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Sample records for rcra waste sites

  1. Case history update: RCRA waste site remediation by telerobotic methods

    International Nuclear Information System (INIS)

    Yemington, C.R.; Stone, J.

    1992-01-01

    This paper presents a summary of the first 18 months of closure work at the Kerr Hollow Quarry site on the DOE reservation at Oak Ridge, Tennessee. Closure work includes recovery and processing of explosive, toxic and radioactive waste. As of January 1992, more than 10,000 items had been processed and removed from the quarry, exclusively by remotely operated equipment. Drums, buckets, tubing assemblies and other containers are being shredded to react any explosive contents. Concussion and projectiles are controlled by operating the shredder under 30 feet of water. The performance of the shredder, the effectiveness of the approach, production rates and maintenance requirements are addressed in the paper. To avoid exposing personnel to hazards, all work in the restricted area is done remotely. Two remotely operated vehicles were used to clear a pad, set a stand and install the 200-hp shredder. Some materials exposed by shredding are stable in water but react when exposed to air. In addition, radioactive items are mixed in with the other wastes. Safety considerations have therefore led to use of remote techniques for handling and examining materials after recovery. Deteriorated gas cylinders, which may contain pressurized toxic materials, are recovered and handled exclusively by remotely operated equipment. Waste retrieval work at the Kerr Hollow Quarry has proven the capability and cost-effectiveness of remotely operated equipment to deal with a wide variety of hazardous materials in an unstructured waste site environment. A mixture of radioactive materials, toxic chemicals, explosives and asbestos has been found and processed. Remotely operated vehicles have retrieved, sorted and processed more than 10,000 items including drums, buckets, pipe manifolds, gas cylinders and other containers

  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. 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

  5. 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

  6. 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)...

  7. 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

  8. 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

  9. 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.

  10. 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.

  11. 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

  12. 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

  13. Integration of CERCLA and RCRA requirements at the Radioactive Waste Burial Grounds, Savannah River Site, Aiken, South Carolina

    International Nuclear Information System (INIS)

    Hoffman, W.D.; Wyatt, D.E.

    1992-01-01

    The purpose of this paper to is present the comprehensive approach being taken at the Savannah River Site (SRS) to consolidate regulatory documents, characterization and assessment activities for 3 contiguous waste management facilities. These facilities cover 7.12 x 10 5 m 2 (194 acres) and include an Old Radioactive Waste Burial Ground, a Low Level Radioactive Waste Disposal Facility, and a closed Mixed Waste Management Facility. Each of these facilities include one or more operable units including solvent tanks, transuranic waste storage pads, research lysimeters and experimental confinement disposal vaults. All of these facilities have differing submittal dates for regulatory documents but similar and continuous environmental problems. The characterization and risk assessment require simultaneous efforts for all facilities to adequately define the nature and extent of past, present and future environmental impact. Current data indicates that contaminant plumes in both soil and water are comingled, interspersed and possibly exist internally within the contiguous facilities, requiring a combined investigative effort. This paper describes the combination of regulatory documents leading to this comprehensive and integrative approach for burial ground characterization at the Savannah River Site

  14. RCRA Assessment Plan 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

    A groundwater quality assessment plan was prepared for waste management area S-SX at the Hanford Site. Groundwater monitoring is conducted at this facility in accordance with Title 40, Code of Federal Regulation (CFR) Part 265, Subpart F [and by reference of Washington Administrative Code (WAC) 173-303-400(3)]. The facility was placed in assessment groundwater monitoring program status after elevated waste constituents and indicator parameter measurements (i.e., chromium, technetium-99 and specific conductance) in downgradient monitoring wells were observed and confirmed. A first determination, as allowed under 40 CFR 265.93(d), provides the owner/operator of a facility an opportunity to demonstrate that the regulated unit is not the source of groundwater contamination. Based on results of the first determination it was concluded that multiple source locations in the waste management area could account for observed spatial and temporal groundwater contamination patterns. Consequently, a continued investigation is required. This plan, developed using the data quality objectives process, is intended to comply with the continued investigation requirement. Accordingly, the primary purpose of the present plan is to determine the rate and extent of dangerous waste (hexavalent chromium and nitrate) and radioactive constituents (e.g., technetium-99) in groundwater and to determine their concentrations in groundwater beneath waste management area S-SX. Comments and concerns expressed by the Washington State Department of Ecology on the initial waste management area S-SX assessment report were addressed in the descriptive narrative of this plan as well as in the planned activities. Comment disposition is documented in a separate addendum to this plan

  15. 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

  16. 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.

  17. 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.

  18. 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.

  19. 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

  20. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, P. M.

    2013-02-21

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 1993 RCRA Part B permit renewal application, Savannah River Site: Volume 10, Consolidated Incineration Facility, Section C, Revision 1

    International Nuclear Information System (INIS)

    Molen, G.

    1993-08-01

    This section describes the chemical and physical nature of the RCRA regulated hazardous wastes to be handled, stored, and incinerated at the Consolidated Incineration Facility (CIF) at the Savannah River Site. It is in accordance with requirements of South Carolina Hazardous Waste Management Regulations R.61-79.264.13(a) and(b), and 270.14(b)(2). This application is for permit to store and teat these hazardous wastes as required for the operation of CIF. The permit is to cover the storage of hazardous waste in containers and of waste in six hazardous waste storage tanks. Treatment processes include incineration, solidification of ash, and neutralization of scrubber blowdown

  12. Fall 2010 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility and the CPP 601/627/640 Facility at the INL Site

    Energy Technology Data Exchange (ETDEWEB)

    Boehmer, Ann

    2010-11-01

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment. The post closure permit also includes semiannual reporting requirements under Permit Conditions III.H. and I.U. These reporting requirements have been combined into this single semiannual report, as agreed between the Idaho Cleanup Project and Idaho Department of Environmental Quality. The Permit Condition III.H. portion of this report includes a description and the results of field methods associated with groundwater monitoring of the Waste Calcining Facility. Analytical results from groundwater sampling, results of inspections and maintenance of monitoring wells in the Waste Calcining Facility groundwater monitoring network, and results of inspections of the concrete cap are summarized. The Permit Condition I.U. portion of this report includes noncompliances not otherwise required to be reported under Permit Condition I.R. (advance notice of planned changes to facility activity which may result in a noncompliance) or Permit Condition I.T. (reporting of noncompliances which may endanger human health or the environment). This report also provides groundwater sampling results for wells that were installed and monitored as part of the Phase 1 post-closure period of the landfill closure components in accordance with HWMA/RCRA Landfill Closure Plan for the CPP-601 Deep

  13. 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

  14. A RCRA clean closure of a unique site - Kerr Hollow quarry at the Y-12 Plant

    International Nuclear Information System (INIS)

    Stone, J.E.; Yemington, C.

    1991-01-01

    An abandoned rock quarry, Kerr Hollow Quarry (KHQ), near the DOE Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, was used from 1951-1988 as a site to treat RCRA wastes which were reactive, corrosive, or ignitable and which posed major concerns for personnel safety. The wastes were generated from operations at the Y-12 Plant and Oak Ridge National Laboratory and were previously treated by allowing the wastes to react with the water in KHQ. When closure of the site was required by the RCRA regulations, a closure method was selected to allow for clean closure of the quarry without treatment or removal of the water in KHQ. The method proposed to and approved by the Tennessee Department of Health and Environment (TDHE) was one of surveying the containers in the quarry by a submersible Remotely Operated Vehicle (ROV) using sonar and visually inspecting the containers by camera to confirm that all containers are breached and empty. Any container found intact would be breached to allow the contents to react with water and form non-hazardous residue. The progress of this unique type of closure is presented along with a summary of the problems encountered, planning activities, equipment utilized and other information about the closure. All work was done with remotely operated equipment. This work is being performed by Sonsub, Inc. This closure project showed the practicality and cost benefits of telerobotic systems for work on hazardous waste sites. In addition to the intangible benefit of reduced exposure of workers, insurance costs are much lower and efficiency is higher. Daily start-up time is reduced since there is no need to don protective suits or other gear. Productivity is higher since personnel work only in clean areas where they are not hampered by protective gear. Cleanup time at shift end is minimized since the remote equipment does not leave the hazardous area and personnel need not go through decontamination

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for Single-Shell Tank (SST) Waste Management Areas

    International Nuclear Information System (INIS)

    MCCARTHY, M.M.

    1999-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly

  4. Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    MCCARTHY, M.M.

    1999-08-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

  5. 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

  6. 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

  7. 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

  8. Mixed waste management at the Hanford Site

    International Nuclear Information System (INIS)

    Roberts, R.J.; Jasen, W.G.

    1991-01-01

    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 (AEA) and the Resource Conservation and Recovery Act (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, special projects have been initiated for the management of RMW. This paper addresses the management of solid RMW. The management of bulk liquid RMW will not be described. 7 refs., 4 figs

  9. 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.

  10. 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

  11. 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

  12. 75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

    Science.gov (United States)

    2010-01-07

    ...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. 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

  18. 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...

  19. 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

  20. Spring 2009 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post-Closure Permit for the INTEC Waste Calcining Facility at the INL Site

    International Nuclear Information System (INIS)

    Boehmer, Ann M.

    2009-01-01

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under and approved Hazardous Waste Management Act/Resource Conservation and Recovery Act Closure plan. Vessels and spaces were grouted and then covered with a concrete cap. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment.

  1. Spring 2009 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post-Closure Permit for the INTEC Waste Calcining Facility at the INL Site

    Energy Technology Data Exchange (ETDEWEB)

    Boehmer, Ann M.

    2009-05-31

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under and approved Hazardous Waste Management Act/Resource Conservation and Recovery Act Closure plan. Vessels and spaces were grouted and then covered with a concrete cap. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment.

  2. 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

  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. 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

  5. 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

  6. 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.

  7. 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

  8. 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.

  9. Hanford Site waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    Place, B.G.

    1998-01-01

    This plan, which is required by US Department of Energy (DOE) Order 5400. 1, provides waste minimization and pollution prevention guidance for all Hanford Site contractors. The plan is primary in a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan, Prime contractor implementation plans, and the Hanford Site Guide for Preparing and Maintaining Generator Group Pollution Prevention Program Documentation (DOE-RL, 1997a) describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and 3005(h) (RCRA and EPA, 1994). Items discussed include the pollution prevention policy and regulatory background, organizational structure, the major objectives and goals of Hanford Site's pollution prevention program, and an itemized description of the Hanford Site pollution prevention program. The document also includes US Department of Energy, Richland Operations Office's (RL's) statement of policy on pollution prevention as well as a listing of regulatory drivers that require a pollution prevention program

  10. Hanford Site Transuranic (TRU) Waste Certification Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    2000-01-01

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

  11. 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...

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 78 FR 79654 - Vermont: Proposed Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-12-31

    ...] Vermont: Proposed Authorization of State Hazardous Waste Management Program Revisions AGENCY... Docket ID No. EPA-R01- RCRA-2013-0554, by mail to Sharon Leitch, RCRA Waste Management and UST Section..., RCRA Waste Management and UST Section, Office of Site Remediation and Restoration (OSRR07-1), US EPA...

  18. Performance demonstration program plan for RCRA constituent analysis of solidified wastes

    International Nuclear Information System (INIS)

    1995-06-01

    Performance Demonstration Programs (PDPS) are designed to help ensure compliance with the Quality Assurance Objectives (QAOs) for the Waste Isolation Pilot Plant (WIPP). The PDPs are intended for use by the Department of Energy (DOE) Carlsbad Area Office (CAO) to assess and approve the laboratories and other measurement facilities supplying services for the characterization of WIPP TRU waste. The PDPs may also be used by CAO in qualifying laboratories proposing to supply additional analytical services that are required for other than waste characterization, such as WIPP site operations. The purpose of this PDP is to test laboratory performance for the analysis of solidified waste samples for TRU waste characterization. This performance will be demonstrated by the successful analysis of blind audit samples of simulated, solidified TRU waste according to the criteria established in this plan. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess laboratory performance regarding compliance with the QAOs. The concentration of analytes in the PDP samples will address levels of regulatory concern and will encompass the range of concentrations anticipated in actual waste characterization samples. Analyses that are required by the WIPP to demonstrate compliance with various regulatory requirements and which are included in the PDP must be performed by laboratories that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses and the samples on which they are performed are referred to as WIPP samples for the balance of this document

  19. 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

  20. 75 FR 50932 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-08-18

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...-1990. FOR FURTHER INFORMATION CONTACT: Robin Biscaia, RCRA Waste Management Section, Office of Site... final [[Page 50933

  1. RCRA Part B permit modifications for cost savings and increased flexibility at the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Jierree, C.; Ticknor, K.

    1996-10-01

    With shrinking budgets and downsizing, a need for streamlined compliance initiatives became evident at the Rocky Flats Environmental Technology Site (RFETS). Therefore, Rocky Mountain Remediation Services (RMRS) at the RFETS successfully and quickly modified the RFETS RCRA Part B Permit to obtain significant cost savings and increased flexibility. This 'was accomplished by requesting operations personnel to suggest changes to the Part B Permit which did not diminish overall compliance and which would be most. cost beneficial. The U.S. Department of Energy (DOE) subsequently obtained approval of those changes from the Colorado Department of Public Health and the Environment (CDPHE)

  2. 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

  3. 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

  4. 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)

  5. Nuclear waste repository siting

    International Nuclear Information System (INIS)

    Soloman, B.D.; Cameron, D.M.

    1987-01-01

    This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

  6. 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

  7. 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

  8. 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

  9. 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.

  10. Waste Sites - Municipal Waste Operations

    Data.gov (United States)

    NSGIC Education | GIS Inventory — A Municipal Waste Operation is a DEP primary facility type related to the Waste Management Municipal Waste Program. The sub-facility types related to Municipal Waste...

  11. Managing Hanford Site solid waste through strict acceptance criteria

    International Nuclear Information System (INIS)

    Jasen, W.G.; Pierce, R.D.; Willis, N.P.

    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) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

  12. Methodology to remediate a mixed waste site

    Energy Technology Data Exchange (ETDEWEB)

    Berry, J.B.

    1994-08-01

    In response to the need for a comprehensive and consistent approach to the complex issue of mixed waste management, a generalized methodology for remediation of a mixed waste site has been developed. The methodology is based on requirements set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA) and incorporates ``lessons learned`` from process design, remediation methodologies, and remediation projects. The methodology is applied to the treatment of 32,000 drums of mixed waste sludge at the Oak Ridge K-25 Site. Process technology options are developed and evaluated, first with regard to meeting system requirements and then with regard to CERCLA performance criteria. The following process technology options are investigated: (1) no action, (2) separation of hazardous and radioactive species, (3) dewatering, (4) drying, and (5) solidification/stabilization. The first two options were eliminated from detailed consideration because they did not meet the system requirements. A quantitative evaluation clearly showed that, based on system constraints and project objectives, either dewatering or drying the mixed waste sludge was superior to the solidification/stabilization process option. The ultimate choice between the drying and the dewatering options will be made on the basis of a technical evaluation of the relative merits of proposals submitted by potential subcontractors.

  13. Methodology to remediate a mixed waste site

    International Nuclear Information System (INIS)

    Berry, J.B.

    1994-08-01

    In response to the need for a comprehensive and consistent approach to the complex issue of mixed waste management, a generalized methodology for remediation of a mixed waste site has been developed. The methodology is based on requirements set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA) and incorporates ''lessons learned'' from process design, remediation methodologies, and remediation projects. The methodology is applied to the treatment of 32,000 drums of mixed waste sludge at the Oak Ridge K-25 Site. Process technology options are developed and evaluated, first with regard to meeting system requirements and then with regard to CERCLA performance criteria. The following process technology options are investigated: (1) no action, (2) separation of hazardous and radioactive species, (3) dewatering, (4) drying, and (5) solidification/stabilization. The first two options were eliminated from detailed consideration because they did not meet the system requirements. A quantitative evaluation clearly showed that, based on system constraints and project objectives, either dewatering or drying the mixed waste sludge was superior to the solidification/stabilization process option. The ultimate choice between the drying and the dewatering options will be made on the basis of a technical evaluation of the relative merits of proposals submitted by potential subcontractors

  14. 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

  15. The marriage of RCRA and CERCLA at the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Shelton, D.C.; Brooks, L.M.

    1998-01-01

    A key goal of the Rocky Flats Cleanup Agreement (RFCA) signed in July of 1996 was to provide a seamless marriage of the Resource Conservation and Recovery Act (RCRA) (and other media specific programs) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the implementing agencies of each. This paper examines the two years since the signing of RFCA and identifies the successes, failures, and stresses of the marriage. RFCA has provided an excellent vehicle for regulatory and substantive progress at the Department of Energy's Rocky Flats facility. The key for a fully successful marriage is to build on the accomplishments to date and to continually improve the internal and external systems and relationships. To date, the parties can be proud of both the substantial accomplishment of substantive environmental work and the regulatory systems that have enabled the work

  16. 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

  17. 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)

  18. Mixed waste characterization and certification at the Nevada Test Site

    International Nuclear Information System (INIS)

    Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

    1988-01-01

    The Radioactive Waste Management Project at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste. The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B permit application, pertinent DOE guidelines governing waste acceptance criteria and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with ALARA precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

  19. Mixed waste characterization and certification at the Nevada Test Site

    International Nuclear Information System (INIS)

    Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

    1988-01-01

    The Radioactive Waste Management Project (RWMP) at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste (MW). The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B Permit application, pertinent DOE guidelines governing waste acceptance criteria (WAC) and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with as low as reasonably achievable (ALARA) precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

  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. 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. Borehole Data Package for Calendar Year 2001 RCRA Wells at Single-Shell Tank Waste Management Area U

    International Nuclear Information System (INIS)

    Horton, Duane G.

    2002-01-01

    This document provides information on the construction of three new RCRA wells at Waste Management Area U in September 2001. These wells were constructed to the specifications and requirements described in Washington Administrative Codes 173-160 and 173-303. Grab samples for geological description and archive were collected every 5 ft throughout the wells. Borehole and drill cuttings were monitored regularly for organic vapors and radionuclide contaminants. At well 299-W18-40, beta-gamma activity was found to be slightly above background at 120 ft below ground surface. All other measurements were below background. Cesium-137 was found at the ground surface and at 3 ft below ground surface (bgs). No other manmade contamination was found. At well 299-W19-44, no radionuclide contamination was found, but several intervals of high carbon monoxide were detected. Cesium-137 was detected at 3 ft bgs at 0.4 pCi/g. At well 299-W19-45, no radionuclide contamination was found, but several intervals of high carbon monoxide were detected. Cesium-137 was detected near the surface at 0.4 pCi/g. No other manmade radionuclide was detected. At well 299-W19-45, samples for geological description and archive were collected every 5 ft throughout the well. No contamination was noted. Cesium-137 was detected near the surface at 0.4 to 1.4 pCi/g. No other manmade radionuclide was detected

  3. 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

  4. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E.

    1998-10-02

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

  5. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    International Nuclear Information System (INIS)

    Palmer, E.

    1998-01-01

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina

  6. Fast-turnaround RCRA site characterization of former TA-42 at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pratt, A.R.; Gainer, G.M.; Thomson, C.N.; Hutton, R.D.

    1994-01-01

    This report describes the results of an accelerated characterization to evaluate contamination at the site of former Technical Area (TA)-42. This characterization supported the construction validation for the Nuclear Safeguards Technology Laboratory (NSTL), which will be constructed at the site

  7. Development of TRU waste mobile analysis methods for RCRA-regulated metals

    International Nuclear Information System (INIS)

    Mahan, C.A.; Villarreal, R.; Drake, L.; Figg, D.; Wayne, D.; Goldstein, S.

