-07-01

    The study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75x45x10') at Beltsville, MD, and results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: 1) resistive layer barrier, 2) conductive layer barrier, and 3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry into waste and without institutional care. As mentioned in the preceding paragraph, a bioengineering management cover might well be the cover of choice during tho active subsidence phase of a waste disposal unit. Some maintenance is required during that period. Final

  9. Control of water infiltration into near surface LLW disposal units - Progress report on field experiments at a humid region site, Beltsville, Maryland

    International Nuclear Information System (INIS)

    O'Donnell, Edward; Ridky, Robert W.; Schulz, Robert K.

    1992-01-01

    The study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75x45x10') at Beltsville, MD, and results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: 1) resistive layer barrier, 2) conductive layer barrier, and 3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry into waste and without institutional care. As mentioned in the preceding paragraph, a bioengineering management cover might well be the cover of choice during tho active subsidence phase of a waste disposal unit. Some maintenance is required during that period. Final

  10. The disposal of low-level radioactive waste into the sea

    International Nuclear Information System (INIS)

    Saruhashi, Katsuko

    1979-01-01

    Disposal of low-level radioactive wastes is made both on land and in sea. Though the land disposal has been already carried out in the U.S.A. and the U.S.S.R., it is impossible in the narrow land of Japan. In the United States, the wastes solidified with cement in drums were previously abandoned in deep seas of the Pacific and the Atlantic. This is no longer done presently; instead, the land disposal is employed due to its lower costs. In European countries, the sea disposal is performed under OECDNEA, trial disposal in 1961 and full-scale disposal since 1967, in the Atlantic. Meanwhile, in Japan, test sea disposal will be carried out in the near future in deep sea of the northern Pacific, the important sea area for fisheries. The international trends of the deep sea disposal of low-level wastes and the correspondent trends of the same in Japan, in the past years are described. (J.P.N.)

  11. Corrective Action Investigation Plan for Corrective Action Unit 410: Waste Disposal Trenches, Tonopah Test Range, Nevada, Revision 0 (includes ROTCs 1, 2, and 3)

    Energy Technology Data Exchange (ETDEWEB)

    NNSA/NV

    2002-07-16

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 410 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 410 is located on the Tonopah Test Range (TTR), which is included in the Nevada Test and Training Range (formerly the Nellis Air Force Range) approximately 140 miles northwest of Las Vegas, Nevada. This CAU is comprised of five Corrective Action Sites (CASs): TA-19-002-TAB2, Debris Mound; TA-21-003-TANL, Disposal Trench; TA-21-002-TAAL, Disposal Trench; 09-21-001-TA09, Disposal Trenches; 03-19-001, Waste Disposal Site. This CAU is being investigated because contaminants may be present in concentrations that could potentially pose a threat to human health and/or the environment, and waste may have been disposed of with out appropriate controls. Four out of five of these CASs are the result of weapons testing and disposal activities at the TTR, and they are grouped together for site closure based on the similarity of the sites (waste disposal sites and trenches). The fifth CAS, CAS 03-19-001, is a hydrocarbon spill related to activities in the area. This site is grouped with this CAU because of the location (TTR). Based on historical documentation and process know-ledge, vertical and lateral migration routes are possible for all CASs. Migration of contaminants may have occurred through transport by infiltration of precipitation through surface soil which serves as a driving force for downward migration of contaminants. Land-use scenarios limit future use of these CASs to industrial activities. The suspected contaminants of potential concern which have been identified are volatile organic compounds; semivolatile organic compounds; high explosives; radiological constituents including depleted

  12. TMI abnormal wastes disposal options

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.

    1984-03-01

    A substantial quantity of high beta-gamma/high-TRU contaminated wastes are expected from cleanup activities of Unit 2 of the Three Mile Island Nuclear Power Station. Those wastes are not disposable because of present regulatory constraints. Therefore, they must be stored temporarily. This paper discusses three options for storage of those wastes at the Idaho National Engineering Laboratory: (1) storage in temporary storage casks; (2) underground storage in vaults; and (3) storage in silos at a hot shop. Each option is analyzed and evaluated. Also included is a discussion of future disposal strategies, which might be pursued when a suitable federal or commercial repository is built

  13. DOE regulatory reform initiative vitrified mixed waste

    International Nuclear Information System (INIS)

    Carroll, S.J.; Holtzscheiter, E.W.

    1997-01-01

    The US Department of Energy (DOE) is charged with responsibly managing the largest volume of mixed waste in the United States. This responsibility includes managing waste in compliance with all applicable Federal and State laws and regulations, and in a cost-effective, environmentally responsible manner. Managing certain treated mixed wastes in Resource Conservation and Recovery Act (RCRA) permitted storage and disposal units (specifically those mixed wastes that pose low risks from the hazardous component) is unlikely to provide additional protection to human health and the environment beyond that afforded by managing these wastes in storage and disposal units subject to requirements for radiological control. In October, 1995, the DOE submitted a regulatory reform proposal to the Environmental Protection Agency (EPA) relating to vitrified mixed waste forms. The technical proposal supports a regulatory strategy that would allow vitrified mixed waste forms treated through a permit or other environmental compliance mechanism to be granted an exemption from RCRA hazardous waste regulation, after treatment, based upon the inherent destruction and immobilization capabilities of vitrification technology. The vitrified waste form will meet, or exceed the performance criteria of the Environmental Assessment (EA) glass that has been accepted as an international standard for immobilizing radioactive waste components and the LDR treatment standards for inorganics and metals for controlling hazardous constituents. The proposal further provides that vitrified mixed waste would be responsibly managed under the Atomic Energy Act (AEA) while reducing overall costs. Full regulatory authority by the EPA or a State would be maintained until an acceptable vitrified mixed waste form, protective of human health and the environment, is produced

  14. Sampling and analysis plan for the 100-D Ponds voluntary remediation project

    International Nuclear Information System (INIS)

    1996-08-01

    This Sampling and Analysis Plan (SAP) describes the sampling and analytical activities which will be performed to support closure of the 100-D Ponds Resource Conservation and Recovery Act (RCRA) treatment, storage, and/or disposal (TSD) unit. This SAP includes the Field Sampling Plan (FSP) presented in Section 2.0, and the Quality Assurance Project Plan (QAPjP) described in Section 3.0. The FSP defines the sampling and analytical methodologies to be performed, and the QAPjP provides or includes information on the requirements for precision, accuracy, representativeness, comparability, and completeness of the analytical data. This sampling and analysis plan was developed using the Environmental Protection Agency's Seven-Step Data Quality Objectives (DQO) Guidance (EPA, 1994). The purpose of the DQO meetings was (1) to identify the contaminants of concern and their cleanup levels under the Washington State Model Toxics Control Act (MTCA, WAC-173-340) Method B, and (2) to determine the number and locations of samples necessary to verify that the 100-D Ponds meet the cleanup criteria. The data collected will be used to support RCRA closure of this TSD unit

  15. Temporal trend analysis of RCRA groundwater monitoring data

    International Nuclear Information System (INIS)

    Need, E.A.

    1994-01-01

    Statistical analysis of RCRA groundwater monitoring data at a uranium hexafluoride processing facility showed a statistically significant increase in the concentration of gross beta activity in monitor wells downgradient of surface impounds storing calcium fluoride sludge and high pH water. Because evidence of leakage had not been detected in lysimeters installed beneath the impounds, the operator sought an evaluation of other potential causes of the result, including natural variability. This study determined that all five data sets showed either long-term excursionary (spike-like), or seasonal forms of temporal variation. Gross beta had an upward long-term trend with multiple excursions that almost appeared to be seasonal. Gross alpha had an upward long-term trend with multiple excursions that were clearly not seasonal. Specific conductance had both upward and downward long-term trends but no other variations. pH had a downward long-term trend with multiple excursions that were clearly not seasonal. Fluoride had a downward long-term trend without excursions but with clear seasonal variations. The gross beta result that appeared to be a significant change was a spike event on the upward long-term trend

  16. Analysis of alternatives for immobilized low activity waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Burbank, D.A.

    1997-10-28

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

  17. Analysis of alternatives for immobilized low-activity waste disposal

    International Nuclear Information System (INIS)

    Burbank, D.A.

    1997-01-01

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program

  18. Offsite source recovery project - ten years of sealed source recovery and disposal

    Energy Technology Data Exchange (ETDEWEB)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA

    2010-01-01

    meeting the DOE definition of 'transuranic,' OSRP has achieved many milestones, including defense determinations for various isotopes, a WIPP RCRA permit modification to accommodate headspace gas sampling requirements, and approval of a peer-reviewed non-assay radiological characterization methodology. For non-transuranic sources, which OSRP began to recover in 2004, OSRP has achieved NEP A coverage for storage and implemented consolidated storage at both DOE and commercial locations, as well as completing several specific disposal operations. The closure of the Barnwell low-level waste disposal site in 2008 has left 36 states with absolutely no commercial disposal pathway for most sealed sources, increasing the demands on OSRP. This and other current challenges and future work will also be discussed.

  19. Trench design and construction techniques for low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    Tucker, P.G.

    1983-02-01

    This document provides information on trench design and construction techniques which can be used in the disposal of LLW by shallow land burial. It covers practices currently in use not only in the LLW disposal field, but also methods and materials being used in areas of hazardous and municipal waste disposal which are compatible with the performance objectives of 10 CFR Part 61. The complexity of a disposal site and its potential problems dictate the use of site-specific characteristics when designing a LLW disposal trench. This report presents the LLW disposal trench as consisting of various elements or unit processes. The term unit processes is used as it more fully relays the impact of the designer's choice of methods and materials. When choosing a material to fulfill the function of a certain trench element, the designer is also stipulating a portion of his operational procedure which must be compatible with the disposal operation as a whole. Information is provided on the properties, selection, and installation of various materials such as bentonite, soil-cement, polymeric materials, asphaltic materials, and geotechnical fabrics. This is not intended to outline step-by-step procedures. Basically, three time frames are addressed with respect to construction techniques; preoperational, operational, and postoperational. Within each of these time frames there are certain construction techniques which can be employed by the designer to enhance the overall ease of construction and ultimate success of the disposal facility. Among the techniques presented are precontouring the disposal area, alignment of the trench axis, sloping the trench bottom, incremental excavation, and surface water (runoff) management

  20. Savannah River Site - Salt-stone Disposal Facility Performance Assessment Update

    International Nuclear Information System (INIS)

    Newman, J.L.

    2009-01-01

    The Savannah River Site (SRS) Salt-stone Facility is currently in the midst of a Performance Assessment revision to estimate the effect on human health and the environment of adding new disposal units to the current Salt-stone Disposal Facility (SDF). These disposal units continue the ability to safely process the salt component of the radioactive liquid waste stored in the underground storage tanks at SRS, and is a crucial prerequisite for completion of the overall SRS waste disposition plan. Removal and disposal of low activity salt waste from the SRS liquid waste system is required in order to empty tanks for future tank waste processing and closure operations. The Salt-stone Production Facility (SPF) solidifies a low-activity salt stream into a grout matrix, known as salt-stone, suitable for disposal at the SDF. The ability to dispose of the low-activity salt stream in the SDF required a waste determination pursuant to Section 3116 of the Ronald Reagan National Defense Authorization Act of 2005 and was approved in January 2006. One of the requirements of Section 3116 of the NDAA is to demonstrate compliance with the performance objectives set out in Subpart C of Part 61 of Title 10, Code of Federal Regulations. The PA is the document that is used to ensure ongoing compliance. (authors)

  1. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report provides a detailed summary of the activities carried out to sample groundwater at Waste Area Grouping (WAG) 6. The analytical results for samples collected during Phase 1, Activity 2 of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI) are also presented. In addition, analytical results for Phase 1, activity sampling events for which data were not previously reported are included in this TM. A summary of the groundwater sampling activities of WAG 6, to date, are given in the Introduction. The Methodology section describes the sampling procedures and analytical parameters. Six attachments are included. Attachments 1 and 2 provide analytical results for selected RFI groundwater samples and ORNL sampling event. Attachment 3 provides a summary of the contaminants detected in each well sampled for all sampling events conducted at WAG 6. Bechtel National Inc. (BNI)/IT Corporation Contract Laboratory (IT) RFI analytical methods and detection limits are given in Attachment 4. Attachment 5 provides the Oak Ridge National Laboratory (ORNL)/Analytical Chemistry Division (ACD) analytical methods and detection limits and Resource Conservation and Recovery Act (RCRA) quarterly compliance monitoring (1988--1989). Attachment 6 provides ORNL/ACD groundwater analytical methods and detection limits (for the 1990 RCRA semi-annual compliance monitoring)

  2. Borehole Data Package for Calendar Year 2000-2001 RCRA Wells at Single-Shell Tank Waste Management Area T

    International Nuclear Information System (INIS)

    Horton, Duane G; Hodges, Floyd N

    2001-01-01

    This document compiles information of the drilling and construction, well development, pump installation, and sediment and groundwater sampling applicable to the installation of five new RCRA wells in calendar year 2000 - 2001. Appendix A contains the Well Summary Sheets (as-built diagrams); the Well Construction Summary Reports, and the geologist's logs; Appendix B contains physical properties data; and Appendix C contains the borehole geophysical logs

  3. RCRA [Resource Conservation and Recovery Act] ground-water monitoring projects for Hanford facilities: Annual progress report for 1988

    International Nuclear Information System (INIS)

    Fruland, R.M.; Lundgren, R.E.