    1998-01-01

    This is the final report of a one-year, Laboratory Directed Research and Development (LDRD) project at Los Alamos National Laboratory (LANL). Glow-discharge mass spectrometry (GD-MS), laser-induced breakdown spectroscopy (LIBS), dc-arc atomic-emission spectroscopy (DC-ARC-AES), laser-ablation inductively-coupled-plasma mass spectrometry (LA-ICP-MS), and energy-dispersive x-ray fluorescence (EDXRF) were identified as potential solid-sample analytical techniques for mobile characterization of TRU waste. Each technology developers was provided with surrogate TRU waste samples in order to develop an analytical method. Following successful development of the analytical method, five performance evaluation samples were distributed to each of the researchers in a blind round-robin format. Results of the round robin were compared to known values and Transuranic Waste Characterization Program (TWCP) data quality objectives. Only two techniques, DC-ARC-AES and EDXRF, were able to complete the entire project. Methods development for GD-MS and LA-ICP-MS was halted due to the stand-down at the CMR facility. Results of the round-robin analysis are given for the EDXRF and DCARC-AES techniques. While DC-ARC-AES met several of the data quality objectives, the performance of the EDXRF technique by far surpassed the DC-ARC-AES technique. EDXRF is a simple, rugged, field portable instrument that appears to hold great promise for mobile characterization of TRU waste. The performance of this technique needs to be tested on real TRU samples in order to assess interferences from actinide constituents. In addition, mercury and beryllium analysis will require another analytical technique because the EDXRF method failed to meet the TWCP data quality objectives. Mercury analysis is easily accomplished on solid samples by cold vapor atomic fluorescence (CVAFS). Beryllium can be analyzed by any of a variety of emission techniques

  8. 75 FR 43478 - Rhode Island: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-07-26

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental.... Mail: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07... Delivery or Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  9. 75 FR 35720 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-06-23

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07-1... Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  10. HWMA/RCRA Closure Plan for the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System

    International Nuclear Information System (INIS)

    K. Winterholler

    2007-01-01

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex (RTC), Idaho National Laboratory Site, to meet a further milestone established under the Voluntary Consent Order SITE-TANK-005 Action Plan for Tank System TRA-009. The tank system to be closed is identified as VCO-SITE-TANK-005 Tank System TRA-009. This closure plan presents the closure performance standards and methods for achieving those standards

  11. Two practical incineration-alternative prototype demonstrations for TSCA and RCRA wastes

    International Nuclear Information System (INIS)

    Coogan, J.J.; Kang, M.; Rosocha, L.A.; Tennant, R.A.; Cage, M.R.; Gill, J.T.

    1994-01-01

    Results from two pilot-scale demonstrations will be presented. The first was performed at the DOE's Savannah River Site where a trailer mounted silent discharge plasma (SDP) system was used to destroy hazardous compounds from the off-gas stream of a soil vapor extraction system. In the second, pilot-plant tests of a two-stage, combined packed-bed silent discharge plasma (PBR/SDP) treatment process were performed for PCB surrogates contained in both kerosene and hydraulic fluid

  12. 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

  13. 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

  14. Nuclear waste disposal site

    International Nuclear Information System (INIS)

    Mallory, C.W.; Watts, R.E.; Sanner, W.S. Jr.; Paladino, J.B.; Lilley, A.W.; Winston, S.J.; Stricklin, B.C.; Razor, J.E.

    1988-01-01

    This patent describes a disposal site for the disposal of toxic or radioactive waste, comprising: (a) a trench in the earth having a substantially flat bottom lined with a layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for obstructing any capillary-type flow of ground water to the interior of the trench; (b) a non-rigid, radiation-blocking cap formed from a first layer of alluvium, a second layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for blocking any capillary-type flow of water between the layer of alluvium and the rest of the cap, a layer of water-shedding silt for directing surface water away from the trench, and a layer of rip-rap over the silt layer for protecting the silt layer from erosion and for providing a radiation barrier; (c) a solidly-packed array of abutting modules of uniform size and shape disposed in the trench and under the cap for both encapsulating the wastes from water and for structurally supporting the cap, wherein each module in the array is slidable movable in the vertical direction in order to allow the array of modules to flexibly conform to variations in the shape of the flat trench bottom caused by seismic disturbances and to facilitate the recoverability of the modules; (d) a layer of solid, fluent, coarse, granular materials having a high hydraulic conductivity in the space between the side of the modules and the walls of the trench for obstructing any capillary-type flow of ground water to the interior of the trench; and (e) a drain and wherein the layer of silt is sloped to direct surface water flowing over the cap into the drain

  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. 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

  17. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2008-01-01

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells

  18. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2008-09-01

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

  19. The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    Roberts, R.J.

    1991-01-01

    The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab

  20. 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

  1. 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

  2. Hydrogeologic data for science trench boreholes at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    1993-12-01

    A program to conduct drilling, sampling, and laboratory testing was designed and implemented to obtain important physical, geochemical, and hydrologic property information for the near surface portion of thick unsaturated alluvial sediments at the Area 5 Radioactive Waste Management Site (RWMS). These data are required to understand and simulate infiltration and redistribution of water as well as the transport of solutes in the immediate vicinity of existing and future low-level, mixed, and high-specific-activity waste disposal cells at the site. The program was designed specifically to meet data needs associated with a Resource Conservation and Recovery Act (RCRA) Part B permit application for disposal of hazardous mixed waste, possible RCRA waivers involving mixed waste, DOE Order 5820.2A, ''Radioactive Waste Management,'' and 40 Code of Federal Regulations (CFR) 191 requirements for land disposal of radioactive waste. The hydrologic condition data, when combined with hydrologic property data, indicate that very little net liquid flow (if any) is occurring in the upper vadose zone, and the direction of movement is upward. It follows that vapor movement is probably the dominant mechanism of water transport in this upper region, except immediately following precipitation events

  3. Hanford Site Waste Management Plan

    International Nuclear Information System (INIS)

    1988-12-01

    The Hanford Site Waste Management Plan (HWMP) was prepared in accordance with the outline and format described in the US Department of Energy Orders. The HWMP presents the actions, schedules, and projected costs associated with the management and disposal of Hanford defense wastes, both radioactive and hazardous. The HWMP addresses the Waste Management Program. It does not include the Environmental Restoration Program, itself divided into the Environmental Restoration Remedial Action Program and the Decontamination and Decommissioning Program. The executive summary provides the basis for the plans, schedules, and costs within the scope of the Waste Management Program at Hanford. It summarizes fiscal year (FY) 1988 including the principal issues and the degree to which planned activities were accomplished. It further provides a forecast of FY 1989 including significant milestones. Section 1 provides general information for the Hanford Site including the organization and administration associated with the Waste Management Program and a description of the Site focusing on waste management operations. Section 2 and Section 3 describe radioactive and mixed waste management operations and hazardous waste management, respectively. Each section includes descriptions of the waste management systems and facilities, the characteristics of the wastes managed, and a discussion of the future direction of operations

  4. 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.

  5. Hanford site waste tank characterization

    International Nuclear Information System (INIS)

    De Lorenzo, D.S.; Simpson, B.C.

    1994-08-01

    This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order

  6. Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL2A

    Energy Technology Data Exchange (ETDEWEB)

    WINTERHALDER, J.A.

    1999-09-29

    This hazardous waste determination report (Report) describes the process and information used on the Hanford Site to determine that waste stream number NPFPDLZA, consisting of 30 containers of contact-handled transuranic debris waste, is not hazardous waste regulated by the Resource Conservation and Recovery Act (RCRA) or the New Mexico Hazardous Waste Act. For a waste to be hazardous under these statutes, the waste either must be specifically listed as a hazardous waste, or exhibit one or more of the characteristics of a hazardous waste, Le., ignitability, corrosivity, reactivity, or toxicity. Waste stream NPFPDLZA was generated, packaged, and placed into storage between 1993 and 1997. Extensive knowledge of the waste generating process, facility operational history, and administrative controls and operating procedures in effect at the time of generation, supported the initial nonhazardous waste determination. Because of the extent and reliability of information pertaining to this waste type, and the total volume of waste in the debris matrix parameter category, the Hanford Site is focusing initial efforts on this and similar waste streams for the first shipment to the Waste Isolation Pilot Plant (WIPP). RCRA regulations authorize hazardous waste determinations to be made either by using approved sampling and analysis methods or by applying knowledge of the waste in light of the materials or the process(es) used. This latter approach typically is referred to as process knowledge. The Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) for WIPP refers to acceptable knowledge in essentially the same terms; acceptable knowledge as used throughout this Report is synonymous with the term process knowledge. The 30 containers addressed in this Report were characterized by the following methods: Acceptable knowledge; Nondestructive examination using real-time radiography; Visual examination; and Headspace gas sampling and analysis. The initial

  7. Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL2A

    International Nuclear Information System (INIS)

    WINTERHALDER, J.A.

    1999-01-01

    This hazardous waste determination report (Report) describes the process and information used on the Hanford Site to determine that waste stream number NPFPDLZA, consisting of 30 containers of contact-handled transuranic debris waste, is not hazardous waste regulated by the Resource Conservation and Recovery Act (RCRA) or the New Mexico Hazardous Waste Act. For a waste to be hazardous under these statutes, the waste either must be specifically listed as a hazardous waste, or exhibit one or more of the characteristics of a hazardous waste, Le., ignitability, corrosivity, reactivity, or toxicity. Waste stream NPFPDLZA was generated, packaged, and placed into storage between 1993 and 1997. Extensive knowledge of the waste generating process, facility operational history, and administrative controls and operating procedures in effect at the time of generation, supported the initial nonhazardous waste determination. Because of the extent and reliability of information pertaining to this waste type, and the total volume of waste in the debris matrix parameter category, the Hanford Site is focusing initial efforts on this and similar waste streams for the first shipment to the Waste Isolation Pilot Plant (WIPP). RCRA regulations authorize hazardous waste determinations to be made either by using approved sampling and analysis methods or by applying knowledge of the waste in light of the materials or the process(es) used. This latter approach typically is referred to as process knowledge. The Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) for WIPP refers to acceptable knowledge in essentially the same terms; acceptable knowledge as used throughout this Report is synonymous with the term process knowledge. The 30 containers addressed in this Report were characterized by the following methods: Acceptable knowledge; Nondestructive examination using real-time radiography; Visual examination; and Headspace gas sampling and analysis. The initial

  8. Old radioactive waste storage sites

    International Nuclear Information System (INIS)

    2008-01-01

    After a recall of the regulatory context for the management of old sites used for the storage of radioactive wastes with respect with their activity, the concerned products, the disposal or storage type, this document describes AREVA's involvement in the radioactive waste management process in France. Then, for the different kinds of sites (currently operated sites having radioactive waste storage, storage sites for uranium mineral processing residues), it indicates their location and name, their regulatory status and their control authority, the reference documents. It briefly presents the investigation on the long term impact of uranium mineral processing residues on health and environment, evokes some aspects of public information transparency, and presents the activities of an expertise group on old uranium mines. The examples of the sites of Bellezane (uranium mineral processing residues) and COMURHEX Malvesi (assessment of underground and surface water quality at the vicinity of this installation) are given in appendix

  9. 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

  10. Characterization of Vadose Zone Sediment: RCRA Borehole 299-E33-338 Located Near the B-BX-BY Waste Management Area

    Energy Technology Data Exchange (ETDEWEB)

    Lindenmeier, Clark W.; Serne, R. Jeffrey; Bjornstad, Bruce N.; Gee, Glendon W.; Schaef, Herbert T.; Lanigan, David C.; Lindberg, Michael J.; Clayton, Ray E.; Legore, Virginia L.; Kutnyakov, Igor V.; Baum, Steven R.; Geiszler, Keith N.; Brown, Christopher F.; Valenta, Michelle M.; Vickerman, Tanya S.; Royack, Lisa J.

    2008-09-11

    This report was revised in September 2008 to remove acid-extractable sodium data from Table 4.8. The sodium data was removed due to potential contamination introduced during the acid extraction process. The rest of the text remains unchanged from the original report issued in June 2003. The overall goals of the of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., are: 1) to define risks from past and future single-shell tank farm activities, 2) to identify and evaluate the efficacy of interim measures, and 3) to aid via collection of geotechnical information and data, future decisions that must be made by the U.S. Department of Energy (DOE) regarding the near-term operations, future waste retrieval, and final closure activities for the single-shell tank waste management areas. For a more complete discussion of the goals of the Tank Farm Vadose Zone Project, see the overall work plan, Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for the Single-Shell Tank Waste Management Areas (DOE 1999). Specific details on the rationale for activities performed at the B-BX-BY tank farm waste management area are found in CH2M HILL (2000).

  11. RCRA facility investigation/corrective measures study work plan for the 200-UP-2 Operable Unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1993-06-01

    The 200-UP-2 Operable Unit is one of two source operable units at the U Plant Aggregate Area at the Hanford Site. Source operable units include waste management units and unplanned release sites that are potential sources of radioactive and/or hazardous substance contamination. This work plan, while maintaining the title RFI/CMS, presents the background and direction for conducting a limited field investigation in the 200-UP-2 Operable Unit, which is the first part of the process leading to final remedy selection. This report discusses the background, prior recommendations, goals, organization, and quality assurance for the 200-UP-2 Operable Unit Work Plan. The discussion begins with a summary of the regulatory framework and the role of the work plan. The specific recommendations leading into the work plan are then addressed. Next, the goals and organization of the report are discussed. Finally, the quality assurance and supporting documentation are presented

  12. 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

  13. 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.

  14. 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.

  15. 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

  16. The Mixed Waste Management Facility closure and expansion at the Savannah River Site

    International Nuclear Information System (INIS)

    Bittner, M.F.; Frye-O'Bryant, R.C.

    1992-01-01

    Process wastes containing radioactive and hazardous constituents have been generated throughout the operational history of the Savannah River Site. Solid wastes containing low level radionuclides were buried in Low Level Radioactive Disposal Facility (LLRWDF). Until 1986, waste containing lead and cadmium was disposed of in the Mixed Waste Management Facility (MWMF) portion of LLRWDF. Between 1986 and 1990, waste containing F-listed hazardous rags were buried. Current Resource Conservation and Recovery Act (RCRA) regulations prohibit the disposal of these hazardous wastes at nonpermitted facilities. This paper describes the closure activities for the MWMF, completed in 1990 and plans proposed for the expansion of this closure to include the LLRWDF suspect solvent rag trenches

  17. Cementation and solidification of miscellaneous mixed wastes at the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Phillips, J.A.; Semones, G.B.

    1995-01-01

    The Rocky Flats Environmental Technology Site produces a variety of wastes which are amenable to micro-encapsulation in cement Portland cement is an inexpensive and readily available material for this application. The Waste Projects (WP) group at Rocky Flats evaluated cementation to determine its effectiveness in encapsulating several wastes. These included waste analytical laboratory solutions, incinerator ash, hydroxide precipitation sludge, and an acidic solution from the Delphi process (a chemical oxidation technology being evaluated as an alternative to incineration). WP prepared surrogate wastes and conducted designed experiments to optimize the cement formulation for the waste streams. These experiments used a Taguchi or factorial experimental design, interactions between the variables were also considered in the testing. Surrogate waste samples were spiked with various levels of each of six Resource Conservation and Recovery Act (RCRA) listed metals (Cd, Cr, Ba, Pb, Ni, and Ag), cemented using the optimized formulation, and analyzed for leach resistance using the Toxicity Characteristic Leaching Procedure (TCLP). The metal spike levels chosen were based on characterization data, and also based on an estimate of the highest levels of contaminants suspected in the waste. This paper includes laboratory test results for each waste studied. These include qualitative observations as well as quantitative data from TCLP analyses and environmental cycling studies. The results from these experiments show that cement stabilization of the different wastes can produce final waste forms which meet the current RCRA Land Disposal Restriction (LDR) requirements. Formulations that resulted in LDR compliant waste forms are provided. The volume increases associated with cementation are also lower than anticipated. Future work will include verification studies with actual mixed radioactive waste as well as additional formulation development studies on other waste streams

  18. Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation

  19. Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation.

  20. 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

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

    OpenAIRE

    Mohammad Hasan Ehrampoush; Mohsen Hesami Arani; Mohammad Taghi Ghaneian; Asghar Ebrahimi; Masoud Shafiee

    2016-01-01

    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 Me...

  2. 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

  3. 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

  4. Results of Phase I groundwater quality assessment for single-shell tank waste management Area S-SX at the Hanford Site

    International Nuclear Information System (INIS)

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

    1998-01-01

    Pacific Northwest National Laboratory (PNNL) conducted a Phase I, Resource Conservation and Recovery Act of 1976 (RCRA) groundwater quality assessment for the Richland Field Office of the U.S. Department of Energy (DOE-RL), in accordance with the Federal Facility Compliance Agreement. The purpose of the investigation was to determine if the Single-Shell Tank Waste Management Area (WMA) S-SX has impacted groundwater quality. The WMA is located in the southern portion of the 200 West Area of the Hanford Site and consists of the 241-S and 241-SX tank farms and ancillary waste systems. The unit is regulated under RCRA interim-status regulations (40 CFR 265, Subpart F) and was placed in assessment groundwater monitoring (40 CFR 265.93 [d]) in August 1996 because of elevated specific conductance and technetium-99, a non-RCRA co-contaminant, in downgradient monitoring wells. Major findings of the assessment are summarized below: (1) Distribution patterns for radionuclides and RCRA/dangerous waste constituents indicate WMA S-SX has contributed to groundwater contamination observed in downgradient monitoring wells. (2) Drinking water standards for nitrate and technetium-99 are currently exceeded in one RCRA-compliant well (299-W22-46) located at the southeastern comer of the SX tank farm. (3) Technetium-99, nitrate, and chromium concentrations in downgradient well 299-W22-46 (the well with the highest current concentrations) appear to be declining after reaching maximum concentrations in May 1997. (4) Cesium-137 and strontium-90, major constituents of concern in single-shell tank waste, were not detected in any of the RCRA-compliant wells in the WMA network, including the well with the highest current technetium-99 concentrations (299-W22-46). (5) Low but detectable strontium-90 and cesium-137 were found in one old well (2-W23-7), located inside and between the S and SX tank farms

  5. 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.

  6. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    International Nuclear Information System (INIS)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-01-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

  7. Hanford Site Tank Waste Remediation System

    International Nuclear Information System (INIS)

    1993-05-01

    The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

  8. 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.

  9. 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)

  10. Hanford Site Transuranic (TRU) Waste Certification Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

  11. Hanford Site Transuranic (TRU) Waste Certification Plan

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    1999-09-09

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

  12. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

    1999-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

  13. Hazardous waste sites and housing appreciation rates

    OpenAIRE

    McCluskey, Jill Jennifer; Rausser, Gordon C

    2000-01-01

    The dynamic effect of a hazardous waste site is analyzed by investigating the causal relationship between housing appreciation rates and house location in relation to a hazardous waste site using resale data from individual sales transactions in Dallas County, Texas. The results indicate that in the period in which the hazardous waste site was identified and cleanup occurred, residential property owners in close proximity to the hazardous waste site experienced lower housing appreciation rate...

  14. Modified TCLP test for evaluating the leachability of site-specific wastes

    International Nuclear Information System (INIS)

    Pier, J.

    1996-01-01

    The Weldon Spring Site Remedial Action Project (WSSRAP) has developed a site-specific test to assess the leachability of wastes that will be placed in its on-site disposal cell. This test is modelled after the TCLP, but examines an expanded list of parameters and uses an extraction solution that is representative of conditions that are expected to exist in the disposal facility. Following the same logic that guided development of TCLP protocols, the WSSRAP developed concentration guidelines for non-TCLP parameters that were contaminants of concern in its wastes. Response actions, specific to the WSSRAP cell and wastes, were also developed to address constituents that failed to meet these guides. From 1955 to 1966, the US Atomic Energy Commission operated a uranium feed materials plant on this site. Nitroaromatic, and later, radiological wastes were disposed of in the quarry from 1945 until 1970. This paper describes testing to determine whether contaminant concentrations in leachates derived from the major waste-types that will be placed in its on-site disposal cell conform with the Department of Energy's (DOE) as low as reasonably achievable (ALARA) policy. Although the WSSRAP will continue to use the TCLP test to determine if any waste is classified RCRA-hazardous, the site-specific test described in this paper will be used to further assess whether leachate from any waste-type has the potential to adversely impact groundwater

  15. 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

  16. Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation, and amount of waste.

  17. Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste

  18. Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation

  19. Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation, and amount of waste

  20. Hanford Site annual dangerous waste report: Volume 3, Part 2, Waste Management Facility report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1944-12-31

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling and containment vessel, waste number, waste designation and amount of waste.

  1. Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information on hazardous materials at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation

  2. Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    This report contains information on hazardous materials at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation.

  3. 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

  4. 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 data and information related to remedial investigation studies for Oak Ridge National Laboratory (ORNL). Information is included on a soil gas survey, surface radiological investigations of waste areas, and well installation for ground water monitoring

  5. 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

  6. Hanford Site Waste management units report

    International Nuclear Information System (INIS)

    1992-01-01

    This report summarizes the operable units in several areas of the Hanford Site Waste Facility. Each operable unit has several waste units (crib, ditch, pond, etc.). The operable units are summarized by describing each was unit. Some of the descriptions are unit name, unit type, waste category start data, site description, etc. The descriptions will vary for each waste unit in each operable unit and area of the Hanford Site

  7. 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

  8. 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.

  9. 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

  10. 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

  11. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Willis, N.P.; Triner, G.C.

    1991-09-01

    Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

  12. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

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

    2005-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

  13. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    Energy Technology Data Exchange (ETDEWEB)

    NNSA/NSO Waste Management Project

    2008-06-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  14. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    International Nuclear Information System (INIS)

    NNSA/NSO Waste Management Project

    2008-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

  15. Hazardous waste operational plan for site 300

    International Nuclear Information System (INIS)

    Roberts, R.S.

    1982-01-01

    This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department

  16. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  17. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2010-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  18. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  19. 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

  20. 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

  1. Hanford Site Solid Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  2. Hanford Site Solid Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    1993-01-01

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

  3. Managing soil moisture on waste burial sites

    International Nuclear Information System (INIS)

    Anderson, J.E.; Ratzlaff, T.D.

    1991-11-01

    Shallow land burial is a common method of disposing of industrial, municipal, and low-level radioactive waste. The exclusion of water from buried wastes is a primary objective in designing and managing waste disposal sites. If wastes are not adequately isolated, water from precipitation may move through the landfill cover and into the wastes. The presence of water in the waste zone may promote the growth of plant roots to that depth and result in the transport of toxic materials to above-ground foliage. Furthermore, percolation of water through the waste zone may transport contaminants into ground water. This report presents results from a field study designed to assess the the potential for using vegetation to deplete soil moisture and prevent water from reaching buried wastes at the Idaho National Engineering Laboratory (INEL). Our results show that this approach may provide an economical means of limiting the intrusion of water on waste sites

  4. 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)

  5. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-16

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  6. Hanford site transuranic waste certification plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP)

  7. 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

  8. Hanford Site Waste Management Units Report

    Energy Technology Data Exchange (ETDEWEB)

    Shearer, Jeffrey P. [Hanford Site (HNF), Richland, WA (United States)

    2012-02-29

    The Hanford Site Waste Management Units Report (HSWMUR) has been created to meet the requirements of the Tri-Party Agreement (TPA) Action Plan, Section 3.5, which states: “The Hanford Site Waste Management Units Report shall be generated, in a format agreed upon by the Parties, as a calendar year report and issued annually by the DOE by the end of February of each year, and posted electronically for regulator and public access. This report shall reflect all changes made in waste management unit status during the previous year.” This February 2012 version of the HSWMUR contains a comprehensive inventory of the 3389 sites and 540 subsites in the Waste Information Data System (WIDS). The information for each site contains a description of each unit and the waste it contains, where applicable. The WIDS database provides additional information concerning the sites contained in this report and is maintained with daily changes to these sites.

  9. Hanford Site Waste Management Units Report

    Energy Technology Data Exchange (ETDEWEB)

    Shearer, Jeffrey P. [Hanford Site (HNF), Richland, WA (United States)

    2013-02-13

    The Hanford Site Waste Management Units Report (HSWMUR) has been created to meet the requirements of the Tri-Party Agreement (TPA) Action Plan, Section 3.5, which states: “The Hanford Site Waste Management Units Report shall be generated, in a format agreed upon by the Parties, as a calendar year report and issued annually by the DOE by the end of February of each year, and posted electronically for regulator and public access. This report shall reflect all changes made in waste management unit status during the previous year.” This February 2013 version of the HSWMUR contains a comprehensive inventory of the 3427 sites and 564 subsites in the Waste Information Data System (WIDS). The information for each site contains a description of each unit and the waste it contains, where applicable. The WIDS database provides additional information concerning the sites contained in this report and is maintained with daily changes to these sites.

  10. Hanford Site Waste Management Units Report

    Energy Technology Data Exchange (ETDEWEB)

    Shearer, Jeffrey P. [Hanford Site (HNF), Richland, WA (United States)

    2014-02-19

    The Hanford Site Waste Management Units Report (HSWMUR) has been created to meet the requirements of the Tri-Party Agreement (TPA) Action Plan, Section 3.5, which states: “The Hanford Site Waste Management Units Report shall be generated, in a format agreed upon by the Parties, as a calendar year report and issued annually by the DOE by the end of February of each year, and posted electronically for regulator and public access. This report shall reflect all changes made in waste management unit status during the previous year.” This February 2013 version of the HSWMUR contains a comprehensive inventory of the 3438 sites and 569 subsites in the Waste Information Data System (WIDS). The information for each site contains a description of each unit and the waste it contains, where applicable. The WIDS database provides additional information concerning the sites contained in this report and is maintained with daily changes to these sites.

  11. 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 describes the borehole geophysical logging performed at selected monitoring wells at waste area grouping (WAG) 6 of Oak Ridge National Laboratory in support of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI). It identifies the locations and describes the methods, equipment used in the effort, and the results of the activity. The actual logs for each well logged are presented in Attachment 1 through 4 of the TM. Attachment 5 provide logging contractor service literature and Attachment 6 is the Oak Ridge National Laboratory (ORNL) Procedure for Control of a Nuclear Source Utilized in Geophysical logging. The primary objectives of the borehole geophysical logging program were to (1) identify water-bearing fractured bedrock zones to determine the placement of the screen and sealed intervals for subsequent installation, and (2) further characterize local bedrock geology and hydrogeology and gain insight about the deeper component of the shallow bedrock aquifer flow system. A secondary objective was to provide stratigraphic and structural correlations with existing logs for Hydraulic Head Monitoring Station (HHMS) wells, which display evidence of faulting

  12. The Drigg low-level waste site

    International Nuclear Information System (INIS)

    1992-01-01

    Safe disposal of waste is a vital aspect of any industrial operation whether it be production of plastics, steel or chemicals or handling of radioactive materials. Appropriate methods must be used in every case. Radioactive waste falls into three distinct categories - high, intermediate and low-level. It is the solid low-level waste making up over 90% of the total which this booklet discusses. British Nuclear Fuels plc (BNFL) operates a site for the disposal of solid low-level waste at Driggs, some six kilometres south of Sellafield in West Cumbria. The daily operations and control of the site, the responsibility of the BNFL Waste Management Unit is described. (author)

  13. 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

  14. Hanford Site annual waste reduction report

    International Nuclear Information System (INIS)

    Nichols, D.H.

    1992-03-01

    The US Department of Energy (DOE), Richland Field Office (RL) has developed and implemented a Hanford Site Waste Minimization and Pollution Prevention Awareness Plan that provides overall guidance and direction on waste minimization and pollution prevention awareness to the four contractors who manage and operate the Hanford Site for the RL. Waste reduction at the RL will be accomplished by following a hierarchy of environmental protection practices. First, waste generation will be eliminated or minimized through source reduction. Second, potential waste materials that cannot be eliminated or minimized will be recycled (i.e., used, reused, or reclaimed). Third, all waste that is nevertheless generated will be treated to reduce volume, toxicity, or mobility before storage or disposal. The scope of this waste reduction program will include nonhazardous, hazardous, radioactive mixed, and radioactive wastes

  15. 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

  16. Engineering study of 50 miscellaneous inactive underground radioactive waste tanks located at the Hanford Site, Washington

    International Nuclear Information System (INIS)

    Freeman-Pollard, J.R.

    1994-01-01

    This engineering study addresses 50 inactive underground radioactive waste tanks. The tanks were formerly used for the following functions associated with plutonium and uranium separations and waste management activities in the 200 East and 200 West Areas of the Hanford Site: settling solids prior to disposal of supernatant in cribs and a reverse well; neutralizing acidic process wastes prior to crib disposal; receipt and processing of single-shell tank (SST) waste for uranium recovery operations; catch tanks to collect water that intruded into diversion boxes and transfer pipeline encasements and any leakage that occurred during waste transfer operations; and waste handling and process experimentation. Most of these tanks have not been in use for many years. Several projects have, been planned and implemented since the 1970's and through 1985 to remove waste and interim isolate or interim stabilize many of the tanks. Some tanks have been filled with grout within the past several years. Responsibility for final closure and/or remediation of these tanks is currently assigned to several programs including Tank Waste Remediation Systems (TWRS), Environmental Restoration and Remedial Action (ERRA), and Decommissioning and Resource Conservation and Recovery Act (RCRA) Closure (D ampersand RCP). Some are under facility landlord responsibility for maintenance and surveillance (i.e. Plutonium Uranium Extraction [PUREX]). However, most of the tanks are not currently included in any active monitoring or surveillance program

  17. Solid waste management complex site development plan

    International Nuclear Information System (INIS)

    Greager, T.M.

    1994-01-01

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated

  18. Solid waste management complex site development plan

    Energy Technology Data Exchange (ETDEWEB)

    Greager, T.M.

    1994-09-30

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated.

  19. 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

  20. 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.

  1. Hanford Site Solid Waste Landfill permit application

    International Nuclear Information System (INIS)

    1991-01-01

    Daily activities at the Hanford Site generate sanitary solid waste (nonhazardous and nonradioactive) that is transported to and permanently disposed of at the Hanford Site Solid Waste Landfill. This permit application describes the manner in which the solid Waste Landfill will be operated under Washington State Department of Ecology Minimum Functional Standards for Solid Waste Handling, Washington Administrative Code 173-304. The solid Waste Landfill is owned by the US Department of Energy -- Richland Operations Office and is used for disposal of solid waste generated at the US Department of Energy Hanford Site. The jurisdictional health department's permit application form for the Solid Waste Landfill is provided in Chapter 1.0. Chapter 2.0 provides a description of the Hanford Site and the Solid Waste Landfill and reviews applicable locational, general facility, and landfilling standards. Chapter 3.0 discusses the characteristics and quantity of the waste disposed of in the Solid Waste Landfill. Chapter 4.0 reviews the regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill. Chapters 5.0, 6.0, and 7.0 contain the plan of operation, closure plan, and postclosure plan, respectively. The plan of operation describes the routine operation and maintenance of the Solid Waste Landfill, the environmental monitoring program, and the safety and emergency plans. Chapter 5.0 also addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The postclosure plan describes requirements for final cover maintenance and environmental monitoring equipment following final closure. Chapter 8.0 discusses the integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill. 76 refs., 48 figs, 15 tabs

  2. Site identification presentation: Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1979-11-01

    The final step in the site identification process for the Basalt Waste Isolation Project is described. The candidate sites are identified. The site identification methodology is presented. The general objectives which must be met in selecting the final site are listed. Considerations used in the screening process are also listed. Summary tables of the guidelines used are included

  3. Vitrification technology for Hanford Site tank waste

    International Nuclear Information System (INIS)

    Weber, E.T.; Calmus, R.B.; Wilson, C.N.

    1995-04-01

    The US Department of Energy's (DOE) Hanford Site has an inventory of 217,000 m 3 of nuclear waste stored in 177 underground tanks. The DOE, the US Environmental Protection Agency, and the Washington State Department of Ecology have agreed that most of the Hanford Site tank waste will be immobilized by vitrification before final disposal. This will be accomplished by separating the tank waste into high- and low-level fractions. Capabilities for high-capacity vitrification are being assessed and developed for each waste fraction. This paper provides an overview of the program for selecting preferred high-level waste melter and feed processing technologies for use in Hanford Site tank waste processing

  4. Waste reduction at the Savannah River Site

    International Nuclear Information System (INIS)

    Stevens, W.E.; Lee, R.A.; Reynolds, R.W.

    1990-01-01

    The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities

  5. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2012-02-28

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  6. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2012-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  7. Waste minimization applications at a remediation site

    International Nuclear Information System (INIS)

    Allmon, L.A.

    1995-01-01

    The Fernald Environmental Management Project (FEMP) owned by the Department of Energy was used for the processing of uranium. In 1989 Fernald suspended production of uranium metals and was placed on the National Priorities List (NPL). The site's mission has changed from one of production to environmental restoration. Many groups necessary for producing a product were deemed irrelevant for remediation work, including Waste Minimization. Waste Minimization does not readily appear to be applicable to remediation work. Environmental remediation is designed to correct adverse impacts to the environment from past operations and generates significant amounts of waste requiring management. The premise of pollution prevention is to avoid waste generation, thus remediation is in direct conflict with this premise. Although greater amounts of waste will be generated during environmental remediation, treatment capacities are not always available and disposal is becoming more difficult and costly. This creates the need for pollution prevention and waste minimization. Applying waste minimization principles at a remediation site is an enormous challenge. If the remediation site is also radiologically contaminated it is even a bigger challenge. Innovative techniques and ideas must be utilized to achieve reductions in the amount of waste that must be managed or dispositioned. At Fernald the waste minimization paradigm was shifted from focusing efforts on source reduction to focusing efforts on recycle/reuse by inverting the EPA waste management hierarchy. A fundamental difference at remediation sites is that source reduction has limited applicability to legacy wastes but can be applied successfully on secondary waste generation. The bulk of measurable waste reduction will be achieved by the recycle/reuse of primary wastes and by segregation and decontamination of secondary wastestreams. Each effort must be measured in terms of being economically and ecologically beneficial

  8. 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

  9. 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.

  10. 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.

  11. Technologies to remediate hazardous waste sites

    International Nuclear Information System (INIS)

    Falco, J.W.

    1990-03-01

    Technologies to remediate hazardous wastes must be matched with the properties of the hazardous materials to be treated, the environment in which the wastes are imbedded, and the desired extent of remediation. Many promising technologies are being developed, including biological treatment, immobilization techniques, and in situ methods. Many of these new technologies are being applied to remediate sites. The management and disposal of hazardous wastes is changing because of federal and state legislation as well as public concern. Future waste management systems will emphasize the substitution of alternatives for the use of hazardous materials and process waste recycling. Onsite treatment will also become more frequently adopted. 5 refs., 7 figs

  12. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Ellefson, M.D.

    1998-01-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

  13. Geohydrology of industrial waste disposal site

    International Nuclear Information System (INIS)

    Gaynor, R.K.

    1984-01-01

    An existing desert site for hazardous chemical and low-level radioactive waste disposal is evaluated for suitability. This site is characterized using geologic, geohydrologic, geochemical, and other considerations. Design and operation of the disposal facility is considered. Site characteristics are also evaluated with respect to new and proposed regulatory requirements under the Resource Conservation and Recovery Act (1976) regulations, 40 CFR Part 264, and the ''Licensing Requirements for Landfill Disposal of Radioactive Waste,'' 10 CRF Part 61. The advantages and disadvantages of siting new disposal facilities in similar desert areas are reviewed and contrasted to siting in humid locations

  14. 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

  15. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  16. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2013-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  17. 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

  18. 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

  19. Historical genesis of Hanford Site wastes

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1991-01-01

    This paper acquaints the audience with historical waste practices and policies as they changed over the years at the Hanford Site, and with the generation of the major waste streams of concern in Hanford Site clean-up today. The paper also describes the founding and basic operating history of the Hanford Site, including World War 11 construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), and some past suggestions and efforts to chemically treat, open-quotes fractionate,close quotes and/or immobilize Hanford's wastes. Recent events, including the designation of the Hanford Site as the open-quotes flagshipclose quotes of Department of Energy (DOE) waste remediation efforts and the signing of the landmark Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), have generated new interest in Hanford's history. Clean-up milestones dictated in this agreement demand information about how, when, in what quantities and mixtures, and under what conditions, Hanford Site wastes were generated and released. This paper presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

  20. Annual Waste Minimization Summary Report for the National Nuclear Security Administration Nevada Site Office

    International Nuclear Information System (INIS)

    Alfred J. Karns

    2007-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U. S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during CY06. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit ((number s ign)NEV HW0021) and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the DOE, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by the NNSA/NSO and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  1. 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

  2. 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

  3. 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

  4. 78 FR 25678 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Gwendolyn Gleaton, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA...

  5. 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

  6. Treatment of M-area mixed wastes at the Savannah River Site

    International Nuclear Information System (INIS)

    1994-06-01

    The Department of Energy has prepared this environmental assessment, DOE/EA-0918, to assess the potential environmental impacts of the treatment of mixed wastes currently stored in the M-Area at the Savannah River Site, near Aiken, South Carolina. DOE is proposing to treat and stabilize approximately 700,000 gallons of mixed waste currently stored in the Interim Treatment/Storage Facility (IT/SF) and Mixed Waste Storage Shed (MWSS). This waste material is proposed to be stabilized using a vitrification process and temporarily stored until final disposal is available by the year 2005. This document has been prepared to assess the potential environmental impacts attributable to the treatment and stabilization of M-area mixed wastes, the closure of the interim storage area, and storage of the vitrified waste until disposal in onsite RCRA vaults. Based on the analyses in the environmental assessment, the Department of Energy has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department of Energy is issuing this finding of no significant impact

  7. 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.

  8. 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

  9. Nevada Test Site Waste Acceptance Criteria, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

  10. Nevada Test Site Waste Acceptance Criteria, December 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

  11. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 5, Technical Memorandums 06-09A, 06-10A, and 06-12A

    Energy Technology Data Exchange (ETDEWEB)

    None

    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).

  12. 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

  13. 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

  14. Disposal of Hanford site tank wastes

    International Nuclear Information System (INIS)

    Kupfer, M.J.

    1993-09-01

    Between 1943 and 1986, 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs) were built and used to store radioactive wastes generated during reprocessing of irradiated uranium metal fuel elements at the U.S. Department of Energy (DOE) Hanford Site in Southeastern Washington state. The 149 SSTs, located in 12 separate areas (tank farms) in the 200 East and 200 West areas, currently contain about 1.4 x 10 5 m 3 of solid and liquid wastes. Wastes in the SSTs contain about 5.7 x 10 18 Bq (170 MCi) of various radionuclides including 90 Sr, 99 Tc, 137 Cs, and transuranium (TRU) elements. The 28 DSTs also located in the 200 East and West areas contain about 9 x 10 4 m 3 of liquid (mainly) and solid wastes; approximately 4 x 10 18 Bq (90 MCi) of radionuclides are stored in the DSTs. Important characteristics and features of the various types of SST and DST wastes are described in this paper. However, the principal focus of this paper is on the evolving strategy for final disposal of both the SST and DST wastes. Also provided is a chronology which lists key events and dates in the development of strategies for disposal of Hanford Site tank wastes. One of these strategies involves pretreatment of retrieved tank wastes to separate them into a small volume of high-level radioactive waste requiring, after vitrification, disposal in a deep geologic repository and a large volume of low-level radioactive waste which can be safely disposed of in near-surface facilities at the Hanford Site. The last section of this paper lists and describes some of the pretreatment procedures and processes being considered for removal of important radionuclides from retrieved tank wastes

  15. Hazardous waste disposal sites: Report 2

    International Nuclear Information System (INIS)

    1979-12-01

    Arkansas, like virtually every other state, is faced with a deluge of hazardous waste. There is a critical need for increased hazardous waste disposal capacity to insure continued industrial development. Additionally, perpetual maintenance of closed hazardous waste disposal sites is essential for the protection of the environment and human health. Brief descriptions of legislative and regulatory action in six other states are provided in this report. A report prepared for the New York State Environmental Facilities Corp. outlines three broad approaches states may take in dealing with their hazardous waste disposal problems. These are described. State assistance in siting and post-closure maintenance, with private ownership of site and facility, appears to be the most advantageous option

  16. GEOTECHNICAL DESIGN OF SOLID WASTE LANDFILL SITES

    Directory of Open Access Journals (Sweden)

    Suat AKBULUT

    2003-02-01

    Full Text Available Solid waste landfills are important engineering structures for protection of wastes, decrease of environmental pollution, and especially prevention of soil and water pollution. Solid wastes should conveniently be maintained in landfill areas to control environmental pollution caused by waste disposals. Until the middle of this century clay liners were used for maintenance of waste disposal, but it was observed that these liner systems were insufficient. Today thinner and less permeable liner systems are constructed by using synthetic materials. In this study, by evaluating the waste landfills, site assessment of landfills and construction of natural and synthetic liner systems were summarized respectively, and especially the design properties of these systems were examined intensively. Also, leachate collection and removal facilities, landfill gas collection unites, and final cover unites were evaluated in a detailed way.