    1989-04-01

    This report describes the progress during 1988 of 14 Hanford Site ground-water monitoring projects covering 16 hazardous waste facilities and 1 nonhazardous waste facility (the Solid Waste Landfill). Each of the projects is being conducted according to federal regulations based on the Resource Conservation and Recovery Act (RCRA) of 1976 and the State of Washington Administrative Code. 21 refs., 23 figs., 8 tabs

  4. Should the U.S. proceed to consider licensing deep geological disposal of high-level nuclear waste

    International Nuclear Information System (INIS)

    Curtiss, J.R.

    1993-01-01

    The United States, as well as other countries facing the question of how to handle high-level nuclear waste, has decided that the most appropriate means of disposal is in a deep geologic repository. In recent years, the Radioactive Waste Management Committee of the Nuclear Energy Agency has developed several position papers on the technical achievability of deep geologic disposal, thus demonstrating the serious consideration of deep geologic disposal in the international community. The Committee has not, as yet, formally endorsed disposal in a deep geologic repository as the preferred method of handling high-level nuclear waste. The United States, on the other hand, has studied the various methods of disposing of high-level nuclear waste, and has determined that deep geologic disposal is the method that should be developed. The purpose of this paper is to present a review of the United States' decision on selecting deep geologic disposal as the preferred method of addressing the high-level waste problem. It presents a short history of the steps taken by the U.S. in determining what method to use, discusses the NRC's waste Confidence Decision, and provides information on other issues in the U.S. program such as reconsideration of the final disposal standard and the growing inventory of spent fuel in storage

  5. Cost estimate of Olkiluoto disposal facility for spent nuclear fuel

    International Nuclear Information System (INIS)

    Kukkola, T.; Saanio, T.

    2005-03-01

    The cost estimate covers the underground rock characterisation facility ONKALO, the investment and the operating costs of the above and underground facilities, the decommissioning of the encapsulation plant and the closure costs of the repository. The above ground facility is a once-investment; a re-investment takes place after 37 years operation. The repository is extended stepwise thus also the investment take place in stages. Annual operating costs are calculated with different operating efficiencies. The total investment costs of the disposal facility are estimated to be 503 M euro (Million Euros), the total operating costs are 1,923 M euro and the decommissioning and the closure costs are 116 M euro totaling 2,542 M euro. The investment costs of the above ground facility are 142 M euro, the operating costs are 1,678 M euro. The repository investment costs are 360 M euro and the operating costs are 245 M euro. The decommissioning costs are 7 M euro and the closure costs are 109 M euro. The costs are calculated by using the price level of December 2003. The cost estimate is based on a plan, where the spent fuel is encapsulated and the disposal canisters are disposed into the bedrock at a depth of about 420 meters in one storey. In the encapsulation process, the fuel assemblies are closed into composite canisters, in which the inner part of the canister is made of nodular cast iron and the outer wall of copper having a thickness of 50 mm. The inner canister is closed gas-tight by a bolted steel lid, and the electron beam welding method is used to close the outer copper lid. The encapsulation plant is independent and located above the deep repository spaces. The disposal canisters are transported to the repository by the lift. The disposal tunnels are constructed and closed in stages according the disposal canisters disposal. The operating time of the Loviisa nuclear power plant units is assumed to be 50 years and the operating time of the Olkiluoto nuclear power

  6. 1999 ESH&Q Liability Assessment Report of Envirocare of Utah, Inc. Clive, Utah

    Energy Technology Data Exchange (ETDEWEB)

    Trump, D. E. [INEEL; Vilord, C. E.

    1999-07-01

    This report contains the results of an environment, safety, health, and quality (ESH&Q) assessment of the treatment technologies and treatment-related operations that was conducted of Envirocare of Utah, Inc. (EOU). EOU is a lowlevel radioactive and mixed Resource Conservation and Recovery Act (RCRA)- regulated haz.ardous low-level radioactive waste (mixed low-level waste) treatment/disposal facility located near Clive, Utah. An ESH&Q assessment of the EOU Clive, Utah facility treatment technologies and related treatment operations was conducted in mid-April 1999. The assessment was required as part of the technical evaluation of proposals received by Lockheed Martin Idaho Technologies Company (LMITCO) for modification of a mixed low-level radioactive waste disposal subcontract (No.K79-180572). The EOU Clive, Utah facility is proposed as a potential treatment/disposal facility for mixed low-level radioactive waste regulated under the RCRA and the Atomic Energy Act

  7. Unique issues concerning ''placement'' vs ''movement'' of contaminated soils at ORNL's CERCLA sites

    International Nuclear Information System (INIS)

    Greer, J.K. Jr.; Schrof, C.A.

    1992-01-01

    At Oak Ridge National Laboratory, which is owned and operated by the US Department of Energy (DOE), there are several areas where hazardous wastes and/or radioactive materials have been placed in shallow land burial trenches or ''auger'' holes for disposal. Since Oak Ridge Reservation (ORR) has been placed on the National Priority List (NPL) by the US Environmental Protection Agency (EPA), the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) applies to waste disposal sites at ORNL. Under CERCLA, the RCRA regulations, pertaining to the LDRs, apply to CERCLA activities if the regulations are deemed ''applicable or relevant and appropriate'' (ARARS) by the lead agency or by the EPA. This report discusses the following issue: Under what conditions will contaminated soil and debris generated at a Superfund site be subject to the Resource Conservation and Recovery Act (RCRA) land disposal restrictions (LDRs) treatment standards?

  8. Field application of the Numobag as a portable disposable isolation unit and for treating chemical, radiological or biologically induced wounds.

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Keith A.; Felton, Robert; Vaughan, Courtenay Thomas

    2005-04-01

    Numotech Inc. has developed the Numobag{trademark}, a disposable, lightweight, wound healing device which produces Topical Hyperbaric Oxygen Therapy (THOT). The Numobag{trademark} is cost effective and has been clinically validated to heal large skin lesions rapidly and has proven to arrest wound advancement from several insidious forms of biological attack including dermal anthrax, small pox, necrotizing fasciitis etc. The Numobag{trademark} can treat mass casualties wounded by chemical/radiological burns or damaging biological exposures. The Numobag{trademark} can be a frontline tool as an isolation unit, reducing cross-contamination and infection of medical personnel. The heightened oxygen content kills organisms on the skin and in the wound, avoids expensive hospital trash disposal procedures, and helps the flesh heal. The Numobag{trademark} requires high purity oxygen. Numotech Inc. is teaming with Sandia National Laboratories and Spektr Conversion in Russia to develop a cost effective, portable, low power oxygen generator.

  9. Control of water infiltration into near surface LLW disposal units-progress report on field experiments at a humid region site, Beltsville, Maryland

    International Nuclear Information System (INIS)

    O'Donnell, E.; Ridky, R.W.; Schulz, R.K.

    1994-01-01

    The study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters (75'x45'x10') at Beltsville, MD, and results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated. They are: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover. Remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier, or perhaps even better, a resistive layer barrier/conductive layer barrier system. This latter system would then give long-term effective protection against water entry into waste and without institutional care

  10. Risk management for outsourcing biomedical waste disposal - using the failure mode and effects analysis.

    Science.gov (United States)

    Liao, Ching-Jong; Ho, Chao Chung

    2014-07-01

    Using the failure mode and effects analysis, this study examined biomedical waste companies through risk assessment. Moreover, it evaluated the supervisors of biomedical waste units in hospitals, and factors relating to the outsourcing risk assessment of biomedical waste in hospitals by referring to waste disposal acts. An expert questionnaire survey was conducted on the personnel involved in waste disposal units in hospitals, in order to identify important factors relating to the outsourcing risk of biomedical waste in hospitals. This study calculated the risk priority number (RPN) and selected items with an RPN value higher than 80 for improvement. These items included "availability of freezing devices", "availability of containers for sharp items", "disposal frequency", "disposal volume", "disposal method", "vehicles meeting the regulations", and "declaration of three lists". This study also aimed to identify important selection factors of biomedical waste disposal companies by hospitals in terms of risk. These findings can serve as references for hospitals in the selection of outsourcing companies for biomedical waste disposal. Copyright © 2014 Elsevier Ltd. All rights reserved.

  11. Focused feasibility study of engineered barriers for waste management units in the 200 areas

    International Nuclear Information System (INIS)

    1996-05-01

    The U.S. Department of Energy (DOE) at the Hanford Site in Washington State is organized into numerically designated operational areas consisting of the 100, 200, 300, 400, 600, and 1100 Areas. In November 1989, the U.S. Environmental Protection Agency (EPA) included the 200 Areas (as well as the 100, 300, and 1,100 Areas) of the Hanford Site on the National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Inclusion on the NPL initiates the remedial investigation (RI) and feasibility study (FS) process to characterize the nature and extent of contamination, assess risks to human health and the environment, and select remedial actions. The Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) was developed and signed by representatives from the EPA, Washington State Department of Ecology (Ecology), and DOE in May 1989 to provide a framework to implement and integrate cleanup activities. The scope of the agreement covers CERCLA past-practice, Resource Conservation and Recovery Act of 1976 (RCRA) past-practice, and RCRA treatment, storage, and disposal (TSD) activities on the Hanford Site. The 1991 revision to the Tri-Party Agreement required that an aggregate area approach be implemented in the 200 Areas based on the Hanford Site Past-Practice Strategy (HPPS) and established a milestone (M-27-00) to complete 10 Aggregate Area Management Study (AAMS) Reports in 1992

  12. Classification and disposal of radioactive wastes: History and legal and regulatory requirements

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1990-01-01

    This document discusses the laws and regulations in the United States addressing classification of radioactive wastes and the requirements for disposal of different waste classes. This review emphasizes the relationship between waste classification and the requirements for permanent disposal

  13. Control of water infiltration into near surface LLW disposal units: Task report, A discussion

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

    1988-03-01

    The principal pathway for water entry into LLW disposal units in the humid eastern United States is through their covers. Two types of sub-surface features that may be constructed to enhance run-off (surface or sub-surface run-off) and thus reduce percolation are the resistive layer barrier, and the conductive layer barrier. The resistive layer barrier is the compacted soil or compacted clay layer and depends on compaction of permeable porous material to obtain low flow rates. The conductive layer barrier is a special case of the capillary barrier. Use is made of the capillary barrier phenomenon not only to increase the moisture content above an interface but to divert water away from the waste. During such diversion the water is at all times at negative capillary potential or under tension in the flow layer. A very effective barrier system might be constructed by placing a resistive barrier over a conductive barrier. Such a system must fail if appreciable subsidence takes place. An alternate procedure called bioengineering management utilizes engineered features at the surface (as opposed to the subsurface) to ensure adequate run-off. The engineered features are combined with stressed vegetation, that is, vegetation in an overdraft condition, to control deep percolation. (59 refs., 10 figs.)

  14. Developments in support of low level waste disposal at BNFL's Drigg Site

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1988-01-01

    The continued upgrading of low-level waste pretreatment and disposal practices related to the United Kingdom Drigg disposal site is described, noting the need to take into account operational safety, long term post-closure safety, regulatory and public acceptance factors

  15. Economy may be harmed by lack of LLW disposal

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    A study released by Organizations United for Responsible Low-Level Radioactive Waste Solutions warns that the substantial benefits of using radioactive materials are threatened by the lack of a low-level waste (LLW) disposal facility. The main point of the study is the threat to the American economy posed by insufficient facilities for disposal of the 1.7 billion ft 3 of LLW produced by the use of radioactive materials every year only 34.8 percent of which comes from nuclear power plants. open-quotes Thirty years of experience have provided the technical knowledge to design waste disposal facilities that protect the public and environment. But an impending lack of adequate disposal facilities jeopardizes our continued use of radioactive materials,close quotes according to the study

  16. Deep Borehole Disposal Concept: Development of Universal Canister Concept of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Rigali, Mark J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Applied Systems Analysis and Research; Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Applied Systems Analysis and Research

    2016-08-01

    This report documents key elements of the conceptual design for deep borehole disposal of radioactive waste to support the development of a universal canister concept of operations. A universal canister is a canister that is designed to be able to store, transport, and dispose of radioactive waste without the canister having to be reopened to treat or repackage the waste. This report focuses on the conceptual design for disposal of radioactive waste contained in a universal canister in a deep borehole. The general deep borehole disposal concept consists of drilling a borehole into crystalline basement rock to a depth of about 5 km, emplacing WPs in the lower 2 km of the borehole, and sealing and plugging the upper 3 km. Research and development programs for deep borehole disposal have been ongoing for several years in the United States and the United Kingdom; these studies have shown that deep borehole disposal of radioactive waste could be safe, cost effective, and technically feasible. The design concepts described in this report are workable solutions based on expert judgment, and are intended to guide follow-on design activities. Both preclosure and postclosure safety were considered in the development of the reference design concept. The requirements and assumptions that form the basis for the deep borehole disposal concept include WP performance requirements, radiological protection requirements, surface handling and transport requirements, and emplacement requirements. The key features of the reference disposal concept include borehole drilling and construction concepts, WP designs, and waste handling and emplacement concepts. These features are supported by engineering analyses.

  17. Technical resource documents and technical handbooks for hazardous-wastes management

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.; Bliss, T.M.

    1986-07-01

    The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

  18. Special Analysis: Disposal Plan for Pit 38 at Technical Area 54, Area G

    Energy Technology Data Exchange (ETDEWEB)

    French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [URS Coporation

    2012-06-26

    been made to utilize the remaining disposal capacity within MDA G to the greatest extent possible. One approach for doing this has been to dispose of low-activity waste from cleanup operations at LANL in the headspace of selected disposal pits. Waste acceptance criteria (WAC) for the material placed in the headspace of pits 15, 37, and 38 have been developed (LANL, 2010) and the impacts of placing waste in the headspace of these units has been evaluated (LANL, 2012a). The efforts to maximize disposal efficiency have taken on renewed importance because of the disposal demands placed on MDA G by the large volumes of waste that are being generated at LANL by cleanup efforts. For example, large quantities of waste were recently generated by the retrieval of waste formerly disposed of at TA-21, MDA B. A portion of this material has been disposed of in the headspace of pit 38 in compliance with the WAC developed for that disposal strategy; a large amount of waste has also been sent to off-site facilities for disposal. Nevertheless, large quantities of MDA B waste remain that require disposal. An extension of pit 38 was proposed to provide the disposal capacity that will be needed to dispose of institutional waste and MDA B waste through 2013. A special analysis was prepared to evaluate the impacts of the pit extension (LANL, 2012b). The analysis concluded that the disposal unit could be extended with modest increases in the exposures projected for the Area G performance assessment and composite analysis, as long as limits were placed on the radionuclide concentrations in the waste that is placed in the headspace of the pit. Based, in part, on the results of the special analysis, the extension of pit 38 was approved and excavation of the additional disposal capacity was started in May 2012. The special analysis presented here uses performance modeling to identify a disposal plan for the placement of waste in pit 38. The modeling uses a refined design of the disposal unit and

  19. Special Analysis: Disposal Plan for Pit 38 at Technical Area 54, Area G

    International Nuclear Information System (INIS)

    French, Sean B.; Shuman, Rob

    2012-01-01

    have been made to utilize the remaining disposal capacity within MDA G to the greatest extent possible. One approach for doing this has been to dispose of low-activity waste from cleanup operations at LANL in the headspace of selected disposal pits. Waste acceptance criteria (WAC) for the material placed in the headspace of pits 15, 37, and 38 have been developed (LANL, 2010) and the impacts of placing waste in the headspace of these units has been evaluated (LANL, 2012a). The efforts to maximize disposal efficiency have taken on renewed importance because of the disposal demands placed on MDA G by the large volumes of waste that are being generated at LANL by cleanup efforts. For example, large quantities of waste were recently generated by the retrieval of waste formerly disposed of at TA-21, MDA B. A portion of this material has been disposed of in the headspace of pit 38 in compliance with the WAC developed for that disposal strategy; a large amount of waste has also been sent to off-site facilities for disposal. Nevertheless, large quantities of MDA B waste remain that require disposal. An extension of pit 38 was proposed to provide the disposal capacity that will be needed to dispose of institutional waste and MDA B waste through 2013. A special analysis was prepared to evaluate the impacts of the pit extension (LANL, 2012b). The analysis concluded that the disposal unit could be extended with modest increases in the exposures projected for the Area G performance assessment and composite analysis, as long as limits were placed on the radionuclide concentrations in the waste that is placed in the headspace of the pit. Based, in part, on the results of the special analysis, the extension of pit 38 was approved and excavation of the additional disposal capacity was started in May 2012. The special analysis presented here uses performance modeling to identify a disposal plan for the placement of waste in pit 38. The modeling uses a refined design of the disposal unit

  20. Modeling of release of radionuclides from an engineered disposal facility for shallow-land disposal of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Matsuzuru, H.; Suzuki, A.

    1989-01-01

    The computer code, ENBAR-1, for the simulation of radionuclide releases from an engineered disposal facility has been developed to evaluate the source term for subsequent migration of radionuclides in and through a natural barrier. The system considered here is that a waste package (waste form and container) is placed, together with backfill materials, into a concrete pit as a disposal unit for shallow-land disposal of low-level radioactive wastes. The code developed includes the following modules: water penetration into a concrete pit, corrosion of a drum as a container, leaching of radionuclides from a waste form, migration of radionuclides in backfill materials, release of radionuclides from the pit. The code has the advantage of its simplicity of operation and presentation while still allowing comprehensive evaluation of each element of an engineered disposal facility to be treated. The performance and source term of the facility might be readily estimated with a few key parameters to define the problem

  1. Borehole disposal of spent radiation sources: 1. Principles

    International Nuclear Information System (INIS)

    Blerk, J.J. van; Kozak, M.W.

    2000-01-01

    Large numbers of spent radiation sources from the medical and other technical professions exist in many countries, even countries that do not possess facilities related to the nuclear fuel cycle, that have to be disposed. This is particularly the case in Africa, South America and some members of the Russian Federation. Since these sources need to be handled separately from the other types of radioactive waste, mainly because of their activity to volume ratio, countries (even those with access to operational repositories) find it difficult to manage and dispose this waste. This has led to the use of boreholes as disposal units for these spent sources by some members of the Russian Federation and in South Africa. However, the relatively shallow boreholes used by these countries are not suitable for the disposal of isotopes with long half-lifes, such as 226 Ra and 241 Am. With this in mind the Atomic Energy Corporation of South Africa initiated the development of the BOSS disposal concept - an acronym for Borehole disposal Of Spent Sources - as part of an International Atomic Energy Agency (IAEA) AFRA I-14 Technical Corporation (TC) project. In this paper, the principles of this disposal concept, which is still under development, will be discussed. (author)

  2. The siting dilemma: Low-level radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    English, M.R.

    1991-01-01

    The 1980 Low-Level Radioactive Waste Policy Act ushered in a new era in low-level waste disposal; one with vastly increased state responsibilities. By a 1985 amendment, states were given until January 1993 to fulfill their mandate. In this dissertation, their progress is reviewed. The focus then turns to one particularly intractable problem: that of finding technically and socially acceptable sites for new disposal facilities. Many lament the difficulty of siting facilities that are intended to benefit the public at large but are often locally unwanted. Many label local opposition as purely self-interested; as simply a function of the NIMBY (Not In My Backyard) syndrome. Here, it is argued that epithets such as NIMBY are unhelpful. Instead, to lay the groundwork for widely acceptable solutions to siting conflicts, deeper understanding is needed of differing values on issues concerning authority, trust, risk, and justice. This dissertation provides a theoretical and practical analysis of those issues as they pertain to siting low-level waste disposal facilities and, by extension, other locally unwanted facilities

  3. Air modelling as an alternative to sampling for low-level radioactive airborne releases

    International Nuclear Information System (INIS)

    Morgenstern, M.Y.; Hueske, K.

    1995-01-01

    This paper describes our efforts to assess the effect of airborne releases at one DOE laboratory using air modelling based on historical data. Among the facilities affected by these developments is Los Alamos National Laboratory (LANL) in New Mexico. RCRA, as amended by the Hazardous and Solid Waste Amendments (HSWA) in 1984, requires all facilities which involve the treatment, storage, and disposal of hazardous waste obtain a RCRA/HSWA waste facility permit. LANL complied with CEARP by initiating a process of identifying potential release sites associated with LANL operations prior to filing a RCRA/HSWA permit application. In the process of preparing the RCRA/HSWA waste facility permit application to the U.S. Environmental Protection Agency (EPA), a total of 603 Solid Waste Management Units (SWMUs) were identified as part of the requirements of the HSWA Module VIH permit requirements. The HSWA Module VIII permit requires LANL to determine whether there have been any releases of hazardous waste or hazardous constituents from SWMUs at the facility dating from the 1940's by performing a RCRA Facility Investigation to address known or suspected releases from specified SWMUs to affected media (i.e. soil, groundwater, surface water, and air). Among the most troublesome of the potential releases sites are those associated with airborne radioactive releases. In order to assess health risks associated with radioactive contaminants in a manner consistent with exposure standards currently in place, the DOE and LANL have established Screening Action Levels (SALs) for radioactive soil contamination. The SALs for each radionuclide in soil are derived from calculations based on a residential scenario in which individuals are exposed to contaminated soil via inhalation and ingestion as well as external exposure to gamma emitters in the soil. The applicable SALs are shown

  4. Disposal of fissionable material from dismantled nuclear weapons

    International Nuclear Information System (INIS)

    Taylor, J.J.

    1991-01-01

    The reduction in tensions between the United States and the Soviet Union has improved the prospects for nuclear disarmament, making it more likely that significant numbers of nuclear warheads will be dismantled by the United States and USSR in the foreseeable future. Thus, the question becomes more urgent as to the disposition of the weapons materials, highly enriched uranium and plutonium. It is timely, therefore, to develop specific plans for such disposal. The overall process for disposal of weapons materials by the burnup option involves the following steps: (1) removing the weapons material from the warheads, (2) converting the material to a fuel form suitable for power reactors, (3) burning it up as a power reactor fuel, and (4) removing the spent fuel and placing it in a permanent repository. This paper examines these four steps with the purpose of answering the following questions. What facilities would be appropriate for the disposal process? Do they need to be dedicated facilities, or could industrial facilities be used? What is the present projection of the economics of the burnup process, both the capital investment and the operating costs? How does one assure that fissionable materials will not be diverted to military use during the disposal process? Is the spent fuel remaining from the burnup process proliferation resistant? Would the disposal of spent fuel add an additional burden to the spent fuel permanent repository? The suggested answers are those of the author and do not represent a position by the Electric Power Research Institute

  5. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  6. Benefits Assessment of Two California Hazardous Waste Disposal Facilities (1983)

    Science.gov (United States)

    The purpose of this study was to assess the benefits of RCRA regulations, comparing the results before and after new regulations at two existing hazardous waste sites previously regulated under California state law

  7. Waste disposal in the deep ocean: An overview

    International Nuclear Information System (INIS)

    O'Connor, T.P.; Kester, D.R.; Burt, W.V.; Capuzzo, J.M.; Park, P.K.; Duedall, I.W.