  17. Hanford site transuranic waste sampling plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed

  18. Cleanup around an old waste site

    International Nuclear Information System (INIS)

    Vandergaast, G.; Moffett, D.; Lawrence, B.E.

    1988-01-01

    42,500 m 3 of contaminated soil were removed from off-site areas around an old, low-level radioactive waste site near Port Hope, Ontario. The cleanup was done by means of conventional excavation equipment to criteria developed by Eldorado specific to the land use around the company's waste management facility. These cleanup criteria were based on exposure analyses carried out for critical receptors in two different scenarios. The excavated soils, involving eight different landowners, were placed on the original burial area of the waste management facility. Measures were also undertaken to stabilize the soils brought on-site and to ensure that there would be no subsequent recontamination of the off-site areas

  19. Preliminary Performance Assessment for the Waste Management Area C at the Hanford Site in Southeast Washington

    International Nuclear Information System (INIS)

    Bergeron, Marcel P.; Singleton, Kristin M.; Eberlein, Susan J.

    2015-01-01

    A performance assessment (PA) of Single-Shell Tank (SST) Waste Management Area C (WMA C) located at the U.S. Department of Energy's (DOE) Hanford Site in southeastern Washington is being conducted to satisfy the requirements of the Hanford Federal Facility Agreement and Consent Order (HFFACO), as well as other Federal requirements and State-approved closure plans and permits. The WMP C PA assesses the fate, transport, and impacts of radionuclides and hazardous chemicals within residual wastes left in tanks and ancillary equipment and facilities in their assumed closed configuration and the subsequent risks to humans into the far future. The part of the PA focused on radiological impacts is being developed to meet the requirements for a closure authorization under DOE Order 435.1 that includes a waste incidental to reprocessing determination for residual wastes remaining in tanks, ancillary equipment, and facilities. An additional part of the PA will evaluate human health and environmental impacts from hazardous chemical inventories in residual wastes remaining in WMA C tanks, ancillary equipment, and facilities needed to meet the requirements for permitted closure under RCRA.

  20. Preliminary Performance Assessment for the Waste Management Area C at the Hanford Site in Southeast Washington

    Energy Technology Data Exchange (ETDEWEB)

    Bergeron, Marcel P. [Washington River Protection Solutions LLC, Richland, WA (United States); Singleton, Kristin M. [Washington River Protection Solutions LLC, Richland, WA (United States); Eberlein, Susan J. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2015-01-07

    A performance assessment (PA) of Single-Shell Tank (SST) Waste Management Area C (WMA C) located at the U.S. Department of Energy's (DOE) Hanford Site in southeastern Washington is being conducted to satisfy the requirements of the Hanford Federal Facility Agreement and Consent Order (HFFACO), as well as other Federal requirements and State-approved closure plans and permits. The WMP C PA assesses the fate, transport, and impacts of radionuclides and hazardous chemicals within residual wastes left in tanks and ancillary equipment and facilities in their assumed closed configuration and the subsequent risks to humans into the far future. The part of the PA focused on radiological impacts is being developed to meet the requirements for a closure authorization under DOE Order 435.1 that includes a waste incidental to reprocessing determination for residual wastes remaining in tanks, ancillary equipment, and facilities. An additional part of the PA will evaluate human health and environmental impacts from hazardous chemical inventories in residual wastes remaining in WMA C tanks, ancillary equipment, and facilities needed to meet the requirements for permitted closure under RCRA.

  1. Final vegetative cover for closed waste sites

    International Nuclear Information System (INIS)

    Cook, J.R.; Salvo, S.K.

    1993-01-01

    Low-level, hazardous, and mixed waste disposal sites normally require some form of plant material to prevent erosion of the final closure cap. Waste disposal sites are closed and capped in a complex scientific manner to minimize water infiltration and percolation into and through the waste material. Turf type grasses are currently being used as an interim vegetative cover for most sites. This coverage allows for required monitoring of the closure cap for settlement and maintenance activities. The purpose of this five year study was to evaluate plant materials for use on wastes sites after the post-closure care period that are quickly and easily established and economically maintained, retard water infiltration, provide maximum year-round evapotranspiration, are ecologically acceptable and do not harm the closure cap. The results of the study suggest that two species of bamboo (Phyllostachys (P.) bissetii and P. rubromarginata) can be utilized to provide long lived, low maintenance, climax vegetation for the waste sites after surveillance and maintenance requirements have ceased

  2. 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.

  3. Radioactive Solid Waste Management Site (RSMS), Trombay

    International Nuclear Information System (INIS)

    Kaushik, C.P.; Agarwal, K.

    2017-01-01

    Nuclear operations generate a variety of primary solid waste comprising of tissue materials, glassware, plastics, protective rubber-wears, used components like filters, piping, structural items, unserviceable equipment, etc. This type of solid waste is generally associated with low and intermediate level of beta and gamma radiation and, in some cases, by low levels of alpha contamination. Radioactive Solid Waste Management Site (RSMS), Trombay is operational with an objective of safe and efficient management of low and intermediate level solid waste generated from various nuclear fuel cycle facilities of BARC, Trombay. The RSMS also manages the spent radioactive sources, utilised in healthcare, industries and research institutes, after completion of their useful life. The radioactive solid waste is first segregated, treated for volume reduction and disposed in engineered disposal module to prevent the migration of radionuclides and isolate them from human environment

  4. Fate of nuclear waste site remains unclear

    International Nuclear Information System (INIS)

    Anderson, E.V.

    1980-01-01

    The only commercial nuclear fuel reprocessing plant in the U.S., located in West Valley, N.Y., has been shut down since 1972, and no efforts have yet been made to clean up the site. The site contains a spent-fuel pool, high level liquid waste storage tanks, and two radioactive waste burial grounds. Nuclear Fuel Services, Inc., has been leasing the site from the New York State Energy RandD Authority. Federal litigation may ensue, prompted by NRC and DOE, if the company refuses to decontaminate the area when its lease expires at the end of 1980. DOE has developed a plan to solidify the liquid wastes at the facility but needs additional legislation and funding to implement the scheme

  5. Nuclear waste: Status of DOE's nuclear waste site characterization activities

    International Nuclear Information System (INIS)

    1987-01-01

    Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

  6. Citizen participation in nuclear waste repository siting

    International Nuclear Information System (INIS)

    Howell, R.E.; Olsen, D.

    1982-12-01

    The following study presents a proposed strategy for citizen participation during the planning stages of nuclear waste repository siting. It discusses the issue from the general perspective of citizen participation in controversial issues and in community development. Second, rural institutions and attitudes toward energy development as the context for developing a citizen participation program are examined. Third, major citizen participation techniques and the advantages and disadvantages of each approach for resolving public policy issues are evaluated. Fourth, principles of successful citizen participation are presented. Finally, a proposal for stimulating and sustaining effective responsible citizen participation in nuclear waste repository siting and management is developed

  7. Waste repository planned for Bruce Site

    International Nuclear Information System (INIS)

    King, F.

    2004-01-01

    Ontario Power Generation (OPG) and Kincardine, the municipality nearest the Bruce site, have agreed in principal to the construction of a deep geologic repository for low and medium level radioactive waste on the site. The two parties signed the 'Kincardine Hosting Agreement' on October 13, 2004 to proceed with planning, seek regulatory approval and further public consultation of the proposed project. A construction Licence is not expected before 2013. (author)

  8. 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...

  9. Siting a low-level waste facility

    International Nuclear Information System (INIS)

    English, M.R.

    1988-01-01

    In processes to site disposal facilities for low-level radioactive waste, volunteerism and incentives packages hold more promise for attracting host communities than they have for attracting host states. But volunteerism and incentives packages can have disadvantages as well as advantages. This paper discusses their pros and cons and summarizes the different approaches that states are using in their relationships with local governments

  10. Cleanup Verification Package for the 600-259 Waste Site

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2006-02-09

    This cleanup verification package documents completion of remedial action for the 600-259 waste site. The site was the former site of the Special Waste Form Lysimeter, consisting of commercial reactor isotope waste forms in contact with soils within engineered caissons, and was used by Pacific Northwest National Laboratory to collect data regarding leaching behavior for target analytes. A Grout Waste Test Facility also operated at the site, designed to test leaching rates of grout-solidified low-level radioactive waste.

  11. Cleanup Verification Package for the 600-259 Waste Site

    International Nuclear Information System (INIS)

    Capron, J.M.

    2006-01-01

    This cleanup verification package documents completion of remedial action for the 600-259 waste site. The site was the former site of the Special Waste Form Lysimeter, consisting of commercial reactor isotope waste forms in contact with soils within engineered caissons, and was used by Pacific Northwest National Laboratory to collect data regarding leaching behavior for target analytes. A Grout Waste Test Facility also operated at the site, designed to test leaching rates of grout-solidified low-level radioactive waste

  12. 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

  13. Conflicts concerning sites for waste treatment and waste disposal plants

    International Nuclear Information System (INIS)

    Werbeck, N.

    1993-01-01

    The erection of waste treatment and waste disposal flants increasingly meets with the disapproval of local residents. This is due to three factors: Firstly, the erection and operation of waste treatment plants is assumed to necessarily entail harmful effects and risks, which may be true or may not. Secondly, these disadvantages are in part considered to be non-compensable. Thirdly, waste treatment plants have a large catchment area, which means that more people enjoy their benefits than have to suffer their disadvantages. If residents in the vicinity of such plants are not compensated for damage sustained or harmed in ways that cannot be compensated for it becomes a rational stance for them, while not objecting to waste treatment and waste disposal plants in principle to object to their being in their own neighbourhood. The book comprehensively describes the subject area from an economic angle. The causes are analysed in detail and an action strategy is pointed, out, which can help to reduce acceptance problems. The individual chapters deal with emissions, risk potentials, optimization calculus considering individual firms or persons and groups of two or more firms or persons, private-economy approaches for the solving of site selection conflicts, collective decision-making. (orig./HSCH) [de

  14. 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

  15. 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.

  16. An integrated building demolition and waste planning model for the Fernald Site

    International Nuclear Information System (INIS)

    Hampshire, L.H.; Clark, T.R.; Frost, M.L.; Reising, J.W.

    1995-01-01

    The Fernald DOE site will begin full-scale remediation of buildings under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) during the 1995 fiscal year pursuant to a signed Record of Decision. This effort is currently estimated to cost $350 million and span a minimum duration of 8 years, if funding is not a constraint. The identification of the most viable sequence and schedule for the effort involved the development of an integrated planning model and the commissioning of a sitewide planning team. The resulting work product represents the best combination of assumptions and calculations possible at this time and provides information necessary for compliance with the CERCLA Remedial Design documentation requirements for the over 230 component structures governed by the decision. Sequence and integrated schedule development for the decontamination and dismantlement (D ampersand D) of Fernald structures has involved evaluation of current and future utilization of structures, availability of waste storage and staging space, the needs and impacts of other on-going Fernald projects, Resource Conservation and Recovery Act (RCRA) waste management and remediation projects, the layout of site utilities, site hydrology, and the potential sizing, location, and construction rates for an on-property disposal cell

  17. Risk management at hazardous waste sites

    International Nuclear Information System (INIS)

    Travis, C.C.; Doty, C.B.

    1990-01-01

    The Superfund Amendments and Reauthorization Act of 1986 (SARA) provided the Environmental Protection Agency (EPA) with additional resources and direction for the identification, evaluation, and remediation of hazardous waste sites in the United States. SARA established more stringent requirements for the Superfund program, both in terms of the pace of the program and the types of remedial alternatives selected. The central requirement is that remedial alternatives be ''protective of public health and the environment'' and ''significantly and permanently'' reduce the toxicity, mobility, or volume of contaminants. The mandate also requires that potential risk be considered in the decision-making process. This document discusses risk management at hazardous waste sites. Topics include selection of sites for placement on the National Priority List, risk assessment and the decision process, risk reduction and remedial alternative selection, and aquifer restoration. 10 refs., 2 figs

  18. Site suitability analysis and route optimization for solid waste ...

    African Journals Online (AJOL)

    Solid waste management system is a tedious task that is facing both developing and developed countries. Site Suitability analysis and route optimization for solid waste disposal can make waste management cheap and can be used for sustainable development. However, if the disposal site(s) is/are not sited and handle ...

  19. Physical sampling for site and waste characterization

    International Nuclear Information System (INIS)

    Bonnough, T.L.

    1994-01-01

    Physical sampling plays a basic role in site and waste characterization program effort. The term ''physical sampling'' used here means collecting tangible, physical samples of soil, water, air, waste streams, or other materials. The industry defines the term ''physical sampling'' broadly to include measurements of physical conditions such as temperature, wind conditions, and pH which are also often taken in a sample collection effort. Most environmental compliance actions are supported by the results of taking, recording, and analyzing physical samples and the measuring of physical conditions taken in association with sample collecting

  20. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Reneau, S.L.; Raymond, R. Jr.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau

  1. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Reneau, S.L.; Raymond, R. Jr. [eds.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

  2. 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

  3. 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

  4. Evolution of EPA/DOE technical cooperation in remediation of radiation/mixed waste contaminated sites

    International Nuclear Information System (INIS)

    Dyer, Robert S.; Garcia-Frias, Beverly; Wolbarst, Anthony B.; Coe, Larry J.

    1992-01-01

    The EPA Office of Radiation Programs (ORP) and the DOE Office of Environmental Restoration and Waste Management (EM) are cooperating in efforts related to restoration of radioactive and mixed waste sites. The impetus for these efforts derived from DOE's need to perform restoration activities according to CERCLA/RCRA requirements, and from ORP's role as a supplier of radiation expertise to federal agencies. These activities include: assessing remediation technology, developing radioanalytical protocols; matching cleanup technologies to soil characteristics; developing a process for the evaluation, selection, and appropriate use of groundwater models; reviewing incinerator practices; and addressing technical issues associated with the WIPP. Cooperative projects planned for the future include: evaluation of methodologies for streamlining the restoration process; assessment of the applicability of process knowledge for waste characterization; evaluation of recycling of radioactive metals; and expansion of selected environmental protection initiatives at the International Atomic Energy Agency (IAEA). Public acceptance is a crucial component of the remediation process. An underlying objective of these cooperative initiatives is to address issues of concern to the public in an open and honest fashion. (author)

  5. Nevada test site waste acceptance criteria

    International Nuclear Information System (INIS)

    1996-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  6. Compensation: Will it provide a waste site?

    International Nuclear Information System (INIS)

    Pulsipher, A.G.

    1993-01-01

    Offering an attractive compensation package to persuade a community to voluntarily accept an otherwise undesirable facility may work in some cases, but it's not likely to work for high-level nuclear-waste disposal. The public perception of the risks involved and the public distrust of the institutions responsible for managing those risks are just too great. Much of the controversy stems from public perceptions that the site-selection process itself is unfair. Resentment builds when this occurs, and offers of compensation come to be labeled bribes or blood money. The driving force behind current nuclear-waste policy is intergenerational equity - the moral concept that the generation that produced the waste should dispose of it, permanently. Regardless of the moral appeal, doubts have been raised about the technical feasibility of this approach. Alternatives featuring intergenerational monetary compensation may better honor the commitment hor-ellipsis and reduce pressure to try to do what may be impossible

  7. Nevada test site waste acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  8. Solid waste dumping site suitability analysis using geographic ...

    African Journals Online (AJOL)

    Solid waste dumping is a serious problem in the urban areas because most solid wastes are not dumped in the suitable areas. Bahir Dar Town has the problem of solid waste dumping site identification. The main objective of this study was to select potential areas for suitable solid waste dumping sites for Bahir Dar Town, ...

  9. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3. Appendixes 1 through 8

    Energy Technology Data Exchange (ETDEWEB)

    None

    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. (CBS)

  10. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2. Sections 4 through 9

    Energy Technology Data Exchange (ETDEWEB)

    None

    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.

  11. Hanford Site Waste Storage Tank Information Notebook

    International Nuclear Information System (INIS)

    Husa, E.I.; Raymond, R.E.; Welty, R.K.; Griffith, S.M.; Hanlon, B.M.; Rios, R.R.; Vermeulen, N.J.

    1993-07-01

    This report provides summary data on the radioactive waste stored in underground tanks in the 200 East and West Areas at the Hanford Site. The summary data covers each of the existing 161 Series 100 underground waste storage tanks (500,000 gallons and larger). It also contains information on the design and construction of these tanks. The information in this report is derived from existing reports that document the status of the tanks and their materials. This report also contains interior, surface photographs of each of the 54 Watch List tanks, which are those tanks identified as Priority I Hanford Site Tank Farm Safety Issues in accordance with Public Law 101-510, Section 3137*

  12. RCRA Facility Information

    Data.gov (United States)

    U.S. Environmental Protection Agency — This asset includes hazardous waste information, which is mostly contained in the Resource Conservation and Recovery Act Information (RCRAInfo) System, a national...

  13. Performance of a radioactive waste internment site

    International Nuclear Information System (INIS)

    Bernhardt, D.E.; Owen, D.H.; Mishub, R.J.; Prewett, S.V.; Cole, L.W.

    1990-01-01

    Aerojet disposed of 30,000 cubic meters of uranium and thorium wastes in an engineered 12,000 square meter (3 acre) internment site in Tennessee. The operation, performed under a State of Tennessee source material license, is based on termination of the license with the material remaining in place, and the option of future commercial use of the site. The closure plan included a long-term monitoring program. Yearly monitoring of the site has verified performance within the design criteria. Full-time construction monitored by a licensed engineer and extensive testing of materials ensured construction of the site according to or better than the specifications. Surface subsidence of the site has averaged about 2.2 cm with a range of 0 to 4.3 cm at 11 settlement markers after 4 years. The anticipated settlement, based on design parameters, was between 15 and 25 cm. The present anticipated settlement is 8 to 15 cm, based on the as-built parameters, and the long-term monitoring results. Slope stability analysis indicates the stability has improved with time due to consolidation of materials and reduced groundwater activity as a result of site construction. There has been no need for corrective action maintenance due to erosion, sluffing of slopes, or subsidence. Groundwater monitoring indicates the materials have been isolated, and there have also been no indications of springs or leakage from the site. 9 refs., 2 figs., 3 tabs

  14. Strategy for managing mixed waste at a plant site

    International Nuclear Information System (INIS)

    Fentiman, A.

    1991-01-01

    No waste disposal site is currently accepting mixed waste, but facilities across the country continue to generate it. The waste manager at each site is faced with two problems: how to manage the mixed waste already on-site and how to minimize the amount of new waste generated. A strategy has been developed to address each problem. A key element of the strategy is a building-by-building survey of the site. The survey provides information on how and where mixed waste is generated and stored. This paper describes a method for planning and conducting a site-wide mixed-waste survey. It then outlines approaches to managing existing mixed waste and to minimizing mixed-waste generation using information from the survey

  15. Radioactive waste on-site storage alternative

    International Nuclear Information System (INIS)

    Dufrane, K.H.

    1983-01-01

    The first, most frequently evaluated approach for the large producer is the construction of a relatively expensive storage building. However, with the likely possibility that at least one disposal site will remain available and the building never used, such expenditures are difficult to justify. A low cost, but effective alternative, is the use of ''On-Site Storage Containers'' (OSSC) when and if required. Radwaste is only stored in the OSSC if a disposal site is not available. A small number of OSSC's would be purchased initially just to assure immediate access to storage. Only in the unlikely event of total disposal sites closure would additional OSSC's have to be obtained and even this is cost effective. With two or three months of storage available on site, production lead time is sufficient for the delivery of additional units at a rate faster than the waste can be produced. The recommended OSSC design would be sized and shielding optimized to meet the needs of the waste generator. Normally, this would duplicate the shipping containers (casks or vans) currently in use. The reinforced concrete design presented is suitable for outside storage, contains a leakproof polyethylene liner and has remote sampling capability. Licensing would be under 10CFR50.59 for interim storage with long-term storage under 10CFR30 not an impossibility. Cost comparisons of this approach vs. building construction show that for a typical reactor plant installation, the OSSC offers direct savings even under the worst case assumption that no disposal sites are available and the time value of money is zero

  16. 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

  17. 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

  18. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    Energy Technology Data Exchange (ETDEWEB)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996.

  19. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996

  20. 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

  1. Savannah River Site Approved Site Treatment Plan, 1998 Annual Update

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, B. [Westinghouse Savannah River Company, AIKEN, SC (United States); Berry, M.