    1985-01-01

    Incineration at sea, industrial and sewage waste disposal in the surface mixing zone, and disposal of low-level nuclear wastes, obsolete munitions, and nerve gas onto the seafloor have been the main uses of the deep sea for waste management. In 1981 the wastes disposed of in the deep sea consisted of 48 X 10/sup 4/ t of liquid industrial wastes and 2 X 10/sup 4/ t of sewage sludge by the United States; 1.5 X 10/sup 4/ t (solids) of sewage sludge by the Federal Republic of German; 5300 t of liquid industrial wastes by Denmark; 99 t of solid industrial wastes by the United Kingdom; and 9400 t of low-level radioactive wastes by several European countries. Also in 1981 at-sea incineration of slightly more than 10/sup 5/ t of organic wastes from Belgium, France, the Federal Republic of Germany, the Netherlands, Norway, Sweden, and the United Kingdom was carried out in the North Sea. Unique oceanographic features of the deep sea include its large dilution capacity; the long residence time of deep-sea water (on the order of 10/sup 2/ y); low biological productivity in the surface water of the open ocean (≅50 g m/sup -2/ of carbon per year); the existence of an oxygen minimum zone at several hundred meters deep in the mid-latitudes; and the abyssal-clay regions showing sedimentary records of tens of millions of years of slow, uninterrupted deposition of fine-grained clay. Any deep-sea waste disposal strategy must take into account oceanic processes and current scientific knowledge in order to attain a safe solution that will last for centuries

  8. Status of US program for disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    Smith, R.I.

    1991-04-01

    In this paper, a brief history of the United States' program for the disposal of spent nuclear fuel (SNF) and the legislative acts that have guided the program are discussed. The current plans and schedules for beginning acceptance of SNF from the nuclear utilities for disposal are described, and some of the development activities supporting the program are discussed. And finally, the viability of the SNF disposal fee presently paid into the Nuclear Waste Fund by the owners/generators of commercial SNF and high-level waste (HLW) is examined. 12 refs., 9 figs

  9. Fluorine disposal processes for nuclear applications

    International Nuclear Information System (INIS)

    Netzer, W.D.

    1977-01-01

    A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable

  10. Fluorine disposal processes for nuclear applications

    Energy Technology Data Exchange (ETDEWEB)

    Netzer, W.D.

    1977-04-08

    A study was performed to determine the best method for disposing of waste fluorine in the effluent from a uranium oxide conversion facility. After reviewing the fluorine disposal literature and upon considering the nuclear safety constraints, it was determined that the two most promising processes were the fluidized alumina bed and the caustic scrubber. To obtain more design data for the latter process, a 3-stage, 5-in. I.D. spray tower was constructed and operated. This unit used a 10% potassium hydroxide solution at flows of 1.5 to 3 gpm and achieved a 90% fluorine efficiency at fluorine flowrates as high as 4 scfm. However, two toxic by-products, oxygen difluoride and nitroxy fluoride, were detected in the effluent gases. After considering the relative merits of both disposal processes, it is concluded that the fluidized bed is superior, especially if the contaminated waste material were salable.

  11. Source Release Modeling for the Idaho National Engineering and Environmental Laboratory's Subsurface Disposal Area

    International Nuclear Information System (INIS)

    Becker, B.H.

    2002-01-01

    A source release model was developed to determine the release of contaminants into the shallow subsurface, as part of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) evaluation at the Idaho National Engineering and Environmental Laboratory's (INEEL) Subsurface Disposal Area (SDA). The output of the source release model is used as input to the subsurface transport and biotic uptake models. The model allowed separating the waste into areas that match the actual disposal units. This allows quantitative evaluation of the relative contribution to the total risk and allows evaluation of selective remediation of the disposal units within the SDA

  12. INEL RCRA [Resource Conservation and Recovery Act] permit for incineration of hazardous waste: Status report

    International Nuclear Information System (INIS)

    McFee, J.N.; Dalton, J.D.; Bohrer, H.A.

    1987-01-01

    The Waste Experimental Reduction Facility (WERF) was constructed to reduce the volume of low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). To address the problem of radioactively contaminated ignitable hazardous waste resulting from INEL activities, a development program was carried out to evaluate WERF's ability to meet the regulated criteria for incinerating liquid and solid ignitable waste. Concurrently, INEL submitted its hazardous waste Part B application under the Resource Conservation and Recovery Act (RCRA). As required, and as a major step in the permitting process, the WERF incinerator portion of the permit application included a proposed trial burn, which is a demonstration test of the incinerator's ability to destroy hazardous materials. The trial burn plan was designed to demonstrate the system performance for liquid and solid ignitable wastes at three operating conditions, using a prepared mix of materials representative of waste to be processed. EPA Region X reviewed and commented on the plan prior to the trial burn. Results of the liquid feed trial burn showed a greater than 97% probability of meeting the RCRA-dictated DRE value for chlorinated solvents and a greater than 99% probability for nonchlorinated solvents. Nonchlorinated solid waste results were calculated at a 93% probability of meeting the required DRE, with a 75% probability for chlorinated solid wastes. In addition, the incinerator DRE continued to improve long after the assumed pre-test equilibrium period had ended. The trial burn demonstrates that the WERF incinerator can safely and adequately destroy ignitable hazardous and mixed waste and provides a significant enhancement of the INEL's waste management system

  13. Control of water infiltration into near surface LLW disposal units: Progress report on field experiments at a humid region site, Beltsville, Maryland

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.

    1996-08-01

    This study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (70 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

  14. The cost of engineered disposal facilities

    International Nuclear Information System (INIS)

    Mallory, C.W.; Razor, J.E.; Mills, D.

    1987-01-01

    An improved disposal trench was designed, constructed and placed into operation at the Maxey Flats Disposal Site during the period April 1985 through July 1986. With the improved trench design, the waste packages are placed in clusters and the surrounding space is filled with gravel and grouted with a sand/cement mixture to form walls and cells that surround the waste package. The walls provide structural support for a poly-ethylene reinforced soil beam which in turn supports a multi-layer protective cap. About 2,700 drums of waste (20,250 CF) were placed into the trench. The total cost of the improved trench was $193,500 and the unit cost was $9.56 per cubic foot not including the placement of the waste. The engineered features of the trench (i.e., sidewall infiltration barrier, grout backfill and the soil beam) cost $82,600 for a unit cost of $4.08 per cubic foot of waste. This is compared to the cost of concrete cannisters used for radioactive waste disposal. On a production basis the cannisters are estimated to cost about $1,260. Depending upon the type waste, the cost of the cannisters will range from $2 to $12 per cubic foot of waste. The slightly higher cost of the concrete cannisters is offset by certain performance advantages

  15. 39 CFR 262.6 - Retention and disposal.

    Science.gov (United States)

    2010-07-01

    ... Service UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION RECORDS AND INFORMATION MANAGEMENT DEFINITIONS § 262.6 Retention and disposal. (a) Records control schedule. A directive describing records... the Smithsonian Institution, local museums or historical societies. (3) Sale as waste material. (4...

  16. Ecological effects of contaminants in McCoy Branch, 1991--1993

    Energy Technology Data Exchange (ETDEWEB)

    Ryon, M.G. [ed.

    1996-09-01

    The 1984 Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act (RCRA) required assessment of all current and former solid waste management units. Following guidelines under RCRA and the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), a remedial investigation (RI) was required of the Y-12 Plant for their filled coal ash pond (FCAP) and associated areas on McCoy Branch. The RI process was initiated and assessments were presented. Because the disposal of coal ash in the ash pond, McCoy Branch, and Rogers Quarry was not consistent with the Tennessee Water Quality Act, several remediation steps were implemented between 1986 and 1994 for McCoy Branch to address disposal problems. The required ecological risk assessments of McCoy Branch watershed included provisions for biological monitoring of the watershed. The objectives of the biological monitoring were to (1) document changes in biological quality of McCoy Branch after completion of a pipeline bypassing upper McCoy Branch and further, after termination of all discharges to Rogers Quarry, (2) provide guidance on the need for additional remediation, and (3) evaluate the effectiveness of implemented remedial actions. The data from the biological monitoring program may also determine whether the goals of protection of human health and the environment of McCoy Branch are being accomplished.

  17. New DEA rules expand options for controlled substance disposal.

    Science.gov (United States)

    Peterson, David M

    2015-03-01

    Prescription drug abuse and overdose are rapidly growing problems in the United States. The United States federal Disposal of Controlled Substances Rule became effective 9 October 2014, implementing the Secure and Responsible Drug Disposal Act of 2010 (Disposal Act). These regulations target escalating prescription drug misuse by reducing accumulation of unused controlled substances that may be abused, diverted or accidentally ingested. Clinical areas that can now participate in collecting unused controlled substances include retail pharmacies, hospitals or clinics with an onsite pharmacy, and narcotic treatment programs. Collection methods include placing a controlled substance collection receptacle or instituting a mail-back program. Because prompt onsite destruction of collected items is required of mail-back programs, collection receptacles are more likely to be used in clinical areas. Retail pharmacies and hospitals or clinics with an onsite pharmacy may also place and maintain collection receptacles at long-term care facilities. The Act and Rule are intended to increase controlled substance disposal methods and expand local involvement in collection of unused controlled substances. Potential barriers to participating in controlled substance collection include acquisition of suitable collection receptacles and liners, lack of available space meeting the necessary criteria, lack of employee time for verification and inventory requirements, and program costs.

  18. The impact of new technology on compact disposal costs

    International Nuclear Information System (INIS)

    Arrowsmith, H.W.; Zidow, T.M.

    1989-01-01

    The cost of disposal of low-level waste (LLW) has increased dramatically since the 1960s. In the '60s waste was put into the ground for a fee of less than $1/ft 3 in truck-size quantities. Fees for the same burial services today begin in the $30/ft 3 range and increase rapidly from that level. Although the user fees associated with compacts will clearly exceed $100/ft 3 , improved operating techniques by the generators will reduce the amount of waste produced. Current estimates suggest this reduction will drive the per-cubic-foot cost of disposal over the $200 mark. Technology is the only solution to this predicament. While costs already incurred will contribute to the fixed portion of the base user fees, the means to minimize the variable portion of the fees in now at hand. This variable portion results from on-site processing costs, waste form stability enhancements, and ongoing disposal unit construction. Technology exists to minimize volume through ultra compaction and selective incineration, greatly reducing the ongoing disposal unit construction requirements. Vitrification of incinerator residue provides waste form stability far in excess of that provided by concrete overpacks. As overpacks represent the second largest material cost at an engineered barrier facility, the potential for cost savings is substantial

  19. Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

    International Nuclear Information System (INIS)

    Di Sanza, E.F.; Carilli, J.T.

    2006-01-01

    Waste Acceptance Criteria. The disposal operations previously mentioned take place at the NTS in two disposal facilities. The isolation protection and overall performance of the two LLW disposal facilities at the NTS transcend those of any federal radioactive waste disposal site in the United States. The first of the two disposal sites is the Area 5 Radioactive Waste Management Site (RWMS) which is situated on alluvial fan deposits in the Frenchman Flat basin, approximately 770 feet (235 meters) above the water table. The Area 5 RWMS utilizes a combination of engineered shallow land disposal cells and deep augured shafts for the disposal of a variety of waste streams. Fifteen miles (24 kilometers) north of the Area 5 RWMS is the Area 3 RWMS located approximately 1,600 feet (488 meters) above the water table in Yucca Flat. Disposal activities at the Area 3 RWMS center around the placement of bulk LLW in subsidence craters formed from underground testing of nuclear weapons. Native alluvium soil is used to cover waste placed in the disposal cells at both facilities. In addition, information on the technical attributes, facility performance, updates on waste disposal volumes and capabilities, and current and future disposal site requirements will also be described. (authors)

  20. Long-term surveillance plan for the Lowman, Idaho, disposal site

    International Nuclear Information System (INIS)

    1993-09-01

    The long-term surveillance plan (LTSP) for the Lowman, Idaho, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lowman disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This preliminary final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. The LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and describes, in detail, how the long-term care of the disposal site will be carried out through the UMTRA Project long-term surveillance program. The Lowman, Idaho, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program, (DOE, 1992)

  1. Feasibility study of X-ray K-edge analysis of RCRA heavy metal contamination of sludge packaged in drums

    International Nuclear Information System (INIS)

    Jensen, T.