    1998-03-01

    The U.S. Department of Energy, Savannah River Operations Office (DOE- SR),has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume I. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore,pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE`s requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021.Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW.The Compliance Plan Volume (Volume I) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information.

  2. Waste management units - Savannah River Site

    International Nuclear Information System (INIS)

    1989-10-01

    This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only

  3. DSEM, Radioactive Waste Disposal Site Economic Model

    International Nuclear Information System (INIS)

    Smith, P.R.

    2005-01-01

    1 - Description of program or function: The Disposal Site Economic Model calculates the average generator price, or average price per cubic foot charged by a disposal facility to a waste generator, one measure of comparing the economic attractiveness of different waste disposal site and disposal technology combinations. The generator price is calculated to recover all costs necessary to develop, construct, operate, close, and care for a site through the end of the institutional care period and to provide the necessary financial returns to the site developer and lender (when used). Six alternative disposal technologies, based on either private or public financing, can be considered - shallow land disposal, intermediate depth disposal, above or below ground vaults, modular concrete canister disposal, and earth mounded concrete bunkers - based on either private or public development. 2 - Method of solution: The economic models incorporate default cost data from the Conceptual Design Report (DOE/LLW-60T, June 1987), a study by Rodgers Associates Engineering Corporation. Because all costs are in constant 1986 dollars, the figures must be modified to account for inflation. Interest during construction is either capitalized for the private developer or rolled into the loan for the public developer. All capital costs during construction are depreciated over the operation life of the site using straight-line depreciation for the private sector. 3 - Restrictions on the complexity of the problem: Maxima of - 100 years post-operating period, 30 years operating period, 15 years pre-operating period. The model should be used with caution outside the range of 1.8 to 10.5 million cubic feet of total volume. Depreciation is not recognized with public development

  4. Defense waste management operations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Williams, R.E.; Kendall, E.W.

    1988-01-01

    Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class-C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types. The paper discusses site selection; establishment of the Radioactive Waste Management Project; operations with respect to low-level radioactive wastes, transuranic waste storage, greater confinement disposal test, and mixed waste management facility; and related research activities such as tritium migration studies, revegetation studies, and in-situ monitoring of organics

  5. Electronic Denitration Savannah River Site Radioactive Waste

    International Nuclear Information System (INIS)

    Hobbs, D.T.

    1995-01-01

    Electrochemical destruction of nitrate in radioactive Savannah River Site Waste has been demonstrated in a bench-scale flow cell reactor. Greater than 99% of the nitrate can be destroyed in either an undivided or a divided cell reactor. The rate of destruction and the overall power consumption is dependent on the cell configuration and electrode materials. The fastest rate was observed using an undivided cell equipped with a nickel cathode and nickel anode. The use of platinized titanium anode increased the energy requirement and costs compared to a nickel anode in both the undivided and divided cell configurations

  6. Low-level radioactive waste disposal at a humid site

    International Nuclear Information System (INIS)

    Lee, D.W.

    1987-03-01

    Waste management in humid environments poses a continuing challenge because of the potential contamination of groundwater in the long term. Short-term needs for waste disposal, regulatory uncertainty, and unique site and waste characteristics have led to the development of a site-specific waste classification and management system proposed for the Oak Ridge Reservation. The overlying principle of protection of public health and safety is used to define waste classes compatible with generated waste types, disposal sites and technologies, and treatment technologies. 1 fig., 1 tab

  7. Mixed waste disposal facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Wells, M.N.; Bailey, L.L.

    1991-01-01

    The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission

  8. Operational radioactive waste management plan for the Nevada Test Site

    International Nuclear Information System (INIS)

    1980-11-01

    The Operational Radioactive Waste Management Plan for the Nevada Test Site establishes procedures and methods for the safe shipping, receiving, processing, disposal, and storage of radioactive waste. Included are NTS radioactive waste disposition program guidelines, procedures for radioactive waste management, a description of storage and disposal areas and facilities, and a glossary of specifications and requirements

  9. Pre-1970 transuranic solid waste at the Hanford Site

    International Nuclear Information System (INIS)

    Greenhalgh, W.O.

    1995-01-01

    The document is based on a search of pre-1970 Hanford Solid Waste Records. The available data indicates seven out of thirty-one solid waste burial sites used for pre-1970 waste appear to be Transuranic (TRU). A burial site defined to be TRU contains >100 nCi/gm Transuranic nuclides

  10. Biological tracer for waste site characterization

    International Nuclear Information System (INIS)

    Strong-Gunderson, J.

    1995-01-01

    Remediating hazardous waste sites requires detailed site characterization. In groundwater remediation, characterizing the flow paths and velocity is a major objective. Various tracers have been used for measuring groundwater velocity and transport of contaminants, colloidal particles, and bacteria and nutrients. The conventional techniques use dissolved solutes, dyes. and gases to estimate subsurface transport pathways. These tracers can provide information on transport and diffusion into the matrix, but their estimates for groundwater flow through fractured regions are very conservative. Also, they do not have the same transport characteristics as bacteria and suspended colloid tracers, both of which must be characterized for effective in-place remediation. Bioremediation requires understanding bacterial transport and nutrient distribution throughout the acquifer, knowledge of contaminants s mobile colloidal particles is just essential

  11. Conceptual Evaluation for the Installation of Treatment Capability for Mixed Low-Level Waste at the Nevada National Security Site

    International Nuclear Information System (INIS)

    2010-01-01

    National Security Technologies, LLC, initiated an evaluation of treatment technologies that they would manage and operate as part of the mixed low-level waste (MLLW) disposal facilities at the Nevada National Security Site (NNSS). The NNSS Disposal Facility has been receiving radioactive waste from the U.S. Department of Energy (DOE) complex since the 1960s, and since 2005 the NNSS Disposal Facility has been receiving radioactive and MLLW for disposal only. In accordance with the Resource Conservation and Recovery Act (RCRA), all mixed waste must meet land disposal restrictions (LDRs) prior to disposal. Compliance with LDRs is attained through treatment of the waste to mitigate the characteristics of the listed waste hazard. Presently, most generators utilize commercial capacity for waste treatment prior to shipment to the NNSS Disposal Facility. The objectives of this evaluation are to provide a conceptual study of waste treatment needs (i.e., demand), identify potential waste treatment technologies to meet demand, and analyze implementation considerations for initiating MLLW treatment capacity at the NNSS Disposal Facility. A review of DOE complex waste generation forecast data indicates that current and future Departmental demand for mixed waste treatment capacity will remain steady and strong. Analysis and screening of over 30 treatment technologies narrowed the field of treatment technologies to four: (1) Macroencapsulation; (2) Stabilization/microencapsulation; (3) Sort and segregation; and (4) Bench-scale mercury amalgamation. The analysis of treatment technologies also considered existing permits, current the NNSS Disposal Facility infrastructure such as utilities and procedures, and past experiences such as green-light and red-light lessons learned. A schedule duration estimate has been developed for permitting, design, and construction of onsite treatment capability at the NNSS Disposal Facility. Treatment capability can be ready in 20 months.

  12. Conceptual Evaluation for the Installation of Treatment Capability for Mixed Low Level Waste at the Nevada National Security Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-11-24

    National Security Technologies, LLC, initiated an evaluation of treatment technologies that they would manage and operate as part of the mixed low-level waste (MLLW) disposal facilities at the Nevada National Security Site (NNSS). The NNSS Disposal Facility has been receiving radioactive waste from the U.S. Department of Energy (DOE) complex since the 1960s, and since 2005 the NNSS Disposal Facility has been receiving radioactive and MLLW for disposal only. In accordance with the Resource Conservation and Recovery Act (RCRA), all mixed waste must meet land disposal restrictions (LDRs) prior to disposal. Compliance with LDRs is attained through treatment of the waste to mitigate the characteristics of the listed waste hazard. Presently, most generators utilize commercial capacity for waste treatment prior to shipment to the NNSS Disposal Facility. The objectives of this evaluation are to provide a conceptual study of waste treatment needs (i.e., demand), identify potential waste treatment technologies to meet demand, and analyze implementation considerations for initiating MLLW treatment capacity at the NNSS Disposal Facility. A review of DOE complex waste generation forecast data indicates that current and future Departmental demand for mixed waste treatment capacity will remain steady and strong. Analysis and screening of over 30 treatment technologies narrowed the field of treatment technologies to four: • Macroencapsulation • Stabilization/microencapsulation • Sort and segregation • Bench-scale mercury amalgamation The analysis of treatment technologies also considered existing permits, current the NNSS Disposal Facility infrastructure such as utilities and procedures, and past experiences such as green-light and red-light lessons learned. A schedule duration estimate has been developed for permitting, design, and construction of onsite treatment capability at the NNSS Disposal Facility. Treatment capability can be ready in 20 months.

  13. 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...

  14. The Savannah River Site Waste Inventory Management Program

    International Nuclear Information System (INIS)

    Griffith, J.M.; Holmes, B.R.

    1995-01-01

    Each hazardous and radioactive waste generator that delivers waste to Savannah River Site (SRS) treatment, storage and disposal (TSD) facilities is required to implement a waste certification plan. The waste certification process ensures that waste has been properly identified, characterized, segregated, packaged, and shipped according to the receiving facilities waste acceptance criteria. In order to comply with the rigid acceptance criteria, the Reactor Division developed and implemented the Waste Inventory Management Program (WIMP) to track the generation and disposal of low level radioactive waste. The WIMP system is a relational database with integrated barcode technology designed to track the inventory radioactive waste. During the development of the WIMP several waste minimization tools were incorporated into the design of the program. The inclusion of waste minimization tools as part of the WIMP has resulted in a 40% increase in the amount of waste designated as compactible and an overall volume reduction of 5,000 cu-ft

  15. Radioactive waste disposal: Recommendations for a repository site selection

    International Nuclear Information System (INIS)

    Cadelli, N.; Orlowski, S.

    1992-01-01

    This report is a guidebook on recommendations for site selection of radioactive waste repository, based on a consensus in european community. This report describes particularly selection criteria and recommendations for radioactive waste disposal in underground or ground repositories. 14 refs

  16. Hanford Site waste management and environmental restoration integration plan

    International Nuclear Information System (INIS)

    Merrick, D.L.

    1990-01-01

    The ''Hanford Site Waste Management and Environmental Restoration Integration Plan'' describes major actions leading to waste disposal and site remediation. The primary purpose of this document is to provide a management tool for use by executives who need to quickly comprehend the waste management and environmental restoration programs. The Waste Management and Environmental Restoration Programs have been divided into missions. Waste Management consists of five missions: double-shell tank (DST) wastes; single-shell tank (SST) wastes (surveillance and interim storage, stabilization, and isolation); encapsulated cesium and strontium; solid wastes; and liquid effluents. Environmental Restoration consists of two missions: past practice units (PPU) (including characterization and assessment of SST wastes) and surplus facilities. For convenience, both aspects of SST wastes are discussed in one place. A general category of supporting activities is also included. 20 refs., 14 figs., 7 tabs

  17. Blasting at a Superfund chemical waste site

    International Nuclear Information System (INIS)

    Burns, D.R.

    1991-01-01

    During the summer of 1989, Maine Drilling and Blasting of Gardiner, Maine was contracted by Cayer Corporation of Harvard, Massachusetts to drill and blast an interceptor trench at the Nyanza Chemical Superfund Site in Ashland, Massachusetts. The interceptor trench was to be 1,365 feet long and to be blasted out of granite. The trench was to be 12 feet wide at the bottom with 1/1 slopes, the deepest cut being 30 feet deep. A French drain 12 feet wide by 15 to 35 feet deep was blasted below the main trench on a 2% slope from its center to each end. A French drain is an excavation where the rock is blasted but not dug. The trench would be used as a perimeter road with any ground water flow going through the French drain flowing to both ends of the trench. Being a Superfund project turned a simple blasting project into a regulatory nightmare. The US Environmental Protection Agency performed all the chemical related functions on site. The US Army Corps of Engineers was overseeing all related excavation and construction on site, as was the Massachusetts Department of Environmental Quality Engineering, the local Hazardous Wastes Council, and the local Fire Department. All parties had some input with the blasting and all issues had to be addressed. The paper outlines the project, how it was designed and completed. Also included is an outline of the blast plan to be submitted for approval, an outline of the Safety/Hazardous Waste training and a description of all the problems which arose during the project by various regulatory agencies

  18. Application to transfer radioactive waste to the Nevada Test Site

    International Nuclear Information System (INIS)

    1992-01-01

    All waste described in this application has been, and will be, generated by LANL in support of the nuclear weapons test program at the NTS. All waste originates on the NTS. DOE Order 5820.2A states that low-level radioactive waste shall be disposed of at the site where it is generated, when practical. Since the waste is produced at the NTS, it is cost effective for LANL to dispose of the waste at the NTS

  19. Waste classification and methods applied to specific disposal sites

    International Nuclear Information System (INIS)

    Rogers, V.C.

    1979-01-01

    An adequate definition of the classes of radioactive wastes is necessary to regulating the disposal of radioactive wastes. A classification system is proposed in which wastes are classified according to characteristics relating to their disposal. Several specific sites are analyzed with the methodology in order to gain insights into the classification of radioactive wastes. Also presented is the analysis of ocean dumping as it applies to waste classification. 5 refs

  20. 75 FR 76633 - Oregon; Correction of Federal Authorization of the State's Hazardous Waste Management Program

    Science.gov (United States)

    2010-12-09

    ...; Correction of Federal Authorization of the State's Hazardous Waste Management Program AGENCY: Environmental... its federally authorized RCRA Hazardous Waste Management Program. These authorized changes included... with Conditionally Exempt Small Quality Generators (CESQG) waste is subject to RCRA used oil management...

  1. Defense waste management operations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Williams, R.E.; Kendall, E.W.

    1988-01-01

    Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types

  2. 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.

  3. Hanford site implementation plan for buried, transuranic-contaminated waste

    International Nuclear Information System (INIS)

    1987-05-01

    The GAO review of DOE's Defense Waste Management Plan (DWMP) identified deficiencies and provided recommendations. This report responds to the GAO recommendations with regard to the Hanford Site. Since the issuance of the DWMP, an extensive planning base has been developed for all high-level and transuranic waste at the Hanford Site. Thirty-three buried sites have been identified as possibly containing waste that can be classified as transuranic waste. Inventory reports and process flowsheets were used to provide an estimate of the radionuclide and hazardous chemical content of these sites and approximately 370 additional sites that can be classified as low-level waste. A program undertaken to characterize select sites suspected of having TRU waste to refine the inventory estimates. Further development and evaluation are ongoing to determine the appropriate remedial actions, with the objectives of balancing long-term risks with costs and complying with regulations. 18 refs., 7 figs., 6 tabs

  4. Waste site grouping for 200 Areas soil investigations

    International Nuclear Information System (INIS)

    1997-01-01

    The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models

  5. Focused feasibility study of engineered barriers for waste management units in the 200 areas

    International Nuclear Information System (INIS)

    1996-08-01

    This Focused Feasibility Study (FFS) evaluates a total of four conceptual barrier designs for different types of waste sites. The Hanford Barrier, the Modified RCRA Subtitle C Barrier, and the Modified RCRA Subtitle D Barrier are being considered as the baseline design for the purpose of the FFS evaluation. A fourth barrier design, the Standard RCRA Subtitle C Barrier, is also evaluated in this FFS; it is commonly applied at other waste sites across the country. These four designs provide a range of cover options to minimize health and environmental risks associated with a site and specific waste categories for active design life periods of 30, 100, 500, and 1,000 years. Design criteria for the 500 and 1,000-year design life barriers include design performance to extend beyond active institutional control and monitoring periods

  6. 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.

  7. Long-term gas and brine migration at the Waste Isolation Pilot Plant: Preliminary sensitivity analyses for post-closure 40 CFR 268 (RCRA), May 1992

    International Nuclear Information System (INIS)

    1992-12-01

    This report describes preliminary probabilistic sensitivity analyses of long term gas and brine migration at the Waste Isolation Pilot Plant (WIPP). Because gas and brine are potential transport media for organic compounds and heavy metals, understanding two-phase flow in the repository and the surrounding Salado Formation is essential to evaluating long-term compliance with 40 CFR 268.6, which is the portion of the Land Disposal Restrictions of the Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act that states the conditions for disposal of specified hazardous wastes. Calculations described here are designed to provide guidance to the WIPP Project by identifying important parameters and helping to recognize processes not yet modeled that may affect compliance. Based on these analyses, performance is sensitive to shaft-seal permeabilities, parameters affecting gas generation, and the conceptual model used for the disturbed rock zone surrounding the excavation. Brine migration is less likely to affect compliance with 40 CFR 268.6 than gas migration. However, results are preliminary, and additional iterations of uncertainty and sensitivity analyses will be required to provide the confidence needed for a defensible compliance evaluation. Specifically, subsequent analyses will explicitly include effects of salt creep and, when conceptual and computational models are available, pressure-dependent fracturing of anhydrite marker beds

  8. Assessment of LANL waste management site plan

    International Nuclear Information System (INIS)

    Black, R.L.; Davis, K.D.; Hoevemeyer, S.S.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) Waste Management Plan to determine if it meets applicable DOE requirements. DOE Order 5820.2A, Radioactive Waste Management, sets forth requirements and guidelines for the establishment of a Waste Management Plan. The primary purpose of a Waste Management Plan is to describe how waste operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming year

  9. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    2000-01-01

    The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility

  10. Hanford Site guide for preparing and maintaining generator group pollution prevention program documentation

    International Nuclear Information System (INIS)

    Place, B.G.

    1998-01-01

    This document provides guidance to generator groups for preparing and maintaining documentation of Pollution Prevention Waste Minimization (P2/WMin) Program activities. The guidance is one of a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE-RL, 1998a) and Prime contractor implementation plans describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and 3005(h) (RCRA and EPA, 1994). Documentation guidance for the following five P2/WMin elements are discussed: Fiscal Year (FY) Goals; Budget and Staffing; Waste Minimization (WMin) Assessments (WMAs); Quarterly Pollution Prevention (P2) Reporting WMin Certification

  11. Hanford Site Guide for Preparing and Maintaining Fenerator Group Pollution Prevention Program Documentation

    International Nuclear Information System (INIS)

    PLACE, B.G.

    1999-01-01

    This document provides guidance to generator groups for preparing and maintaining documentation of Pollution Prevention/Waste Minimization (P2/WMin) Program activities. The guidance is one of a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE-RL, 1998a) and Prime Contractor implementation plans describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and (300501) (RCRA and EPA, 1994). Documentation guidance for the following five P2/WMin elements are discussed: Fiscal Year (FY) Goals; Budget and Staffing; Waste Minimization (WMinn ) Assessments (WMAs); Pollution Prevention (P2) Reporting; WMin Certification

  12. Disposal facilities for radioactive waste - legislative requirements for siting

    International Nuclear Information System (INIS)

    Markova-Mihaylova, Radosveta

    2015-01-01

    The specifics of radioactive waste, namely the content of radionuclides require the implementation of measures to protect human health and the environment against the hazards arising from ionizing radiation, including disposal of waste in appropriate facilities. The legislative requirements for siting of such facilities, and classification of radioactive waste, as well as the disposal methods, are presented in this publication

  13. Passive soil venting at the Chemical Waste Landfill Site at Sandia National Laboratories, Albuquerque, New Mexico

    International Nuclear Information System (INIS)

    Phelan, J.M.; Reavis, B.; Cheng, W.C.

    1995-05-01

    Passive Soil Vapor Extraction was tested at the Chemical Waste Landfill (CWL) site at Sandia National Laboratories, New Mexico (SNLIW). Data collected included ambient pressures, differential pressures between soil gas and ambient air, gas flow rates into and out of the soil and concentrations of volatile organic compounds (VOCS) in vented soil gas. From the differential pressure and flow rate data, estimates of permeability were arrived at and compared with estimates from other studies. Flow, differential pressure, and ambient pressure data were collected for nearly 30 days. VOC data were collected for two six-hour periods during this time. Total VOC emissions were calculated and found to be under the limit set by the Resource Conservation and Recovery Act (RCRA). Although a complete process evaluation is not possible with the data gathered, some of the necessary information for designing a passive venting process was determined and the important parameters for designing the process were indicated. More study is required to evaluate long-term VOC removal using passive venting and to establish total remediation costs when passive venting is used as a polishing process following active soil vapor extraction

  14. Site-Specific Seismic Site Response Model for the Waste Treatment Plant, Hanford, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Rohay, Alan C.; Reidel, Steve P.

    2005-02-24

    This interim report documents the collection of site-specific geologic and geophysical data characterizing the Waste Treatment Plant site and the modeling of the site-specific structure response to earthquake ground motions.

  15. Cleanup Verification Package for the 300-18 Waste Site

    International Nuclear Information System (INIS)

    Capron, J.M.

    2005-01-01

    This cleanup verification package documents completion of remedial action for the 300-18 waste site. This site was identified as containing radiologically contaminated soil, metal shavings, nuts, bolts, and concrete

  16. Risky business: Assessing cleanup plans for waste sites

    International Nuclear Information System (INIS)

    Blaylock, B.

    1995-01-01

    ORNL was chosen to perform human health and ecological risk assessments for DOE because of its risk assessment expertise. The U.S. Department of Energy's many production and research sites contain radioactive and hazardous wastes. These waste sites pose potential risks to the health and safety of remediation and waste management workers and the public. The risks, however, vary from site to site. Some sites undoubtedly present larger risks than others and should be cleaned up first. However, before the cleanup begins, DOE is required by law to prepare an environmental impact statement on any actions that may significantly affect the environment-even actions that would clean it up

  17. Successful characterization of radioactive waste at the Savannah River Site

    International Nuclear Information System (INIS)

    Hughes, M.B.; Miles, G.M.

    1995-01-01

    Characterization of the low-level radioactive waste generated by forty five independent operating facilities at The Savannah River Site (SRS) experienced a slow start. However, the site effectively accelerated waste characterization based on findings of an independent assessment that recommended several changes to the existing process. The new approach included the development of a generic waste characterization protocol and methodology and the formulation of a technical board to approve waste characterization. As a result, consistent, detailed characterization of waste streams from SRS facilities was achieved in six months

  18. Site and facility waste transportation services planning documents

    International Nuclear Information System (INIS)

    Ratledge, J.E.; Schmid, S.; Danese, L.

    1991-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and maintenance of Site- and Facility-Specific Transportation Services Planning Documents (SPDs) and Site-Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities, with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations

  19. RCRA corrective measures using a permeable reactive iron wall US Coast Guard Support Center, Elizabeth City, North Carolina

    International Nuclear Information System (INIS)

    Schmithors, W.L.; Vardy, J.A.

    1997-01-01

    A chromic acid release was discovered at a former electroplating shop at the U.S. Coast Guard Support Center in Elizabeth City, North Carolina. Initial investigative activities indicated that chromic acid had migrated into the subsurface soils and groundwater. In addition, trichloroethylene (TCE) was also discovered in groundwater during subsequent investigations of the hexavalent chromium (Cr VI) plume. Corrective measures were required under the Resource Conservation and Recovery Act (RCRA). The in-situ remediation method, proposed under RCRA Interim Measures to passively treat the groundwater contaminants, uses reactive zero-valent iron to reductively dechlorinate the chlorinated compounds and to mineralize the hexavalent chromium. A 47 meter by 0.6 meter subsurface permeable iron wall was installed downgradient of the source area to a depth of 7 meters using a direct trenching machine. The iron filings were placed in the ground as the soils were excavated from the subsurface. This is the first time that direct trenching was used to install reactive zero-valent iron filings. Over 250 metric tons of iron filings were used as the reactive material in the barrier wall. Installation of the iron filings took one full day. Extensive negotiations with regulatory agencies were required to use this technology under the current facility Hazardous Waste Management Permit. All waste soils generated during the excavation activities were contained and treated on site. Once contaminant concentrations were reduced the waste soils were used as fill material

  20. Hanford Site radioactive mixed waste thermal treatment initiative

    International Nuclear Information System (INIS)

    Place, B.G.; Riddelle, J.G.

    1993-03-01

    This paper is a progress report of current Westinghouse Hanford Company engineering activities related to the implementation of a program for the thermal treatment of the Hanford Site radioactive mixed waste. Topics discussed include a site-specific engineering study, the review of private sector capability in thermal treatment, and thermal treatment of some of the Hanford Site radioactive mixed waste at other US Department of Energy sites

  1. Characterization recommendations for waste sites at the Savannah River Plant

    International Nuclear Information System (INIS)

    Carlton, W.H.; Gordon, D.E.; Johnson, W.F.; Kaback, D.S.; Looney, B.B.; Nichols, R.L.; Shedrow, C.B.

    1987-11-01

    One hundred and sixty six disposal facilities that received or may have received waste materials resulting from operations at the Savannah River Plant (SRP) have been identified. These waste range from innocuous solid and liquid materials (e.g., wood piles) to process effluents that contain hazardous and/or radioactive constituents. The waste sites have been grouped into 45 categories according the the type of waste materials they received. Waste sites are located with SRP coordinates, a local Department of Energy (DOE) grid system whose grid north is 36 degrees 22 minutes west of true north. DOE policy is to close all waste sites at SRP in a manner consistent with protecting human health and environment and complying with applicable environmental regulations (DOE 1984). A uniform, explicit characterization program for SRP waste sites will provide a sound technical basis for developing closure plans. Several elements are summarized in the following individual sections including (1) a review of the history, geohydrology, and available characterization data for each waste site and (2) recommendations for additional characterization necessary to prepare a reasonable closure plan. Many waste sites have been fully characterized, while others have not been investigated at all. The approach used in this report is to evaluate available groundwater quality and site history data. For example, groundwater data are compared to review criteria to help determine what additional information is required. The review criteria are based on regulatory and DOE guidelines for acceptable concentrations of constituents in groundwater and soil

  2. 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

  3. 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.

  4. DEMONSTRATiON OF A SUBSURFACE CONTAINMENT SYSTEM FOR INSTALLATION AT DOE WASTE SITES

    Energy Technology Data Exchange (ETDEWEB)

    Thomas J. Crocker; Verna M. Carpenter

    2003-05-21

    Between 1952 and 1970, DOE buried mixed waste in pits and trenches that now have special cleanup needs. The disposal practices used decades ago left these landfills and other trenches, pits, and disposal sites filled with three million cubic meters of buried waste. This waste is becoming harmful to human safety and health. Today's cleanup and waste removal is time-consuming and expensive with some sites scheduled to complete cleanup by 2006 or later. An interim solution to the DOE buried waste problem is to encapsulate and hydraulically isolate the waste with a geomembrane barrier and monitor the performance of the barrier over its 50-yr lifetime. The installed containment barriers would isolate the buried waste and protect groundwater from pollutants until final remediations are completed. The DOE has awarded a contract to RAHCO International, Inc.; of Spokane, Washington; to design, develop, and test a novel subsurface barrier installation system, referred to as a Subsurface Containment System (SCS). The installed containment barrier consists of commercially available geomembrane materials that isolates the underground waste, similar to the way a swimming pools hold water, without disrupting hazardous material that was buried decades ago. The barrier protects soil and groundwater from contamination and effectively meets environmental cleanup standards while reducing risks, schedules, and costs. Constructing the subsurface containment barrier uses a combination of conventional and specialized equipment and a unique continuous construction process. This innovative equipment and construction method can construct a 1000-ft-long X 34-ft-wide X 30-ft-deep barrier at construction rates to 12 Wday (8 hr/day operation). Life cycle costs including RCRA cover and long-term monitoring range from approximately $380 to $590/cu yd of waste contained or $100 to $160/sq ft of placed barrier based upon the subsurface geology surrounding the waste. Project objectives for Phase

  5. Area 5 Radioactive Waste Management Site Safety Assessment Document

    International Nuclear Information System (INIS)

    Horton, K.K.; Kendall, E.W.; Brown, J.J.

    1980-02-01

    The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization

  6. Low-level waste program technical strategy

    International Nuclear Information System (INIS)

    Bledsoe, K.W.

    1994-01-01

    The Low-Level Waste Technical Strategy document describes the mechanisms which the Low-Level Waste Program Office plans to implement to achieve its mission. The mission is to manage the receipt, immobilization, packaging, storage/disposal and RCRA closure (of the site) of the low-level Hanford waste (pretreated tank wastes) in an environmentally sound, safe and cost-effective manner. The primary objective of the TWRS Low-level waste Program office is to vitrify the LLW fraction of the tank waste and dispose of it onsite

  7. Savannah River Site`s Site Specific Plan. Environmental restoration and waste management, fiscal year 1992

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show the Environmental Restoration and Waste Management activities that were identified during the preparation of the Department of Energy-Headquarters (DOE-HQ) Environmental Restoration and Waste Management Five-Year Plan (FYP) for FY 1992--1996. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. The purpose of the SSP is to develop a baseline for policy, budget, and schedules for the DOE Environmental Restoration and Waste Management activities. The plan explains accomplishments since the Fiscal Year (FY) 1990 plan, demonstrates how present and future activities are prioritized, identifies currently funded activities and activities that are planned to be funded in the upcoming fiscal year, and describes future activities that SRS is considering.

  8. Technical Assessment Of Selection Of A Waste Disposal Site

    International Nuclear Information System (INIS)

    Lee, Bong Hun

    1992-04-01

    This book gives overall descriptions of technical assessment of selection of a waste disposal site, which deals with standard of selection on incinerator of city waste, the method over assessment of selection of incinerator in city waste, prerequisite of technical assessment for selection of incinerator, waste incinerator and related equipment such as form, structure, quality of material, ventilation device, plumbing system and electrical installation, and total plan like plan of construction and a measure taken against environmental pollution.

  9. Storage of intermediate level waste at UKAEA sites

    International Nuclear Information System (INIS)

    Goodill, D.R.; Tymons, B.J.

    1985-08-01

    This report describes the storage of wastes at UKAEA sites and accordingly contributes to the investigations conducted by the Department of the Environment into the Best Practicable Environmental Option (BPEO) for radioactive waste storage and/or disposal. This report on the storage of ILW should be read in conjunction with a similar NII funded CTS study for Licensed Sites in the UK. (author)

  10. Analysis of SRP waste streams for waste tank certification

    International Nuclear Information System (INIS)

    Coleman, C.J.

    1989-01-01

    The Savannah River Plant (SRP) will apply for certification from the State of South Carolina to operate the SRP High-Level Waste Tanks. The permit application will be submitted as a RCRA Part B, Volume 16, entitled ''RCRA Part B Application For the F and H-Area Radioactive Waste Farm.'' RCRA regulations require that influent and effluent streams of hazardous waste sites be characterized to obtain an operating permit. The Waste Management Technology Department requested ADD to determine 21 components (including pH and weight percent solids) in the current influent streams to SRP High-Level Waste Tanks. The analyses will be used to supplement existing data on the composition of High-Level Waste. Effluent streams, which will feed Saltstone and the DWPF, will be analyzed when they are produced. This report contains the data obtained from analyzing key influent streams to SRP High-Level Waste Tanks. The precision of the data and the analytical methods that were used are also discussed

  11. Site-Specific Waste Management Instruction - 100-DR-1 Group 2 Sites

    International Nuclear Information System (INIS)

    Jackson, R.W.

    1998-01-01

    This site-specific waste management instruction (SSWMI) provides guidance for the management of wastes that may be generated during the excavation and remediation of the 100-DR-1 Group 2 sites. The management of waste generated as a result of these activities will be as directed in this SSWMI. This SSWMI will be revised to incorporate guidance for management of wastes encountered that are not addressed in this SSWMI

  12. Hazardous and mixed waste management at UMTRA sites

    International Nuclear Information System (INIS)

    Hampill, H.G.

    1988-01-01

    During the early stages of the Uranium Mill Tailings Remedial Action Project, there were some serious questions regarding the ownership of and consequently the responsibility for disposal of hazardous wastes at UMTRA sites. In addition to State and Indian Tribe waste disposal regulations, UMTRA must also conform to guidelines established by the NRC, OSHA, EPA, and DOT. Because of the differing regulatory thrusts of these agencies, UMTRA has to be vigilant in order to ensure that the disposal of each parcel of waste material is in compliance with all regulations. Mixed-waste disposal presents a particularly difficult problem. No single agency is willing to lay claim to the regulation of mixed-wastes, and no conventional waste disposal facility is willing to accept it. Consequently, the disposal of each lot of mixed-waste at UMTRA sites must be handled on a case by case basis. A recently published position paper which spells out UMTRA policy on waste materials indicates that wastes found at UMTRA sites are either residual radioactive wastes, or mixed-wastes, or for the disposal of hazardous waste is determined by the time the original material arrived. If it arrived prior to the termination of the AEC uranium supply contract, its disposal is the responsibility of UMTRA. If it arrived after the end of the contract, the responsibility for disposal lies with the former operator

  13. 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

  14. Screening criteria for siting waste management facilities: Regional Management Plan

    International Nuclear Information System (INIS)

    1986-01-01

    The Midwest Interstate Low-Level Radioactive Waste Commission (Midwest Compact) seeks to define and place into operation a system for low-level waste management that will protect the public health and safety and the environment from the time the waste leaves its point of origin. Once the system is defined it will be necessary to find suitable sites for the components of that waste management system. The procedure for siting waste management facilities that have been chosen by the compact is one in which a host state is chosen for each facility. The host state is then given the freedom to select the site. Sites will be needed of low-level waste disposal facilities. Depending on the nature of the waste management system chosen by the host state, sites may also be needed for regional waste treatment facilities, such as compactors or incinerators. This report provides example criteria for use in selecting sites for low-level radioactive waste treatment and disposal facilities. 14 refs

  15. Site remediation technologies and environmental management practices in the utility industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    Sessions covered: chemical oxidation; DNAPL and source management; regulatory perspectives and state programs; manufactured gas plant site management; sediments, cyanides, and other issues at MGP sites; biotechnology applications; agricultural waste issues; risk communication and bioremediation; air emissions and air toxics management; project management and redevelopment; environmentally acceptable endpoint and risk-based site management; site assessment, background concentration and closure; risk communication and beneficial use by recycling; PCB and RCRA issues; and phytoremediation and bioremediation of wastes.

  16. 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

  17. Cleanup Verification Package for the 300 VTS Waste Site

    International Nuclear Information System (INIS)

    Clark, S.W.; Mitchell, T.H.

    2006-01-01

    This cleanup verification package documents completion of remedial action for the 300 Area Vitrification Test Site, also known as the 300 VTS site. The site was used by Pacific Northwest National Laboratory as a field demonstration site for in situ vitrification of soils containing simulated waste

  18. Cleanup Verification Package for the 300 VTS Waste Site

    Energy Technology Data Exchange (ETDEWEB)

    S. W. Clark and T. H. Mitchell

    2006-03-13

    This cleanup verification package documents completion of remedial action for the 300 Area Vitrification Test Site, also known as the 300 VTS site. The site was used by Pacific Northwest National Laboratory as a field demonstration site for in situ vitrification of soils containing simulated waste.

  19. 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.

  20. 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.

  1. Hazardous waste shipment data collection from DOE sites

    International Nuclear Information System (INIS)

    Page, L.A.; Kirkpatrick, T.D.; Stevens, L.

    1992-01-01

    Past practices at the US Department of Energy (DOE) sites for offsite release of hazardous waste are being reviewed to determine if radioactively contaminated hazardous wastes were released to commercial treatment, storage, and disposal facilities. Records indicating the presence of radioactivity in waste shipped to and treated at a commercial incineration facility led to a ban on offsite hazardous waste shipments and investigation of past practices for offsite release of hazardous waste from the DOE sites. A House of Representatives Interior and Insular Affairs Committee oversight hearing on potentially contaminated waste shipments to commercial facilities concluded that the main issue was the lack of a uniform national standard to govern disposal of mixed waste

  2. Results of Phase I groundwater quality assessment for single-shell tank waste management areas T and TX-TY at the Hanford Site

    International Nuclear Information System (INIS)

    Hodges, F.N.

    1998-01-01

    Pacific Northwest National Laboratory (PNNL) conducted a Phase I, Resource Conservation and Recovery Act of 1976 (RCRA) groundwater quality assessment for the Richland Field Office of the U.S. Department of Energy (DOE-RL) under the requirements of the Federal Facility Compliance Agreement. The purpose of the investigation was to determine if the Single-Shell Tank Waste Management Areas (WMAs) T and TX-TY have impacted groundwater quality. Waste Management Areas T and TX-TY, located in the northern part of the 200 West Area of the Hanford Site, contain the 241-T, 241-TX, and 241-TY tank farms and ancillary waste systems. These two units are regulated under RCRA interim-status regulations (under 40 CFR 265.93) and were placed in assessment groundwater monitoring because of elevated specific conductance in downgradient wells. Anomalous concentrations of technetium-99, chromium, nitrate, iodine-129, and cobalt-60 also were observed in some downgradient wells. Phase I assessment, allowed under 40 CFR 265, provides the owner-operator of a facility with the opportunity to show that the observed contamination has a source other than the regulated unit. For this Phase I assessment, PNNL evaluated available information on groundwater chemistry and past waste management practices in the vicinity of WMAs T and TX-TY. Background contaminant concentrations in the vicinity of WMAs T and TX-TY are the result of several overlapping contaminant plumes resulting from past-practice waste disposal operations. This background has been used as baseline for determining potential WMA impacts on groundwater

  3. On-site waste storage assuring the success of on-site, low-level nuclear waste storage

    International Nuclear Information System (INIS)

    Preston, E.L.

    1986-01-01

    Waste management has reached paramount importance in recent years. The successful management of radioactive waste is a key ingredient in the successful operation of any nuclear facility. This paper discusses the options available for on-site storage of low-level radioactive waste and those options that have been selected by the Department of Energy facilities operated by Martin Marietta Energy Systems, Inc. in Oak Ridge, Tennessee. The focus of the paper is on quality assurance (QA) features of waste management activities such as accountability and retrievability of waste materials and waste packages, retrievability of data, waste containment, safety and environmental monitoring. Technical performance and careful documentation of that performance are goals which can be achieved only through the cooperation of numerous individuals from waste generating and waste managing organizations, engineering, QA, and environmental management

  4. Waste certification review program at the Savannah River Site

    International Nuclear Information System (INIS)

    Faulk, G.W.; Kinney, J.C.; Knapp, D.C.; Burdette, T.E.

    1996-01-01

    After approving the waste certification programs for 45 generators of low-level radioactive and mixed waste, Westinghouse Savannah River Company (WSRC) moved forward to implement a performance-based approach for assuring that approved waste generators maintain their waste certification programs. WSRC implemented the Waste Certification Review Program, which is comprised of two sitewide programs, waste generator self-assessments and Facility Evaluation Board reviews, integrated with the WSRC Solid Waste Management Department Waste Verification Program Evaluations. The waste generator self-assessments ensure compliance with waste certification requirements, and Facility Evaluation Board reviews provide independent oversight of generators' waste certification programs. Waste verification evaluations by the TSD facilities serve as the foundation of the program by confirming that waste contents and generator performance continue to meet waste acceptance criteria (WSRC 1994) prior to shipment to treatment, storage, and disposal facilities. Construction of the Savannah River Site (SRS) was started by the US Government in 1950. The site covers approximately 300 square miles located along the Savannah River near Aiken, South Carolina. It is operated by the US Department of Energy (DOE). Operations are conducted by managing and operating contractors, including the Westinghouse Savannah River Company (WSRC). Historically, the primary purpose of the SRS was to produce special nuclear materials, primarily plutonium and tritium. In general, low-level radioactive and mixed waste is generated through activities in operations. Presently, 47 SRS facilities generate low-level radioactive and mixed waste. The policies, guidelines, and requirements for managing these wastes are determined by DOE and are reflected in DOE Order 5820.2A (US DOE 1988)

  5. Hanford Site waste treatment/storage/disposal integration

    International Nuclear Information System (INIS)

    MCDONALD, K.M.

    1999-01-01

    In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps

  6. Savannah River Site Approved Site Treatment Plan, 1998 Annual Update (U)

    International Nuclear Information System (INIS)

    Lawrence, B.; Berry, M.

    1998-03-01

    The U.S. Department of Energy, Savannah River Operations Office (DOE- SR),has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume I. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore,pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE's requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021.Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW.The Compliance Plan Volume (Volume I) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information

  7. 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

  8. A history of solid waste packaging at the Hanford Site

    International Nuclear Information System (INIS)

    Duncan, D.R.; Weyns-Rollosson, D.I.; Pottmeyer, J.A.; Stratton, T.J.