    1999-01-01

    A study has been completed to assess the capabilities of X-ray K-edge analysis in the measurement of RCRA metal contamination of sludge packaged in drums. Results were obtained for mercury and lead contamination. It was not possible to measure cadmium contamination using this technique. No false positive signals were observed. In cases where uniformity of the sludge can be assumed, this analysis can provide a quick, accurate measurement of heavy-metal contamination

  2. Conclusions on the two technical panels on HLW-disposal and waste treatment processes respectively

    International Nuclear Information System (INIS)

    Dinkespiller, J.A.; Dejonghe, P.; Feates, F.

    1986-01-01

    The paper reports the concluding panel session at the European Community Conference on radioactive waste management and disposal, Luxembourg 1985. The panel considered the conclusions of two preceeding technical panels on high level waste (HLW) disposal and waste treatment processes. Geological disposal of HLW, waste management, safety assessment of waste disposal, public opinion, public acceptance of the manageability of radioactive wastes, international cooperation, and waste management in the United States, are all discussed. (U.K.)

  3. 1993 report on Hanford Site land disposal restrictions for mixed wastes

    International Nuclear Information System (INIS)

    Black, D.

    1993-04-01

    Since the early 1940s, the contractors at the Hanford Site have been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste (RMW). This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 2 (RCRA) and Atomic Energy Act 3 . This report covers mixed waste only. Hazardous waste that is not contaminated with radionuclides is not addressed in this report. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order 1 (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for RMW. This report is the third update of the plan first issued in 1990. The Tri-Party Agreement requires, and the baseline plan and annual update reports provide, the information that follows: Waste characterization information; storage data; treatment information; waste reduction information; schedule; and progress

  4. Radioactive wastes and their disposal

    International Nuclear Information System (INIS)

    Neumann, L.

    1984-01-01

    The classification of radioactive wastes is given and the achievements evaluated in the disposal of radioactive wastes from nuclear power plants. An experimental pilot unit was installed at the Jaslovske Bohunice nuclear power plant for the bituminization of liquid radioactive wastes. UJV has developed a mobile automated high-output unit for cementation. In 1985 the unit will be tested at the Jaslovske Bohunice and the Dukovany nuclear power plants. A prototype press for processing solid wastes was manufactured which is in operation at the Jaslovske Bohunice plant. A solidification process for atypical wastes from long-term storage of spent fuel elements has been developed to be used for the period of nuclear power plant decommissioning. (E.S.)

  5. Corrective Action Decision Document/Closure Report for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada (Revision 0) with ROTC 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Krauss, Mark J

    2007-03-01

    The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 137 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from February 28 through August 17, 2006, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent. • Provide sufficient information and data to complete appropriate corrective actions. ROTC-1: Downgrade FFACO UR at CAU 137, CAS 07-23-02, Radioactive Waste Disposal Site to an Administrative UR. ROTC-2: Downgrade FFACO UR at CAU 137, CAS 01-08-01, Waste Disposal Site to an Administrative UR.

  6. Unreviewed Disposal Question: A Discipline Process to Manage Change in LLW Disposal

    International Nuclear Information System (INIS)

    Goldston, W.T.

    2000-01-01

    Unreviewed Safety Question process examines changes in nuclear facility operations. The process, which ensures that proposed or discovered changes receive the appropriate level of review, is now being used whenever changes such as new waste streams or changes in the design of a waste disposal unit are proposed at SRS. The process involves going through a series of questions to ensure that the change is within the existing performance envelope. Two series of questions are used. The first is a simple screening process. If the change is obviously within the performance envelope, it will be screened from further evaluation. If it cannot be screened, technical personnel involved in the performance assessment, composite analysis, and DAS processes, perform a more detailed evaluation using the second set of questions. If the evaluation shows that the change is within the performance envelope, it can be approved within the contractor's organization. If the evaluation does not clearly conclude t hat the change is within the performance envelope, then a Special Analysis or other more extensive study is triggered. This is a disciplined way to be sure that one knows which changes are significant and which are not, so that the proper attention can be given to the changes that are significant

  7. Construction of mixed waste storage RCRA facilities, Buildings 7668 and 7669: Environmental assessment

    International Nuclear Information System (INIS)

    1994-04-01

    The Department of Energy has prepared an environmental assessment, DOE/EA-0820, to assess the potential environmental impacts of constructing and operating two mixed waste Resource Conservation and Recovery Act (RCRA) storage facilities. The new facilities would be located inside and immediately west of the security-fenced area of the Oak Ridge National Laboratory Hazardous Waste Management Area in Melton Valley, Tennessee. Based on the analyses in the environmental assessment, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department is issuing this finding of no significant impact

  8. Cost calculation and financial measures for high-level waste disposal business

    International Nuclear Information System (INIS)

    Sekiguchi, Hiromasa.

    1987-01-01

    A study is made on the costs for disposal of high-level wastes, centering on financial problems involving cost calculation for disposal business and methods and systems for funding the business. The first half of the report is focused on calculation of costs for disposal business. Basic equations are shown to calculate the total costs required for a disposal plant and the costs for disposal of one unit of high-level wastes. A model is proposed to calculate the charges to be paid by electric power companies to the plant for disposal of their wastes. Another equation is derived to calculate the disposal charge per kWh of power generation in a power plant. The second half of the report is focused on financial measures concerning expenses for disposal. A financial basis should be established for the implementation of high-level waste disposal. It is insisted that a reasonable method for estimating the disposal costs should be set up and it should be decided who will pay the expenses. Discussions are made on some methods and systems for funding the disposal business. An additional charge should be included in the electricity bill to be paid by electric power users, or it should be included in tax. (Nogami, K.)

  9. Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

    International Nuclear Information System (INIS)

    Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

    1993-01-01

    The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

  10. Safety assessments for centralized waste treatment and disposal facility in Puspokszilagy Hungary

    International Nuclear Information System (INIS)

    Berci, K.; Hauszmann, Z.; Ormai, P.

    2002-01-01

    The centralized waste treatment and disposal facility Puspokszilagy is a shallow land, near surface engineered type disposal unit. The site, together with its geographic, geological and hydrogeological characteristics, is described. Data are given on the radioactive inventory. The operational safety assessment and the post-closure safety assessment is outlined. (author)

  11. Spent fuel disposal problem in Bulgaria

    Energy Technology Data Exchange (ETDEWEB)

    Milanov, M; Stefanova, I [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika

    1994-12-31

    The internationally agreed basic safety principles and criteria for spent fuel (SF) and high level waste (HLW) disposal are outlined. In the framework of these principles the specific problems of Bulgaria described in the `National Concept for Radioactive Waste Management and Disposal in Republic of Bulgaria` are discussed. The possible alternatives for spent fuel management are: (1) sending the spent fuel for disposal in other country; (2) once-through cycle and (3) closed fuel cycle. A mixed solution of the problem is implemented in Bulgaria. According to the agreement between Bulgaria and former Soviet Union a part of the spent fuel has been returned to Russia. The once-through and closed-fuel cycle are also considered. The projected cumulated amount of spent fuel is estimated for two cases: (1) the six units of Kozloduy NPP are in operation till the end of their lifetime (3300 tHM) and (2) low estimate (2700 tHM) - only units 5 and 6 are operated till the end of their lifetime. The reprocessing of the total amount of 3300 tHM will lead to the production of about 370 m{sup 3} vitrified high level wastes. Together with the HLW about 1850 m{sup 3} cladding hulls and 7800 m{sup 3} intermediate-level wastes will be generated, which should be disposed off in deep geological repository. The total production of radioactive waste in once-through cycle is 181 000 m{sup 3}, and in closed cycle - 190 000 m{sup 3}. Geological investigations are performed resulting in categorization of the territory of the country based on geological, geotechnical and hydrogeological conditions. This will facilitate the choice of the most suitable location for deep geological repository. 7 figs., 11 refs.

  12. Calandar year 1996 annual groundwater monitoring report for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This annual monitoring report contains groundwater and surface water monitoring data obtained in the Bear Creek Hydrogeologic Regime (Bear Creek Regime) during calendar year (CY) 1996. The Bear Creek Regime encompasses a portion of Bear Creek Valley (BCV) west of the U.S. Department of Energy (DOE) Oak Ridge Y-12 Plant (unless otherwise noted, directions are in reference to the Y-12 Plant administrative grid) that contains several sites used for management of hazardous and nonhazardous wastes associated with plant operations. Groundwater and surface water quality monitoring in the Bear Creek Regime is performed under the auspices of the Y-12 Plant Groundwater Protection Program (GWPP). This report contains the information and monitoring data required under the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit for the Bear Creek Hydrogeologic Regime (post-closure permit), as modified and issued by the Tennessee Department of Environment and Conservation (TDEC) in September 1995 (permit no. TNHW-087). In addition to the signed certification statement and the RCRA facility information summarized below, permit condition II.C.6 requires the annual monitoring report to address groundwater monitoring activities at the three RCRA Hazardous Waste Disposal Units (HWDUs) in the Bear Creek Regime that are in post-closure corrective action status (the S-3 Site, the Oil Landfarm, and the Bear Creek Burial Grounds/Walk-In Pits).

  13. Risk management for outsourcing biomedical waste disposal – Using the failure mode and effects analysis

    International Nuclear Information System (INIS)

    Liao, Ching-Jong; Ho, Chao Chung

    2014-01-01

    Highlights: • This study is based on a real case in hospital in Taiwan. • We use Failure Mode and Effects Analysis (FMEA) as the evaluation method. • We successfully identify the evaluation factors of bio-medical waste disposal risk. - Abstract: Using the failure mode and effects analysis, this study examined biomedical waste companies through risk assessment. Moreover, it evaluated the supervisors of biomedical waste units in hospitals, and factors relating to the outsourcing risk assessment of biomedical waste in hospitals by referring to waste disposal acts. An expert questionnaire survey was conducted on the personnel involved in waste disposal units in hospitals, in order to identify important factors relating to the outsourcing risk of biomedical waste in hospitals. This study calculated the risk priority number (RPN) and selected items with an RPN value higher than 80 for improvement. These items included “availability of freezing devices”, “availability of containers for sharp items”, “disposal frequency”, “disposal volume”, “disposal method”, “vehicles meeting the regulations”, and “declaration of three lists”. This study also aimed to identify important selection factors of biomedical waste disposal companies by hospitals in terms of risk. These findings can serve as references for hospitals in the selection of outsourcing companies for biomedical waste disposal

  14. Risk management for outsourcing biomedical waste disposal – Using the failure mode and effects analysis

    Energy Technology Data Exchange (ETDEWEB)

    Liao, Ching-Jong; Ho, Chao Chung, E-mail: ho919@pchome.com.tw

    2014-07-15

    Highlights: • This study is based on a real case in hospital in Taiwan. • We use Failure Mode and Effects Analysis (FMEA) as the evaluation method. • We successfully identify the evaluation factors of bio-medical waste disposal risk. - Abstract: Using the failure mode and effects analysis, this study examined biomedical waste companies through risk assessment. Moreover, it evaluated the supervisors of biomedical waste units in hospitals, and factors relating to the outsourcing risk assessment of biomedical waste in hospitals by referring to waste disposal acts. An expert questionnaire survey was conducted on the personnel involved in waste disposal units in hospitals, in order to identify important factors relating to the outsourcing risk of biomedical waste in hospitals. This study calculated the risk priority number (RPN) and selected items with an RPN value higher than 80 for improvement. These items included “availability of freezing devices”, “availability of containers for sharp items”, “disposal frequency”, “disposal volume”, “disposal method”, “vehicles meeting the regulations”, and “declaration of three lists”. This study also aimed to identify important selection factors of biomedical waste disposal companies by hospitals in terms of risk. These findings can serve as references for hospitals in the selection of outsourcing companies for biomedical waste disposal.