    1995-02-01

    Since the initiation of the defense materials product mission, a total of more than 600,000 m 3 of radioactive solid waste has been stored or disposed at the US Department of Energy's (DOE) Hanford Site, located in southeastern Washington State. As the DOE complex prepares for its increasing role in environmental restoration and waste remediation, the characterization of buried and retrievably stored waste will become increasingly important. Key to this characterization is an understanding of the standards and specifications to which waste was packaged; the regulations that mandated these standards and specifications; the practices used for handling and packaging different waste types; and the changes in these practices with time

  9. Savannah River Site Waste Management Program Plan, FY 1993

    International Nuclear Information System (INIS)

    1993-06-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report on facilities being used to manage wastes, forces acting to change current waste management (WM) systems, and how operations are conducted. This document also reports on plans for the coming fiscal year and projects activities for several years beyond the coming fiscal year to adequately plan for safe handling and disposal of radioactive wastes generated at the Savannah River Site (SRS) and for developing technology for improved management of wastes

  10. An approach for sampling solid heterogeneous waste at the Hanford Site waste receiving and processing and solid waste projects

    International Nuclear Information System (INIS)

    Sexton, R.A.

    1993-03-01

    This paper addresses the problem of obtaining meaningful data from samples of solid heterogeneous waste while maintaining sample rates as low as practical. The Waste Receiving and Processing Facility, Module 1, at the Hanford Site in south-central Washington State will process mostly heterogeneous solid wastes. The presence of hazardous materials is documented for some packages and unknown for others. Waste characterization is needed to segregate the waste, meet waste acceptance and shipping requirements, and meet facility permitting requirements. Sampling and analysis are expensive, and no amount of sampling will produce absolute certainty of waste contents. A sampling strategy is proposed that provides acceptable confidence with achievable sampling rates

  11. Public reactions to nuclear waste: Citizens' views of repository siting

    International Nuclear Information System (INIS)

    Rosa, E.A.

    1993-01-01

    This book presents revised and updated papers from a panel of social scientists, at the 1989 AAAS meetings, that examined the public's reactions to nuclear waste disposal and the repository siting process. The papers report the results of original empirical research on citizens' views of nuclear waste repository siting. Topics covered include the following: content analysis of public testimony; sources of public concern about nuclear waste disposal in Texas agricultural communities; local attitudes toward high-level waste repository at Hanford; perceived risk and attitudes toward nuclear wastes; attitudes of Nevada urban residents toward a nuclear waste repository; attitudes of rural community residents toward a nuclear waste respository. An introductory chapter provides background and context, and a concluding chapter summarizes the implications of the reports. Two additional chapters cover important features of high-level waste disposal: long term trends in public attitudes toward nuclear energy and nuclear waste policy and assessment of the effects on the Los Vegas convention business if a high-level nuclear waste depository were sited in Nevada

  12. Estimating the water table under the Radioactive Waste Management Site in Area 5 of the Nevada Test Site: The Dupuit-Forcheimer approximation

    International Nuclear Information System (INIS)

    Lindstrom, F.T.; Barker, L.E.; Cawlfield, D.E.; Daffern, D.D.; Dozier, B.L.; Emer, D.F.; Strong, W.R.

    1992-01-01

    To adequately manage the low level nuclear waste (LLW) repository in Area 5 of the Nevada Test Site (NTS), a knowledge of the water table under the site is paramount. The estimated thickness of the arid intermountain basin alluvium is roughly 900 feet. Very little reliable water table data for Area 5 currently exists. The Special Projects Section of the Reynolds Electrical ampersand Engineering Co., Inc. Waste Management Department is currently formulating a long-range drilling and sampling plan in support of a Resource Conservation Recovery Act (RCRA) Part B permit waiver for groundwater monitoring and liner systems. An estimate of the water table under the LLW repository, called the Radioactive Waste Management Site (RWMS) in Area 5, is needed for the drilling and sampling plan. Very old water table elevation estimates at about a dozen widely scattered test drill holes, as well as water wells, are available from declassified US Geological Survey, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory drilling logs. A three-dimensional steady-state water-flow equation for estimating the water table elevation under a thick, very dry vadose zone is developed using the Dupuit assumption. A prescribed positive vertical downward infiltration/evaporation condition is assumed at the atmosphere/soil interface. An approximation to the square of the elevation head, based upon multivariate cubic interpolation methods, is introduced. The approximate is forced to satisfy the governing elliptic (Poisson) partial differential equation over the domain of definition. The remaining coefficients are determined by interpolating the water table at eight ''boundary point.'' Several realistic scenarios approximating the water table under the RWMS in Area 5 of the NTS are discussed

  13. 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

  14. SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    S. C. Khamankar

    2000-06-20

    The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

  15. SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    S. C. Khamankar

    2000-01-01

    The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

  16. Workplan/RCRA Facility Investigation/Remedial Investigation Report for the Old Radioactive Waste Burial Ground 643-E, S01-S22 - Volume I - Text and Volume II - Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Conner, K.R.

    2000-12-12

    This document presents the assessment of environmental impacts resulting from releases of hazardous substances from the facilities in the Old Radioactive Waste Burial Ground 643-E, including Solvent Tanks 650-01E to 650-22E, also referred to as Solvent Tanks at the Savannah River Site, Aiken, South Carolina.

  17. Historical research in the Hanford site waste cleanup

    International Nuclear Information System (INIS)

    Gerber, Michele S.

    1992-01-01

    This paper will acquaint the audience with role of historical research in the Hanford Site waste cleanup - the largest waste cleanup endeavor ever undertaken in human history. There were no comparable predecessors to this massive waste remediation effort, but the Hanford historical record can provide a partial road map and guide. It can be, and is, a useful tool in meeting the goal of a successful, cost-effective, safe and technologically exemplary waste cleanup. The Hanford historical record is rich and complex. Yet, it poses difficult challenges, in that no central and complete repository or data base exists, records contain obscure code words and code numbers, and the measurement systems and terminology used in the records change many times over the years. Still, these records are useful to the current waste cleanup in technical ways, and in ways that extend beyond a strictly scientific aspect. Study and presentations of Hanford Site history contribute to the huge educational and outreach tasks of helping the Site's work force deal with 'culture change' and become motivated for the cleanup work that is ahead, and of helping the public and the regulators to place the events at Hanford in the context of WWII and the Cold War. This paper traces historical waste practices and policies as they changed over the years at the Hanford Site, and acquaints the audience with the generation of the major waste streams of concern in Hanford Site cleanup today. It presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Examples of the strengths and limitations of the

  18. Characteristics of transuranic waste at Department of Energy sites

    International Nuclear Information System (INIS)

    Jensen, R.T.; Wilkinson, F.J. III.

    1983-05-01

    This document reports data and information on TRU waste from all DOE generating and storage sites. The geographical location of the sites is shown graphically. There are four major sections in this document. The first three cover the TRU waste groups known as Newly Generated, Stored, and Buried Wastes. Subsections are included under Newly Generated and Stored on contact-handled and remote-handled waste. These classifications of waste are defined, and the current or expected totals of each are given. Figure 1.3 shows the total amount of Buried and Stored TRU waste. Preparation of this document began in 1981, and most of the data are as of December 31, 1980. In a few cases data were reported to December 31, 1981, and these have been noted. The projections in the Newly Generated section were made, for the most part, at the end of 1981

  19. Waste treatment at the La Hague and Marcoule sites

    International Nuclear Information System (INIS)

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema's plants

  20. Waste treatment at the La Hague and Marcoule sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

  1. Evaluating the potential of process sites for waste heat recovery

    International Nuclear Information System (INIS)

    Oluleye, Gbemi; Jobson, Megan; Smith, Robin; Perry, Simon J.

    2016-01-01

    Highlights: • Analysis considers the temperature and duties of the available waste heat. • Models for organic Rankine cycles, absorption heat pumps and chillers proposed. • Exploitation of waste heat from site processes and utility systems. • Concept of a site energy efficiency introduced. • Case study presented to illustrate application of the proposed methodology. - Abstract: As a result of depleting reserves of fossil fuels, conventional energy sources are becoming less available. In spite of this, energy is still being wasted, especially in the form of heat. The energy efficiency of process sites (defined as useful energy output per unit of energy input) may be increased through waste heat utilisation, thereby resulting in primary energy savings. In this work, waste heat is defined and a methodology developed to identify the potential for waste heat recovery in process sites; considering the temperature and quantity of waste heat sources from the site processes and the site utility system (including fired heaters and, the cogeneration, cooling and refrigeration systems). The concept of the energy efficiency of a site is introduced – the fraction of the energy inputs that is converted into useful energy (heat or power or cooling) to support the methodology. Furthermore, simplified mathematical models of waste heat recovery technologies using heat as primary energy source, including organic Rankine cycles (using both pure and mixed organics as working fluids), absorption chillers and absorption heat pumps are developed to support the methodology. These models are applied to assess the potential for recovery of useful energy from waste heat. The methodology is illustrated for an existing process site using a case study of a petroleum refinery. The energy efficiency of the site increases by 10% as a result of waste heat recovery. If there is an infinite demand for recovered energy (i.e. all the recoverable waste heat sources are exploited), the site

  2. Hanford Site Solid Waste Landfill permit application. Revision 1

    International Nuclear Information System (INIS)

    1993-01-01

    Both nonhazardous and nonradioactive sanitary solid waste are generated at the Hanford Site. This permit application describes the manner in which the Solid Waste Landfill will be operated. A description is provided of the landfill, including applicable locational, general facility, and landfilling standards. The characteristics and quantity of the waste disposed of are discussed. The regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill are reviewed. A plan is included of operation, closure, and postclosure. This report addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill is discussed

  3. Expected brine movement at potential nuclear waste repository salt sites

    International Nuclear Information System (INIS)

    McCauley, V.S.; Raines, G.E.

    1987-08-01

    The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m 3 brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs

  4. Intrusion scenarios in fusion waste disposal sites

    International Nuclear Information System (INIS)

    Zucchetti, M.; Zucchetti, M.; Rocco, P.

    1998-01-01

    Results of analyses on human intrusions into repositories of fusion radioactive waste are presented. The main topics are: duration of the institutional control, occurrence of intrusion, intrusion scenarios, acceptable risk limits and probabilistic data. Application to fusion waste repositories is implemented with a computational model: wells drilling is considered as the possible scenario. Doses and risks to intruder for different SEAFP-2 cases turn out to be very small. No intervention to reduce the hazard is necessary. (authors)

  5. Intrusion scenarios in fusion waste disposal sites

    Energy Technology Data Exchange (ETDEWEB)

    Zucchetti, M. [European Commission, JRC, Institute for Advanced Material, Ispra, Vatican City State, Holy See (Italy); Zucchetti, M.; Rocco, P. [Energetics Dept., Polytechnic of Turin (Italy)

    1998-07-01

    Results of analyses on human intrusions into repositories of fusion radioactive waste are presented. The main topics are: duration of the institutional control, occurrence of intrusion, intrusion scenarios, acceptable risk limits and probabilistic data. Application to fusion waste repositories is implemented with a computational model: wells drilling is considered as the possible scenario. Doses and risks to intruder for different SEAFP-2 cases turn out to be very small. No intervention to reduce the hazard is necessary. (authors)

  6. Status of siting studies for a near surface repository site for radioactive wastes in the Philippines

    International Nuclear Information System (INIS)

    Valdezco, E.M.; Palattao, M.V.B.; Marcelo, E.A.; Caseria, E.S.; Venida, L.L.; Cruz, J.M. dela

    2002-01-01

    The Philippines, through the Philippine Nuclear Research Institute (PNRI), decided to conduct a study on siting a low level radioactive waste disposal facility. The infrastructure set up for this purpose, the radioactive waste disposal concept, the overall siting process, the methodology applied and preliminary results obtained are described in this paper. (author)

  7. Macroencapsulated and elemental lead mixed waste sites report

    International Nuclear Information System (INIS)

    Kalia, A.; Jacobson, R.

    1996-09-01

    The purpose of this study was to compile a list of the Macroencapsulated (MACRO) and Elemental Lead (EL) Mixed Wastes sites that will be treated and require disposal at the Nevada Test Site within the next five to ten years. The five sites selected were: Hanford Site, Richland, Washington; Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho; Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee; Rocky Flats Environmental Technology (RF), Golden, Colorado; and Savannah River (SRS), Charleston, South Carolina. A summary of total lead mixed waste forms at the five selected DOE sites is described in Table E-1. This table provides a summary of total waste and grand total of the current inventory and five-year projected generation of lead mixed waste for each site. This report provides conclusions and recommendations for further investigations. The major conclusions are: (1) the quantity of lead mixed current inventory waste is 500.1 m 3 located at the INEL, and (2) the five sites contain several other waste types contaminated with mercury, organics, heavy metal solids, and mixed sludges

  8. The role of economic incentives in nuclear waste facility siting

    International Nuclear Information System (INIS)

    Davis, E.M.

    1986-01-01

    There is a need to provide some public benefit and/or reward for accepting a ''locally unwanted land use'' (LULU) facility such as a nuclear waste storage or disposal facility. This paper concludes that DOE, Congress and the states should immediately quantify an economic incentive for consideration ''up front'' by society on siting decisions for nuclear waste storage and disposal facilities

  9. Regulatory Support of Treatment of Savannah River Site Purex Waste

    International Nuclear Information System (INIS)

    Reid, L.T.

    2009-01-01

    This paper describes the support given by federal and state regulatory agencies to Savannah River Site (SRS) during the treatment of an organic liquid mixed waste from the Plutonium Extraction (Purex) process. The support from these agencies allowed (SRS) to overcome several technical and regulatory barriers and treat the Purex waste such that it met LDR treatment standards. (authors)

  10. Basic principles and criteria on radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Dlouhy, Z.; Kropikova, S.

    1980-01-01

    The basic principles are stated of radiation protection of the workers at radioactive waste disposal facilities, which must be observed in the choice of radioactive waste disposal sites. The emergency programme, the operating regulations and the safety report are specified. Workplace safety regulations are cited. (author)

  11. Description of the Northwest hazardous waste site data base and preliminary analysis of site characteristics

    International Nuclear Information System (INIS)

    Woodruff, D.L.; Hartz, K.E.; Triplett, M.B.

    1988-08-01

    The Northwest Hazardous Waste RD and D Center (the Center) conducts research, development, and demonstration (RD and D) activities for hazardous and radioactive mixed-waste technologies applicable to remediating sites in the states of Idaho, Montana, Oregon, and Washington. To properly set priorities for these RD and D activities and to target development efforts it is necessary to understand the nature of the sites requiring remediation. A data base of hazardous waste site characteristics has been constructed to facilitate this analysis. The data base used data from EPA's Region X Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) and from Preliminary Assessment/Site Investigation (PA/SI) forms for sites in Montana. The Center's data base focuses on two sets of sites--those on the National Priorities List (NPL) and other sites that are denoted as ''active'' CERCLIS sites. Active CERCLIS sites are those sites that are undergoing active investigation and analysis. The data base contains information for each site covering site identification and location, type of industry associated with the site, waste categories present (e.g., heavy metals, pesticides, etc.), methods of disposal (e.g., tanks, drums, land, etc.), waste forms (e.g., liquid, solid, etc.), and hazard targets (e.g., surface water, groundwater, etc.). As part of this analysis, the Northwest region was divided into three geographic subregions to identify differences in disposal site characteristics within the Northwest. 2 refs., 18 figs., 5 tabs

  12. Hanford Site waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    1994-05-01

    The Hanford Site WMin/P2 program is an organized, comprehensive, and continual effort to systematically reduce the quantity and toxicity of hazardous, radioactive, mixed, and sanitary wastes; conserve resources; and prevent or minimize pollutant releases to all environmental media from all Site activities. The Hanford Site WMin/P2 program plan reflects national and DOE waste minimization and pollution prevention goals and policies, and represents an ongoing effort to make WMin/P2 part of the Site operating philosophy. In accordance with these policies, a hierarchical approach to environmental management has been adopted and is applied to all types of polluting and waste generating activities. Pollution prevention and waste minimization through source reduction are first priority in the Hanford WMin/P2 program, followed by environmentally safe recycling. Treatment to reduce the quantity, toxicity, and/or mobility will be considered only when prevention or recycling are not possible or practical. Environmentally safe disposal is the last option

  13. Safety assessment for Area 5 radioactive-waste-management site

    International Nuclear Information System (INIS)

    Hunter, P.H.; Card, D.H.; Horton, K.

    1982-09-01

    The Area 5 Radioactive Waste Management Safety Assessment Document contains evaluations of site characteristics, facilities, and operating practices that contribute to the safe handling, storage, and disposal of low-level radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. A separate section considers facilities and operating practices such as monitoring, storage/disposal criteria, site maintenance, equipment, and support. The section also considers the transportation and waste handling requirements supporting the new Greater Confinement Disposal Facility (GCDF), GCDF demonstration project, and other requirements for the safe handling, storage, and disposal of low-level radioactive wastes. Finally, the document provides an analysis of releases and an assessment of the near-term operational impacts and dose commitments to operating personnel and the general public from normal operations and anticipated accidental occurrences. The conclusion of this report is that the Area 5 Radioactive Waste Management Site is suitable for low-level radioactive waste handling, storage, and disposal. Also, the new GCDF demonstration project will not affect the overall safety of the Area 5 Radioactive Waste Management Site

  14. Providing an integrated waste management strategy and operation focused on project end states at the Hanford site

    International Nuclear Information System (INIS)

    Blackford, L.

    2009-01-01

    CH2M HILL Plateau Remediation Company (CHPRC) is the U.S. Department of Energy's (DOE) contractor responsible for the safe, environmental cleanup of the Central Plateau of the Hanford Site. The 586-square-mile Hanford Site is located along the Columbia River in southeastern Washington State. A plutonium production complex with nine nuclear reactors and associated processing facilities, Hanford played a pivotal role in the nation's defense for more than 40 years, beginning in the 1940's with the Manhattan Project. Today, under the direction of the DOE, Hanford is engaged in the world's largest environmental cleanup project. The Plateau Remediation Contract (PRC) is a 10-year project paving the way for closure of the Hanford Site through demolition of the Plutonium Finishing Plant; remediation of six burial grounds and 11 groundwater systems; treatment of 43.8 meters of sludge; and disposition of 8,200 meters of transuranic waste, 800 spent nuclear material containers, 2,100 metric tons of spent nuclear fuel, and two reactors. The $4.5 billion project, funded through the U.S. DOE Office of Environmental Management, focuses equally on reducing risks to workers, the public, and the environment and on protecting the Columbia River. The DOE, which operates the Hanford Site, the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology) signed a comprehensive cleanup and compliance agreement on May 15, 1989. The Hanford Federal Facility Agreement and Consent Order, or Tri-Party Agreement (TPA), is an agreement for achieving compliance with the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) remedial action provisions and with the Resource Conservation and Recovery Act (RCRA) treatment, storage, and disposal (TSD) unit regulations and corrective action provisions . More specifically, the Tri-Party Agreement does the following: 1) defines and ranks CERCLA and RCRA cleanup commitments; 2) establishes

  15. 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

  16. HWMA/RCRA Closure Plan for the Fluorinel Dissolution Process Makeup and Cooling and Heating Systems Voluntary Consent Order SITE-TANK-005 Action Plan Tank Systems INTEC-066, INTEC-067, INTEC-068, and INTEC-072

    Energy Technology Data Exchange (ETDEWEB)

    M.E. Davis

    2007-05-01

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the fluorinel dissolution process makeup and cooling and heating systems located in the Fluorinel Dissolution Process and Fuel Storage Facility (CPP-666), Idaho Nuclear Technology and Engineering Center, Idaho National Laboratory Site, was developed to meet milestones established under the Voluntary Consent Order. The systems to be closed include waste piping associated with the fluorinel dissolution process makeup systems. This closure plan presents the closure performance standards and methods of achieving those standards.