  15. Whither nuclear waste disposal?

    Energy Technology Data Exchange (ETDEWEB)

    Cotton, T A [JK Research Associates, Silver Spring, MD (United States)

    1990-07-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site.

  16. Whither nuclear waste disposal?

    International Nuclear Information System (INIS)

    Cotton, T.A.

    1990-01-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

  17. 36 CFR 6.4 - Solid waste disposal sites not in operation on September 1, 1984.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal sites... PARK SERVICE, DEPARTMENT OF THE INTERIOR SOLID WASTE DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM § 6.4 Solid waste disposal sites not in operation on September 1, 1984. (a) No person may operate...

  18. Analysis of the impacts of the 1984 Resource Conservation and Recovery Act amendments on the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Falconer, K.L.; Davis, K.D.; Johnson, R.D.; Nishimoto, D.D.; Wallace, M.T.

    1986-02-01

    The November 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) have had, and will continue to have, a significant impact on the management of hazardous and radioactive mixed waste at the Idaho National Engineering Laboratory (INEL). These Amendments include new requirements specific to federal facilities such as the INEL. In this paper, areas of direct impact and associated INEL plans for complying with the 1984 RCRA Amendments will be described. The specific areas to be covered are the following: (1) changes in RCRA Part B permitting, including requirements for addressing past hazardous waste TSD sites; (2) the effects of increased restrictions on land disposal; (3) new requirements for undergrond tanks; (4) requirements for federal facilities; and (5) mandatory minimization of waste generation

  19. Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

    Energy Technology Data Exchange (ETDEWEB)

    Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

    2012-05-07

    This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

  20. Institutional innovation to generate the public acceptance of radioactive waste disposal

    International Nuclear Information System (INIS)

    Kemp, R.

    1991-01-01

    Contrasting experiences of public acceptance of radioactive waste disposal are compared for the United Kingdom, France, Sweden and Canada. The disparity between scientifically assessed and publicly perceived levels of risk is noted. The author argues that the form of decision-making process is more important to public acceptance of radioactive waste disposal than the technology of disposal. Public risk perception can be altered by procedures employed in planning, negotiation and consultation. Precisely what constitutes acceptable risk does vary from country to country, and differences in institutional responses and innovation are particularly highlighted. (UK)

  1. Final radioactive waste disposal: A European comparison of organization and costs

    International Nuclear Information System (INIS)

    Drasdo, P.

    2000-01-01

    The investigation is aimed to the comparison of organization structures of operators (plants) and governmental institutions concerned with the final disposal of radioactive waste. The study is covering Germany, France, United Kingdom and Sweden. The capital amount of total final disposal costs are the highest in Germany, the lowest in Sweden. This is also true for the final disposal costs that have to be financed by electricity production from nuclear power plants. The reasons for the differences with respect to economic efficiencies, political decisions and technical concepts are discussed

  2. Sulfur polymer cement encapsulation of RCRA toxic metals and metal oxides

    International Nuclear Information System (INIS)

    Calhoun, C.L. Jr.; Nulf, L.E.; Gorin, A.H.

    1995-06-01

    A study was conducted to determine the suitability of Sulfur Polymer Cement (SPC) encapsulation technology for the stabilization of RCRA toxic metal and metal oxide wastes. In a series of bench-scale experiments, the effects of sodium sulfide additions to the waste mixture, residence time, and temperature profile were evaluated. In addition, an effort was made to ascertain the degree to which SPC affords chemical stabilization as opposed to physical encapsulation. Experimental results have demonstrated that at the 25 wt % loading level, SPC can effectively immobilize Cr, Cr 2 O 3 , Hg, Pb, and Se to levels below regulatory limits. SPC encapsulation also has been shown to significantly reduce the leachability of other toxic compounds including PbO, PbO 2 , As 2 O 3 , BaO, and CdO. In addition, data has confirmed sulfide conversion of Hg, Pb, PbO, PbO 2 , and BaO as the product of their reaction with SPC

  3. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    International Nuclear Information System (INIS)

    2010-01-01

    for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd 3 ) (157,437 cubic feet (ft 3 )). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd 3 (756,999 ft 3 ) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd 3 (0.9 million ft 3 ). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls (PCBs)) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with

  4. Liquid metal coolant disposal from UKAEA reactors at Dounreay

    International Nuclear Information System (INIS)

    Adam, E.R.

    1997-01-01

    As part of the United Kingdom's Fast Reactor Development programme two reactors were built and operated at Dounreay in the North of Scotland. DFR (Dounreay Fast Reactor) was operated from 1959-1977 and PFR (Prototype Fast Reactor) was operated from 1974-1994. Both reactors are currently undergoing Stage 1 Decommissioning and are installing plant to dispose of the bulk coolant (DFR ∼ 60 tonne; PFR ∼ 1500 tonne). The coolant (NaK) remaining at DFR is mainly in the primary circuit which contains in excess of 500 TBq of Cs137. Disposal of 40 tonnes of secondary coolant has already been carried out. The paper will describe the processes used to dispose of this secondary circuit coolant and how it is intended the remaining primary circuit coolant will be handled. The programme to process the primary coolant will also be described which involves the conversion of the liquid metal to caustic and its decontamination. No PFR coolant Na has been disposed off to date. The paper will describe the current decommissioning programme activities relating to liquid metal disposal and treatment describing the materials to be disposed of and the issue of decontamination of the effluents. (author)

  5. Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment plan

    International Nuclear Information System (INIS)

    April, J.G.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Plastino, J.C.; Roeck, F.V.; Tuttle, B.G.

    1997-04-01

    This Readiness Assessment Plan presents the methodology used to assess the readiness of the 300-FF-1 Remedial Action Project. Remediation involves the excavation, treatment if applicable, and final disposal of contaminated soil and debris associated with the waste sites in the 300-FF-1 Operable Unit. The scope of the 300-FF-1 remediation is to excavate, transport, and dispose of contaminated solid from sites identified in the 300-FF-1 Operable Unit

  6. Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Alfred Wickline

    2008-04-01

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): • 02-09-01, Mud Disposal Area • 03-08-03, Mud Disposal Site • 03-17-01, Waste Consolidation Site 3B • 03-23-02, Waste Disposal Site • 03-23-05, Europium Disposal Site • 03-99-14, Radioactive Material Disposal Area • 09-23-02, U-9y Drilling Mud Disposal Crater • 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: • For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. • For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: “Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02.” This CAS is closed with no further action. • For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be

  7. Cost effects of Cu powder and bentonite on the disposal costs of an HLW repository in

    International Nuclear Information System (INIS)

    Kim, Sung Ki; Lee, Min Soo; Lee, Jong Youl; Choi, Heui Joo; Choi, Jong Won

    2008-01-01

    This paper provides the cost effect results of Cu powder and bentonite on the disposal cost for an HLW repository in Korea. In the cost analysis for both of these cost drivers, the price of Cu powder and the bentonite can affect the canister cost and the bentonite cost of the disposal holes as well as backfilling cost of the tunnels, respectively. Finally, we found that the unit cost of Cu and bentonite was the dominant cost drivers for the surface and underground facilities of an HLW repository. Therefore, an optimization of a canister and the layout of a disposal hole and disposal tunnels are essential to decrease the direct disposal cost of spent fuels. The disposal costs can be largely divided into two parts such as a surface facilities' cost and an underground facilities' cost. According to the KRS' cost analysis, the encapsulation material as well as the buffering and backfilling cost were the significant costs. Especially, a canister's cost was approximately estimated to be more than one fourth of the overall disposal costs. So it can be estimated that the unit cost of Cu powder is an important cost diver. Because the outer shell of the canister was made of Cu powder by a cold spray coating method. In addition, the unit cost of bentonite can also affect the buffering and the backfilling costs of the disposal holes and the disposal tunnels. But, these material costs will be highly expensive and unstable due to the modernization of the developing countries. So the studies for a material cost should be continued to identify the actual cost of an HLW repository

  8. The Finnish final disposal programme proceeds to the site selection

    International Nuclear Information System (INIS)

    Seppaelae, T.

    1999-01-01

    Research for the selection of the final disposal site has been carried out already since the beginning of 1980's. Field studies were started in 1987: In the recent years, studied sites have included Olkiluoto in Eurajoki, Haestholmen in Loviisa, Romuvaara in Kuhmo and Kivetty in Aeaenekoski. Based on 40 years operation of four power plant units, the estimate for the accumulation of spent fuel to be disposed of in Finland is 2,600 tU. A 'Decision in Principle' is needed from the Finnish government to select the final disposal site, Posiva submitted the application for a policy decision in May 1999. The intended site of the facility is Olkiluoto which produces most of the spent fuel in Finland: A disposal would minimise the need of transports. In a poll among the inhabitants of Eurajoki, 60 per cent approved the final disposal facility. After a positive decision of the government, Posiva will construct an underground research facility in Olkiluoto. The construction of the final disposal facility will take place in the 2010's, the facility should be operational in 2020. (orig.) [de

  9. Disposal of disused sealed sources and approach for safety assessment of near surface disposal facilities (national practice of Ukraine)

    International Nuclear Information System (INIS)

    Alekseeva, Z.; Letuchy, A.; Tkachenko, N.V.

    2003-01-01

    The main sources of wastes are 13 units of nuclear power plants under operation at 4 NPP sites (operational wastes and spent sealed sources), uranium-mining industry, area of Chernobyl exclusion zone contaminated as a result of ChNPP accident, and over 8000 small users of sources of ionising radiation in different fields of scientific, medical and industrial applications. The management of spent sources is carried out basing on the technology from the early sixties. In accordance with this scheme accepted sources are disposed of either in the near surface concrete vaults or in borehole facilities of typical design. Radioisotope devices and gamma units are placed into near surface vaults and sealed sources in capsules into borehole repositories respectively. Isotope content of radwaste in the repositories is multifarious including Co-60, Cs-137, Sr-90, Ir-192, Tl-204, Po-210, Ra-226, Pu-239, Am-241, H-3, Cf-252. A new programme for waste management has been adopted. It envisions the modifying of the 'Radon' facilities for long-term storage safety assessment and relocation of respective types of waste in 'Vector' repositories.Vector Complex will be built in the site which is located within the exclusion zone 10Km SW of the Chernobyl NPP. In Vector Complex two types of disposal facilities are designed to be in operation: 1) Near surface repositories for short lived LLRW and ILRW disposal in reinforced concrete containers. Repositories will be provided with multi layer waterproofing barriers - concrete slab on layer composed of mixture of sand and clay. Every layer of radwaste is supposed to be filled with 1cm clay layer following disposal; 2) Repositories for disposal of bulky radioactive waste without cans into concrete vaults. Approaches to safety assessment are discussed. Safety criteria for waste disposal in near surface repositories are established in Radiation Protection Standards (NRBU-97) and Addendum 'Radiation protection against sources of potential exposure

  10. Projected tritium releases from F ampersand H Area Seepage Basins and the Solid Waste Disposal Facilities to Fourmile Branch

    International Nuclear Information System (INIS)

    Looney, B.B.; Haselow, J.S.; Lewis, C.M.; Harris, M.K.; Wyatt, D.E.; Hetrick, C.S.

    1993-01-01

    A large percentage of the radioactivity released to the environment by operations at the Savannah River Site (SRS) is due to tritium. Because of the relative importance of the releases of tritium from SRS facilities through the groundwater to the environment, periodic evaluation and documentation of the facility operational status, proposed corrective actions, and projected changes/reductions in tritium releases are justified. Past, current, and projected tritium releases from the F and H Area Seepage Basins and the Solid Waste Disposal Facilities (SWDF) to Fourmile Branch are described. Each section provides a brief operational history along with the current status and proposed corrective actions. A conceptual model and quantitative estimates of tritium release from the facilities into the groundwater and the environment are developed. Tritium releases from the F and H Area Seepage Basins are declining and will be further reduced by the implementation of a groundwater corrective action required by the Resource Conservation and Recovery Act (RCRA). Tritium releases from the SWDF have been relatively stable over the past 10 years. It is anticipated that SWDF tritium releases to Fourmile Branch will remain approximately at current levels for at least 10--20 years. Specific characterization activities are recommended to allow an improved projection of tritium flux and to assist in developing plans for plume mitigation. SRS and the South Carolina Department of Health and Environmental Control are developing groundwater corrective action plans for the SWDF. Portions of the SWDF are also regulated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). Reduction of tritium flux is one of the factors considered in the development of the RCRA/CERCLA groundwater corrective action. The final section of the document presents the sum of the projected tritium fluxes from these facilities to Fourmile Branch

  11. Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident at Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320): Final report

    International Nuclear Information System (INIS)

    1987-06-01

    In accordance with the National Environmental Policy Act, the Commission's implementing regulations, and the Commission's April 27, 1981 Statement of Policy, the Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2 NUREG-0683 (PEIS) is being supplemented. This supplement updates the environmental evaluation of accident-generated water disposal alternatives published in the PEIS, utilizing more complete and current information. Also, the supplement includes a specific environmental evaluation of the licensee's proposal for water disposition. Although no clearly preferable water disposal alternative was identified, the supplement concluded that a number of alternatives could be implemented without significant environmental impact. The NRC staff has concluded that the licensee's proposed disposal of the accident-generated water by evaporation will not significantly affect the quality of the human environment. Further, any impacts from the disposal program are outweighed by its benefits

  12. Sewage Sludge Disposal with Energy Recovery by Fluidized Bed Gasification and CHP-Units

    Energy Technology Data Exchange (ETDEWEB)

    Horst, J.; Gross, B.; Kimmerle, K. [Inst. fuer ZukunftsEnergieSysteme, Saarbruecken (Germany); Eder, C. [Christian Eder Technology e.K., Neunkirchen (Germany)

    2006-07-15

    Sewage sludge is a composition of by-products collected during the different stages of the waste water cleaning process of communal and industrial treatment plants. Because of its harmful impacts on environment as well as animals - and mankind - health sewage sludge has become a problem. Therefore disposal of sludge is today on a crossroad depending on the discussion about soil contamination by using the sludge as fertiliser. Some countries are now abandoning disposal to agriculture and are entering into thermal treatment with the argument: 'Harmful substances already separated with high financial effort should definitely be removed from the food cycle and should not return indirectly via the fields to food and water'. The SEDIS project - a project funded by the European Commission under the specific research and technological development programme 'Promotion of innovation and encouragement of SME participation' - is aimed at eliminating the rising disposal problem of sewage sludge by an energy-related use of the raw sludge directly on site of wastewater treatment plants. SEDIS is developing an innovative, self-sustaining system to process liquid and pasty waste such as sewage sludge and solid biomass to utilise product-gas for power-generation direct on site. This process is called ETVS-process and is patented by Christian Eder Technology e.K. Today, where each company has to look for sustainable savings, the SEDIS concept offers a decentralised process, self-sustaining from other energy sources and able to provide the whole treatment plant with energy. Furthermore the treatment plant would be independent of price policy of sludge disposers.

  13. 1997 State-by-State Assessment of Low-Level Radioactive Wastes Received at Commercial Disposal Sites

    International Nuclear Information System (INIS)

    Fuchs, R. L.

    1998-01-01

    Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in the United States. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included in this report are tables showing the distribution of waste by state for 1997 and a comparison of waste volumes and radioactivity by state for 1993 through 1997; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1997

  14. Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units Nevada Test Site, Nevada, Rev. No.: 0 with ROTC 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    David A. Strand

    2004-05-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S Department of Defense (DoD). Corrective Action Unit 543 is located in Area 6 and Area 15 of the NTS, which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Seven corrective action sites (CASs) comprise CAU 543 and are listed below: (1) 06-07-01, Decon Pad; (2) 15-01-03, Aboveground Storage Tank; (3) 15-04-01, Septic Tank; (4) 15-05-01, Leachfield; (5) 15-08-01, Liquid Manure Tank; (6) 15-23-01, Underground Radioactive Material Area; and (7) 15-23-03, Contaminated Sump, Piping. Corrective Action Site 06-07-01, Decon Pad, is located in Area 6 and consists of the Area 6 Decontamination Facility and its components that are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency (EPA) Farm and are related to waste disposal activities at the EPA Farm. The EPA Farm was a fully-functional dairy associated with animal experiments conducted at the on-site laboratory. The corrective action investigation (CAI) will include field inspections, video-mole surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions. The CASs within CAU 543 are being investigated because hazardous and/or radioactive constituents may be present at concentrations that could potentially pose a threat to human health and the environment. The seven CASs in CAU 543

  15. Management and disposal of used nuclear fuel and reprocessing wastes

    International Nuclear Information System (INIS)

    1983-01-01

    The subject is dealt with in chapters, entitled: introduction (general statement of problem); policy framework (criteria for waste management policy); waste management and disposal, as practised and planned (general; initial storage; reprocessing and conditioning of reprocessing wastes; intermediate storage; transportation; packaging; disposal); international co-operation. Details of the situation in each country concerned (Australia, Belgium, Canada, France, Federal Republic of Germany, Spain, Sweden, Switzerland and United Kingdom) are included as annexes. (U.K.)

  16. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU'S) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment from doses to humans and animals and associated cancer risks, exposure via food chains, and historical data

  17. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU's) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment and baseline human health evaluation including a toxicity assessment, and a baseline environmental evaluation

  18. Differing approaches to waste disposal

    International Nuclear Information System (INIS)

    Greenhalgh, G.

    1983-01-01

    The social, political, and economic problems of radioactive waste management, which are discussed at a scientific afternoon meeting held during the IAEA general conference on 12 October, with speakers from Argentina, West Germany, France, India, Japan, Sweden, Britain and the United States, are described. An OECD Nuclear Energy Agency report on the demonstration of long-term safety of deep underground disposal of high level radioactive waste is discussed. (U.K.)

  19. 36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal sites... NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR SOLID WASTE DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM § 6.6 Solid waste disposal sites within new additions to the National Park System. (a) An operator...

  20. Mixed waste disposal facility at the Nevada Test Site

    International Nuclear Information System (INIS)

    Dickman, P.T.; Kendall, E.W.

    1987-01-01

    In 1984, a law suit brought against DOE resulted in the requirement that DOE be subject to regulation by the state and US Environmental Protection Agency (EPA) for all hazardous wastes, including mixed wastes. Therefore, all DOE facilities generating, storing, treating, or disposing of mixed wastes will be regulated under the Resource Conservation and Recovery Act (RCTA). In FY 1985, DOE Headquarters requested DOE low-level waste (LLW) sites to apply for a RCRA Part B Permit to operate radioactive mixed waste facilities. An application for the Nevada Test Site (NTS) was prepared and submitted to the EPA, Region IX in November 1985 for review and approval. At that time, the state of Nevada had not yet received authorization for hazardous wastes nor had they applied for regulatory authority for mixed wastes. In October 1986, DOE Nevada Operations Office was informed by the Rocky Flats Plant that some past waste shipments to NTS contained trace quantities of hazardous substances. Under Colorado law, these wastes are defined as mixed. A DOE Headquarters task force was convened by the Under Secretary to investigate the situation. The task force concluded that DOE has a high priority need to develop a permitted mixed waste site and that DOE Nevada Operations Office should develop a fast track project to obtain this site and all necessary permits. The status and issues to be resolved on the permit for a mixed waste site are discussed

  1. Oak Ridge greater confinement disposal demonstrations

    International Nuclear Information System (INIS)

    Van Hoesen, S.D.; Clapp, R.B.

    1987-01-01

    Demonstrations are being conducted in association with the disposal of a high activity low-level waste (LLW) stream. The waste stream in question will result from the cement solidification of decanted liquids from the Melton Valley Storage Tanks (MVST). The solid waste will be produced beginning in mid summer 1988. It is anticipated to have significant concentrations of Cs-137 and Sr-90, with smaller amounts of other radionuclides and <100 nCi/gm of TRU. The solid waste forms are expected to have surface dose rates in the 1 to 2 r/hr range. The solid waste will also contain several chemical species at concentrations which are below those of concern, but which may present enhanced corrosion potential for the disposal units. 2 refs., 5 figs

  2. Production rates for United States Forest Service brush disposal planning in the northern Rocky Mountains

    Science.gov (United States)

    Dan Loeffler; Stu Hoyt; Nathaniel Anderson

    2017-01-01

    Timber harvesting operations generate brush and other vegetative debris, which often has no marketable value. In many western U.S. forests, these materials represent a fire hazard and a potential threat to forest health and must be removed or burned for disposal. Currently, there is no established, consistent method to estimate brush disposal production rates in the U....

  3. 1992 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites

    International Nuclear Information System (INIS)

    Fuchs, R.L.; McDonald, S.D.

    1993-09-01

    Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in the United States. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included in this report are tables showing the distribution of waste by state for 1992 and a comparison of waste volumes and radioactivity by state for 1988 through 1992; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1992. This report distinguishes between low-level radioactive waste shipped directly for disposal by generators and waste that was handled by an intermediary, a reporting change introduced in the 1988 state-by-state report

  4. 1994 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in the United States. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included in this report are tables showing the distribution of waste by state for 1994 and a comparison of waste volumes and radioactivity by state for 1990 through 1994; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1994. This report distinguishes between low-level radioactive waste shipped directly for disposal by generators and waste that was handled by an intermediary, a reporting change introduced in the 1988 state-by-state report.

  5. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.

  6. Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

    International Nuclear Information System (INIS)

    Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu

    2016-01-01

    In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea

  7. Environmental Restoration Contractor Resource Conservation and Recovery Act Permit Implementation Plan

    International Nuclear Information System (INIS)

    Lewis, R.A.

    1996-05-01

    This document contains the revised Environmental Restoration Contractor (ERC) Implementation Plan for compliance with the Dangerous Waste and Hazardous and Solid Waste Amendment portions of the Resource Conservation and Recovery Act (RCRA) Permit for the Treatment, Storage, and Disposal of Dangerous Waste (hereafter referred to as the open-quotes Permitclose quotes). The Permit became effective on September 28, 1994. The ERC has developed the Permit Implementation Plan to ensure that the Permit is properly implemented within the ERC project and functions. The plan contains a list of applicable permit conditions, descriptions, responsible organizations, and the status of compliance. The ERC's responsibilities for Permit implementation are identified within both project and functional organizations. Project Managers are responsible for complying with conditions specific to a particular treatment, storage, or disposal (TSD) unit. TSD-specific compliance in include items such as closure plan deliverables, reporting and record keeping requirements, or compliance with non-unit-specific tasks such as spill reporting and emergency response. Functional organizations are responsible for sitewide activities, such as coordinating Permit modifications and developing personnel training programs

  8. Soil management planning for military installations: Strategy for identifying contaminated soils

    International Nuclear Information System (INIS)

    Makdisi, R.S.; Baskin, D.A.; Downey, D.; Taffinder, S.A.

    1992-01-01

    Numerous federal and state regulations mandate the proper handling and disposal and/or treatment of contaminated soils. The Land Disposal Ban and the increasing lack of new or proximal land disposal facilities, coupled with the increasing liability of off-site disposal, have created a need for altering the traditional methods of managing contaminated sods. To delineate soil management decisions, a Soil Management Plan (SMP) was developed which incorporates the substantive requirements of CERCLA/SARA and RCRA into the ongoing base activities (i.e., construction projects, utility repairs and maintenance) and other environmental projects (i.e., underground storage tank removals) that may involve contaminated soils. The decision-making process is developed to guide base personnel in recognizing contamination, following proper sampling and temporary storage procedures, preventing unnecessary human exposure and isolating soils for removal off-site or treatment on-site. The SMP also contains a comprehensive review of soil remediation technologies, such as biological treatment, soil vapor extraction, soil washing, biofiltering, thermal desorption, soil stabilization/solidification, chemical/physical treatment and incineration. Contaminant types expected at the federal military facility are cross-referenced to the appropriate remediation technologies to determine the specific base needs for a soil treatment unit. An example of a conceptual design for a hydrocarbon-contaminated soil treatment unit is presented for a base where underground fuel tanks are the principal source of soil contamination

  9. Hazardous constituent source term. Revision 2

    International Nuclear Information System (INIS)

    1994-01-01

    The Department of Energy (DOE) has several facilities that either generate and/or store transuranic (TRU)-waste from weapons program research and production. Much of this waste also contains hazardous waste constituents as regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA). Toxicity characteristic metals in the waste principally include lead, occurring in leaded rubber gloves and shielding. Other RCRA metals may occur as contaminants in pyrochemical salt, soil, debris, and sludge and solidified liquids, as well as in equipment resulting from decontamination and decommissioning activities. Volatile organic compounds (VOCS) contaminate many waste forms as a residue adsorbed on surfaces or occur in sludge and solidified liquids. Due to the presence of these hazardous constituents, applicable disposal regulations include land disposal restrictions established by Hazardous and Solid Waste Amendments (HSWA). The DOE plans to dispose of TRU-mixed waste from the weapons program in the Waste Isolation Pilot Plant (WIPP) by demonstrating no-migration of hazardous constituents. This paper documents the current technical basis for methodologies proposed to develop a post-closure RCRA hazardous constituent source term. For the purposes of demonstrating no-migration, the hazardous constituent source term is defined as the quantities of hazardous constituents that are available for transport after repository closure. Development of the source term is only one of several activities that will be involved in the no-migration demonstration. The demonstration will also include uncertainty and sensitivity analyses of contaminant transport

  10. Decontamination and disposal of Sb-124 at Palo Verde Nuclear Generating Station

    International Nuclear Information System (INIS)

    Miller, A.D.; Hillmer, T.P.; Kester, J.W.; Hensch, J.R.

    1988-01-01

    Palo Verde Nuclear Generating Station (PVNGS) is a three unit Combustion Engineering pressurized water reactor site. Each unit consists of an identical, self contained 1270 MWe reactor. This standardized design allows sharing of design improvements and equipment leading to optimum operation of the individual units. One design improvement, identified early into the operation of Unit 1, involved the elemental antimony content of the seals and bearings within the reactor coolant pumps. Normal wear of these components releases small amounts of elemental antimony. This antimony in turn deposits on in-core surfaces and activates to produce the isotopes Sb-122 and Sb-124. These isotopes emit highly energetic gamma rays which contribute significantly to the exposure and radwaste disposal charges at PVNGS. For these reasons, the Antimony Removal Program was undertaken to remove the radioactive and elemental antimony from the nuclear steam supply system at all three units. The work presented here describes the antimony decontamination and disposal

  11. Differences in alarm events between disposable and reusable electrocardiography lead wires.

    Science.gov (United States)

    Albert, Nancy M; Murray, Terri; Bena, James F; Slifcak, Ellen; Roach, Joel D; Spence, Jackie; Burkle, Alicia

    2015-01-01

    Disposable electrocardiographic lead wires (ECG-LWs) may not be as durable as reusable ones. To examine differences in alarm events between disposable and reusable ECG-LWs. Two cardiac telemetry units were randomized to reusable ECG-LWs, and 2 units alternated between disposable and reusable ECG-LWs for 4 months. A remote monitoring team, blinded to ECG-LW type, assessed frequency and type of alarm events by using total counts and rates per 100 patient days. Event rates were compared by using generalized linear mixed-effect models for differences and noninferiority between wire types. In 1611 patients and 9385.5 patient days of ECG monitoring, patient characteristics were similar between groups. Rates of alarms for no telemetry, leads fail, or leads off were lower in disposable ECG-LWs (adjusted relative risk [95% CI], 0.71 [0.53-0.96]; noninferiority P < .001; superiority P = .03) and monitoring (artifact) alarms were significantly noninferior (adjusted relative risk [95% CI]: 0.88, [0.62-1.24], P = .02; superiority P = .44). No between-group differences existed in false or true crisis alarms. Disposable ECG-LWs were noninferior to reusable ECG-LWs for all false-alarm events (N [rate per 100 patient days], disposable 2029 [79.1] vs reusable 6673 [97.9]; adjusted relative risk [95% CI]: 0.81 [0.63-1.06], P = .002; superiority P = .12.) Disposable ECG-LWs with patented push-button design had superior performance in reducing alarms created by no telemetry, leads fail, or leads off and significant noninferiority in all false-alarm rates compared with reusable ECG-LWs. Fewer ECG alarms may save nurses time, decrease alarm fatigue, and improve patient safety. ©2015 American Association of Critical-Care Nurses.

  12. Comparison of low-level waste disposal programs of DOE and selected international countries

    International Nuclear Information System (INIS)

    Meagher, B.G.; Cole, L.T.

    1996-06-01

    The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada's first demonstration LLW disposal facility

  13. Control of water infiltration into near surface LLW disposal units. Progress report on field experiments at a humid region site, Beltsville, Maryland: Volume 8

    International Nuclear Information System (INIS)

    Schulz, R.K.; Ridky, R.W.

    1995-04-01

    This study's objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care

  14. Oceanography related to deep sea waste disposal

    International Nuclear Information System (INIS)

    1978-09-01

    In connection with studies on the feasibility of the safe disposal of radioactive waste, from a large scale nuclear power programme, either on the bed of the deep ocean or within the deep ocean bed, preparation of the present document was commissioned by the (United Kingdom) Department of the Environment. It attempts (a) to summarize the present state of knowledge of the deep ocean environment relevant to the disposal options and assess the processes which could aid or hinder dispersal of material released from its container; (b) to identify areas of research in which more work is needed before the safety of disposal on, or beneath, the ocean bed can be assessed; and (c) to indicate which areas of research can or should be undertaken by British scientists. The programmes of international cooperation in this field are discussed. The report is divided into four chapters dealing respectively with geology and geophysics, geochemistry, physical oceanography and marine biology. (U.K.)

  15. Grout and Glass Performance in Support of Stabilization/Solidification of the MVST Tank Sludges

    Energy Technology Data Exchange (ETDEWEB)

    Gilliam, T.M.; Spence, R.D.

    1998-11-01

    Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) pending treatment for disposal. The waste separates into two phases: sludge and supematant. Some of the supematant from these tanks has been decanted, solidified into a grout, and stored for disposal as a solid low-level waste. The sludges in the tank bottoms have been accumulating ,for several years. Some of the sludges contain a high amount of gamma activity (e.g., `37CS concentration range of 0.01 3-11 MBq/g) and contain enough transuranic (TRU) radioisotopes to be classified as TRU wastes. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough in the available total constituent analysis for the MVST sludge to be classified as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste.

  16. Greater confinement disposal program at the Savannah River Plant

    International Nuclear Information System (INIS)

    Towler, O.A.; Cook, J.R.; Peterson, D.L.; Reddick, J.A.

    1984-01-01

    A facility to demonstrate Greater Confinement Disposal (GCD) of low-level solid radioactive waste in a humid environment has been built and is operating at the Savannah River Plant (SRP). GCD practices of waste segregation into high and low activity concentrations, emplacement of waste below the root zone, waste stabilization, and capping are being used in the demonstration. Activity concentrations to select wastes for GCD are based on the volume/activity distribution of low-level solid wastes as obtained from SRP burial records, and are equal to or less than those for Class B waste in 10 CFR 61. The first disposal units constructed are twenty 9-ft-diam, 30-ft-deep boreholes. These holes will be used to dispose of wastes from the production reactors, tritiated wastes, and selected wastes from offsite. In 1984, construction will begin on an engineered GCD trench for disposal of boxed waste and large bulky items that meet the activity concentration criteria. 4 references, 5 figures, 2 tables

  17. Post-Closure Inspection Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench Tonopah Test Range, Nevada, Calendar Year 2000

    Energy Technology Data Exchange (ETDEWEB)

    K. B. Campbell

    2001-06-01

    Post-closure monitoring requirements for the Roller Coaster Sewage Lagoons and North Disposal Trench (Corrective Action Unit [CAW 404]) (Figure 1) are described in Closure Report for Corrective Action Unit 404, Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, report number DOE/NV--187. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on September 11, 1998. Permeability results of soils adjacent to the engineered cover and a request for closure of CAU 404 were transmitted to the NDEP on April 29, 1999. The CR (containing the Post-Closure Monitoring Plan) was approved by the NDEP on May 18, 1999. Post-closure monitoring at CAU 404 consists of the following: (1) Site inspections done twice a year to evaluate the condition of the unit; (2) Verification that the site is secure; (3) Notice of any subsidence or deficiencies that may compromise the integrity of the unit; (4) Remedy of any deficiencies within 90 days of discovery; and (5) Preparation and submittal of an annual report. Site inspections were conducted on June 19, 2000, and November 21, 2000. The site inspections were conducted after completion of the revegetation activities (October 30, 1997) and NDEP approval of the CR (May 18, 1999). All site inspections were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of inspection checklists, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and copies of the inspection photographs are found in Attachment C.

  18. Identification of permit and waste acceptance criteria provisions requiring modification for acceptance of commercial mixed waste

    International Nuclear Information System (INIS)

    1994-03-01

    In October 1990, representatives of States and compact regions requested that the US Department of Energy (DOE) explore an agreement with host States and compact regions under which DOE would accept commercial mixed low-level radioactive waste (LLW) at DOE's own treatment and disposal facilities. A program for DOE management of commercial mixed waste is made potentially more attractive in light of the low commercial mixed waste volumes, high regulatory burdens, public opposition to new disposal sites, and relatively high cost of constructing commercial disposal facilities. Several studies were identified as essential in determining the feasibility of DOE accepting commercial mixed waste for disposal. The purpose of this report is to identify any current or proposed waste acceptance criteria (WAC) or Resource Conservation and Recovery Act (RCRA) provisions that would have to be modified for commercial mixed waste acceptance at specified DOE facilities. Following the introduction, Section 2 of this report (a) provides a background summary of existing and proposed mixed waste disposal facilities at each DOE site, and (b) summarizes the status of any RCRA Part B permit and WAC provisions relating to the disposal of mixed waste, including provisions relating to acceptance of offsite waste. Section 3 provides overall conclusions regarding the current status and permit modifications that must be implemented in order to grant DOE sites authority under their permits to accept commercial mixed waste for disposal. Section 4 contains a list of references

  19. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320): Draft

    International Nuclear Information System (INIS)

    1986-12-01

    In accordance with the National Environmental Policy Act and the Commission's implementing regulations and its April 27, 1981 Statement of Policy, the Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2 NUREG-0683 (PEIS) is being supplemented. This draft supplement updates the environmental evaluation of accident-generated water disposal alternatives published in the PEIS, utilizing more complete and current information. Also, the draft supplement includes a specific environmental evaluation of the licensee's recently submitted proposal for water disposition

  20. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 115: AREA 25 TEST CELL A FACILITY, NEVADA TEST SITE, NEVADA

    International Nuclear Information System (INIS)

    2006-01-01

    This Closure Report (CR) describes the activities performed to close CAU 115, Area 25 Test Cell A Facility, as presented in the NDEP-approved SAFER Plan (NNSA/NSO, 2004). The SAFER Plan includes a summary of the site history, process knowledge, and closure standards. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical and radiological data to confirm that the remediation goals were met and to document final site conditions. The approved closure alternative as presented in the SAFER Plan for CAU 115 (NNSA/NSO, 2004) was clean closure; however, closure in place was implemented under a Record of Technical Change (ROTC) to the SAFER Plan when radiological surveys indicated that the concrete reactor pad was radiologically activated and could not be decontaminated to meet free release levels. The ROTC is included as Appendix G of this report. The objectives of closure were to remove any trapped residual liquids and gases, dispose regulated and hazardous waste, decontaminate removable radiological contamination, demolish and dispose aboveground structures, remove the dewar as a best management practice (BMP), and characterize and restrict access to all remaining radiological contamination. Radiological contaminants of concern (COCs) included cobalt-60, cesium-137, strontium-90, uranium-234/235/236/238, and plutonium-239/240. Additional COCs included Resource Conservation and Recovery Act (RCRA) metals, polychlorinated biphenyls (PCBs), and asbestos