  17. HWMA/RCRA Closure Plan for the Fluorinel Dissolution Process Makeup and Cooling and Heating Systems Voluntary Consent Order SITE-TANK-005 Action Plan Tank Systems INTEC-066, INTEC-067, INTEC-068, and INTEC-072

    International Nuclear Information System (INIS)

    M.E. Davis

    2007-01-01

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the fluorinel dissolution process makeup and cooling and heating systems located in the Fluorinel Dissolution Process and Fuel Storage Facility (CPP-666), Idaho Nuclear Technology and Engineering Center, Idaho National Laboratory Site, was developed to meet milestones established under the Voluntary Consent Order. The systems to be closed include waste piping associated with the fluorinel dissolution process makeup systems. This closure plan presents the closure performance standards and methods of achieving those standards

  18. Hazardous waste market and technology trends

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    What forces are currently driving the growth of the hazardous waste remediation market? Which factors will control the development of cleanup technologies during the next decade? At what types of sites are various technologies being applied? In an effort to answer these questions, EPA has produced an overview of trends in the demand for remedial technologies at CERCLA, RCRA corrective action, underground storage tank (UST), and other cleanup sites across the United States. The 160-page document, entitled Cleaning Up the Nation's Waste Sites: Markets and Technology Trends, was developed by EPA's Office of Solid Waste and Emergency Response. Highlights from the report are presented below. 1 ref., 2 figs., 1 tab

  19. A Bayesian sampling strategy for hazardous waste site characterization

    International Nuclear Information System (INIS)

    Skalski, J.R.

    1987-12-01

    Prior knowledge based on historical records or physical evidence often suggests the existence of a hazardous waste site. Initial surveys may provide additional or even conflicting evidence of site contamination. This article presents a Bayes sampling strategy that allocates sampling at a site using this prior knowledge. This sampling strategy minimizes the environmental risks of missing chemical or radionuclide hot spots at a waste site. The environmental risk is shown to be proportional to the size of the undetected hot spot or inversely proportional to the probability of hot spot detection. 12 refs., 2 figs

  20. 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

  1. Intruder scenarios for site-specific waste classification

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.

    1988-01-01

    The US Department of Energy (DOE) is currently revising its low-level radioactive waste (LLW) management requirements and guidelines for waste generated at its facilities that support defense missions. Specifically, draft DOE 5820.2A, Chapter 3, describes the purpose, policy, and requirements necessary for the management of defense LLW. The draft DOE policy calls for DOE LLW operations to be managed to protect the health and safety of the public, preserve the environment, and ensure that no remedial action will be necessary after termination of operations. The requirements and guidelines apply to radioactive wastes but are also intended to apply to mixed hazardous and radioactive wastes as defined in draft DOE 5400.5, Hazardous and Radioactive Mixed Waste. The basic approach used by DOE is to establish overall performance objectives in terms of ground-water protection and public radiation dose limits and to require site-specific performance assessments to determine compliance. As a result of these performance assessments, each site shall develop waste acceptance criteria that define the allowable quantities and concentrations of specific radioisotopes. Additional limitations on waste disposal design, waste form, and waste treatment shall also be developed on a site-specific basis. As a key step in the site-specific performance assessments, an evaluation must be conducted of potential radiation doses to intruders who may inadvertently move onto a closed DOE LLW disposal site after loss of institutional controls must be conducted. This paper describes the types of intruder scenarios that should be considered when performing this step of the site-specific performance assessment

  2. 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

  3. Low-level waste disposal site selection demonstration

    International Nuclear Information System (INIS)

    Rogers, V.C.

    1984-01-01

    This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

  4. Hazard ranking systems for chemical wastes and chemical waste sites

    International Nuclear Information System (INIS)

    Waters, R.D.; Parker, F.L.; Crutcher, M.R.

    1991-01-01

    Hazardous materials and substances have always existed in the environment. Mankind has evolved to live with some degree of exposure to toxic materials. Until recently the risk has been from natural toxins or natural background radiation. While rapid technological advances over the past few decades have improved the lifestyle of our society, they have also dramatically increased the availability, volume and types of synthetic and natural hazardous materials. Many of their effects are as yet uncertain. Products and manufacturing by-products that no longer serve a useful purpose are deemed wastes. For some waste products land disposal will always be their ultimate fate. Hazardous substances are often included in the waste products. One needs to classify wastes by degree of hazard (risk). Risk (degree of probability of loss) is usually defined for risk assessment as probability of an occurrence times the consequences of the occurrence. Perhaps even more important than the definition of risk is the choice of a risk management strategy. The choice of strategy will be strongly influenced by the decision criteria used. Those decision criteria could be utility (the greatest happiness of the greatest number), rights or technology based or some combination of the three. It is necessary to make such choices about the definition of risks and criteria for management. It is clear that these are social (i.e., political) and value choices and science has little to say on this matter. This is another example of what Alvin Weinberg has named Transcience where the subject matter is scientific and technical but the choices are social, political and moral. This paper shall deal only with the scientific and technical aspects of the hazardous waste problem to create a hazardous substances classification system

  5. Verifying generator waste certification: NTS waste characterization QA requirements

    International Nuclear Information System (INIS)

    Williams, R.E.; Brich, R.F.

    1988-01-01

    Waste management activities managed by the US Department of Energy (DOE) at the Nevada Test Site (NTS) include the disposal of low-level wastes (LLW) and mixed waste (MW), waste which is both radioactive and hazardous. A majority of the packaged LLW is received from offsite DOE generators. Interim status for receipt of MW at the NTS Area 5 Radioactive Waste Management Site (RWMS) was received from the state of Nevada in 1987. The RWMS Mixed Waste Management Facility (MWMF) is expected to be operational in 1988 for approved DOE MW generators. The Nevada Test Site Defense Waste Acceptance Criteria and Certification Requirements (NVO-185, Revision 5) delineates waste acceptance criteria for waste disposal at the NTS. Regulation of the hazardous component of mixed waste requires the implementation of US Environmental Protection Agency (EPA) requirements pursuant to the Resource Conservation and Recovery Act (RCRA). Waste generators must implement a waste certification program to provide assurance that the disposal site waste acceptance criteria are met. The DOE/Nevada Operations Office (NV) developed guidance for generator waste certification program plans. Periodic technical audits are conducted by DOE/NV to assess performance of the waste certification programs. The audit scope is patterned from the waste certification program plan guidance as it integrates and provides a common format for the applicable criteria. The criteria focus on items and activities critical to processing, characterizing, packaging, certifying, and shipping waste

  6. Summary of tank waste physical properties at the Hanford Site

    International Nuclear Information System (INIS)

    Nguyen, Q.H.

    1994-04-01

    This report summarizes the physical parameters measured from Hanford Site tank wastes. Physical parameters were measured to determine the physical nature of the tank wastes to develop simulants and design in-tank equipment. The physical parameters were measured mostly from core samples obtained directly below tank risers. Tank waste physical parameters were collected through a database search, interviewing and selecting references from documents. This report shows the data measured from tank waste but does not describe how the analyses wee done. This report will be updated as additional data are measured or more documents are reviewed

  7. Physical sampling for site and waste characterization

    International Nuclear Information System (INIS)

    Bonnough, T.L.

    1996-01-01

    Physical sampling plays a basic role in high-level radioactive waste management program effort. The term ''physical sampling'' used here means collecting tangible, physical samples of soil, water, air, waste streams, or other materials. The industry defines the term ''physical sampling'' broadly to include measurements of physical conditions such as temperature, wind conditions, and pH, which are also often taken in a sample collection effort. Most environmental compliance actions are supported by the results of taking, recording, and analyzing physical samples and the measurements of physical conditions taken in association with sample collecting. Therefore, the when and how to take samples is needed to be known and planned

  8. Environmental Assessment: Waste Tank Safety Program, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1994-02-01

    The US Department of Energy (DOE) needs to take action in the near-term, to accelerate resolution of waste tank safety issues at the Hanford Site near the City of Richland, Washington, and reduce the risks associated with operations and management of the waste tanks. The DOE has conducted nuclear waste management operations at the Hanford Site for nearly 50 years. Operations have included storage of high-level nuclear waste in 177 underground storage tanks (UST), both in single-shell tank (SST) and double-shell tank configurations. Many of the tanks, and the equipment needed to operate them, are deteriorated. Sixty-seven SSTs are presumed to have leaked a total approximately 3,800,000 liters (1 million gallons) of radioactive waste to the soil. Safety issues associated with the waste have been identified, and include (1) flammable gas generation and episodic release; (2) ferrocyanide-containing wastes; (3) a floating organic solvent layer in Tank 241-C-103; (4) nuclear criticality; (5) toxic vapors; (6) infrastructure upgrades; and (7) interim stabilization of SSTs. Initial actions have been taken in all of these areas; however, much work remains before a full understanding of the tank waste behavior is achieved. The DOE needs to accelerate the resolution of tank safety concerns to reduce the risk of an unanticipated radioactive or chemical release to the environment, while continuing to manage the wastes safely

  9. Remaining Sites Verification Package for the 600-233 Waste Site, Vertical Pipe Near 100-B Electrical Laydown Area. Attachment to Waste Site Reclassification Form 2005-041

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2005-01-01

    The 600-233 waste site consisted of three small-diameter pipelines within the 600-232 waste site, including previously unknown diesel fuel supply lines discovered during site remediation. The 600-233 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

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

    International Nuclear Information System (INIS)

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

    1987-01-01

    Since passage of the 1984 amendments to the Resource Conservation and Recovery Act (RCRA), major changes have occurred in the regulation of hazardous waste. The US Environmental Protection Agency (EPA) has also greatly modified its interpretation of how these regulations apply to wastes from federal facilities, including defense wastes from US Department of Energy (DOE) sites. As a result, the regulatory distinctions between low-level radioactive waste (LLW) and hazardous waste are becoming blurred. This paper discusses recent statutory and regulatory changes and how they might affect the management of LLW at DOE facilities. 6 references

  11. A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

    International Nuclear Information System (INIS)

    England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

    1991-01-01

    Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal

  12. Approved Site Treatment Plan, Volumes 1 and 2. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Helmich, E.H.; Molen, G.; Noller, D.

    1996-03-22

    The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE`s requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information.

  13. Approved Site Treatment Plan, Volumes 1 and 2. Revision 4

    International Nuclear Information System (INIS)

    Helmich, E.H.; Molen, G.; Noller, D.

    1996-01-01

    The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE's requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information

  14. 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

  15. Forming artificial soils from waste materials for mine site rehabilitation

    Science.gov (United States)

    Yellishetty, Mohan; Wong, Vanessa; Taylor, Michael; Li, Johnson

    2014-05-01

    Surface mining activities often produce large volumes of solid wastes which invariably requires the removal of significant quantities of waste rock (overburden). As mines expand, larger volumes of waste rock need to be moved which also require extensive areas for their safe disposal and containment. The erosion of these dumps may result in landform instability, which in turn may result in exposure of contaminants such as trace metals, elevated sediment delivery in adjacent waterways, and the subsequent degradation of downstream water quality. The management of solid waste materials from industrial operations is also a key component for a sustainable economy. For example, in addition to overburden, coal mines produce large amounts of waste in the form of fly ash while sewage treatment plants require disposal of large amounts of compost. Similarly, paper mills produce large volumes of alkaline rejected wood chip waste which is usually disposed of in landfill. These materials, therefore, presents a challenge in their use, and re-use in the rehabilitation of mine sites and provides a number of opportunities for innovative waste disposal. The combination of solid wastes sourced from mines, which are frequently nutrient poor and acidic, with nutrient-rich composted material produced from sewage treatment and alkaline wood chip waste has the potential to lead to a soil suitable for mine rehabilitation and successful seed germination and plant growth. This paper presents findings from two pilot projects which investigated the potential of artificial soils to support plant growth for mine site rehabilitation. We found that pH increased in all the artificial soil mixtures and were able to support plant establishment. Plant growth was greatest in those soils with the greatest proportion of compost due to the higher nutrient content. These pot trials suggest that the use of different waste streams to form an artificial soil can potentially be used in mine site rehabilitation

  16. Low-Level Radioactive Waste siting simulation information package

    International Nuclear Information System (INIS)

    1985-12-01

    The Department of Energy's National Low-Level Radioactive Waste Management Program has developed a simulation exercise designed to facilitate the process of siting and licensing disposal facilities for low-level radioactive waste. The siting simulation can be conducted at a workshop or conference, can involve 14-70 participants (or more), and requires approximately eight hours to complete. The exercise is available for use by states, regional compacts, or other organizations for use as part of the planning process for low-level waste disposal facilities. This information package describes the development, content, and use of the Low-Level Radioactive Waste Siting Simulation. Information is provided on how to organize a workshop for conducting the simulation. 1 ref., 1 fig

  17. Identification of potential transuranic waste tanks at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Colburn, R.P.

    1995-05-05

    The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.

  18. Identification of potential transuranic waste tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Colburn, R.P.

    1995-01-01

    The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document

  19. Modular risk analysis for assessing multiple waste sites

    International Nuclear Information System (INIS)

    Whelan, G.; Buck, J.W.; Nazarali, A.

    1994-06-01

    Human-health impacts, especially to the surrounding public, are extremely difficult to assess at installations that contain multiple waste sites and a variety of mixed-waste constituents (e.g., organic, inorganic, and radioactive). These assessments must address different constituents, multiple waste sites, multiple release patterns, different transport pathways (i.e., groundwater, surface water, air, and overland soil), different receptor types and locations, various times of interest, population distributions, land-use patterns, baseline assessments, a variety of exposure scenarios, etc. Although the process is complex, two of the most important difficulties to overcome are associated with (1) establishing an approach that allows for modifying the source term, transport, or exposure component as an individual module without having to re-evaluate the entire installation-wide assessment (i.e., all modules simultaneously), and (2) displaying and communicating the results in an understandable and useable maimer to interested parties. An integrated, physics-based, compartmentalized approach, which is coupled to a Geographical Information System (GIS), captures the regional health impacts associated with multiple waste sites (e.g., hundreds to thousands of waste sites) at locations within and surrounding the installation. Utilizing a modular/GIS-based approach overcomes difficulties in (1) analyzing a wide variety of scenarios for multiple waste sites, and (2) communicating results from a complex human-health-impact analysis by capturing the essence of the assessment in a relatively elegant manner, so the meaning of the results can be quickly conveyed to all who review them

  20. Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal

    International Nuclear Information System (INIS)

    Feo, Giovanni De; Gisi, Sabino De

    2014-01-01

    Highlights: • Wasting land for the siting of hazardous waste landfills must be avoided. • The siting procedure is based on a land use map of potentially suitable areas. • All the waste facilities of the management system are simultaneously considered. • A case study is developed considering two multi-criteria techniques. • An innovative criteria weighting tool (PSW) is used in combination with the AHP. - Abstract: The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a “land use map of potentially suitable areas” for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the “Priority Scale”) in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method

  1. Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Feo, Giovanni De, E-mail: g.defeo@unisa.it [Department of Industrial Engineering, University of Salerno, via Giovanni Paolo II, 132, 84084 Fisciano, SA (Italy); Gisi, Sabino De [Italian National Agency for New Technologies, Energy and Sustainable Economic Development, ENEA, Water Resource Management Lab., via Martiri di Monte Sole 4, 40129 Bologna, BO (Italy)

    2014-11-15

    Highlights: • Wasting land for the siting of hazardous waste landfills must be avoided. • The siting procedure is based on a land use map of potentially suitable areas. • All the waste facilities of the management system are simultaneously considered. • A case study is developed considering two multi-criteria techniques. • An innovative criteria weighting tool (PSW) is used in combination with the AHP. - Abstract: The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a “land use map of potentially suitable areas” for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the “Priority Scale”) in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method.

  2. 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.

  3. 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

  4. Effectiveness evaluation of three RCRA caps at the Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Shevenell, L.A. [Nevada Bureau of Mines and Geology, Reno, NV (United States); Goldstrand, P.M. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Geological Sciences

    1994-01-01

    Because installation of Resource Conservation and Recovery Act (RCRA)- engineered caps is costly, it is prudent to evaluate the effectiveness of this procedure for hydrologically isolating contaminants. The objective for installation of five-part engineered caps at the Y-12 Plant was to (1) satisfy the regulatory compliance issues, (2) minimize the risk of direct contact with the wastes, and (3) reduce rainfall infiltration. Although the original objectives of installing the caps were not to alter groundwater flow, a potential effect of reducing infiltration is to minimize leaching, thus retarding groundwater contaminant migration from the site. Hence, cap effectiveness with respect to reduced groundwater contaminant migration is evaluated using groundwater data in this report. Based on the available data at the Y-12 capped areas, evaluation of cap effectiveness includes studying water level and chemical variability in nearby monitoring wells. Three caps installed during 1989 are selected for evaluation in this report. These caps are located in three significantly different hydrogeologic settings: overlying a karst aquifer (Chestnut Ridge Security Pits [CRSP]), overlying shales located on a hill slope (Oil Landfarm Waste Management Area [OLWMA]), and overlying shales in a valley floor which is a site of convergent groundwater flow (New Hope Pond [NHP]). Presumably, the caps have been effective in minimizing risk of direct contact with the wastes and halting direct rainfall infiltration into the sites over the extent of the capped areas, but no evidence is presented in this report to directly demonstrate this. The caps installed over the three sites appear to have had a minimal effect on groundwater contaminant migration from the respective sites. Following cap construction, no changes in the configuration of the water table were observed. Migration of contaminant plumes occurred at all three sites, apparently without regard to the timing of cap installation.

  5. Cleanup Verification Package for the 600-47 Waste Site

    International Nuclear Information System (INIS)

    Cutlip, M.J.

    2005-01-01

    This cleanup verification package documents completion of interim remedial action for the 600-47 waste site. This site consisted of several areas of surface debris and contamination near the banks of the Columbia River across from Johnson Island. Contaminated material identified in field surveys included four areas of soil, wood, nuts, bolts, and other metal debris

  6. In situ vitrification of buried waste sites

    International Nuclear Information System (INIS)

    Shade, J.W.; Thompson, L.E.; Kindle, C.H.

    1991-04-01

    In situ vitrification (ISV) is a remedial technology initially developed to treat soils contaminated with a variety of organics, heavy metals, and/or radioactive materials. Recent tests have indicated the feasibility of applying the process to buried wastes including containers, combustibles, and buried metals. In addition, ISV is being considered for application to the emplacement of barriers and to the vitrification of underground tanks. This report provides a review of some of the recent experiences of applying ISV in engineering-scale and pilot-scale tests to wastes containing organics, the Environmental Protection Agency (EPA) Toxic metals buried in sealed containers, and buried ferrous metals, with emphasis on the characteristics of the vitrified product and adjacent soil. 9 refs., 2 figs., 3 tabs

  7. Regulatory requirements for groundwater monitoring networks at hazardous waste sites

    International Nuclear Information System (INIS)

    Keller, J.F.

    1989-10-01

    In the absence of an explicit national mandate to protect groundwater quality, operators of active and inactive hazardous waste sites must use a number of statutes and regulations as guidance for detecting, correcting, and preventing groundwater contamination. The objective of this paper is to provide a framework of the technical and regulatory considerations that are important to the development of groundwater monitoring programs at hazardous waste sites. The technical site-specific needs and regulatory considerations, including existing groundwater standards and classifications, will be presented. 14 refs., 2 tabs

  8. Hanford Site Composite Analysis Technical Approach Description: Radionuclide Inventory and Waste Site Selection Process.

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, Will E.; Mehta, Sunil

    2017-09-13

    The updated Hanford Site Composite Analysis will provide an all-pathways dose projection to a hypothetical future member of the public from all planned low-level radioactive waste disposal facilities and potential contributions from all other projected end-state sources of radioactive material left at Hanford following site closure. Its primary purpose is to support the decision-making process of the U.S. Department of Energy (DOE) under DOE O 435.1-1, Radioactive Waste Management (DOE, 2001), related to managing low-level waste disposal facilities at the Hanford Site.

  9. TANK WASTE RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE

    International Nuclear Information System (INIS)

    DODD, R.A.

    2006-01-01

    One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the US Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60% of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring the waste to the DST system since 1997 as part of the interim stabilization program. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. This paper presents lessons learned from retrieval of tank waste at the Hanford Site and discusses how this information is used to optimize retrieval system efficiency, improve overall cost effectiveness of retrieval operations, and ensure that HFFACO requirements are met

  10. RCRA permitting strategies for the development of innovative technologies: Lessons from Hanford

    International Nuclear Information System (INIS)

    Gajewski, S.W.; Donaghue, J.F.

    1994-01-01

    The Hanford Site restoration is the largest waste cleanup operation in history. The Hanford plutonium production mission generated two-thirds of all the nuclear waste, by volume, in the Department of Energy (DOE) Complex. Cleanup challenges include not only large stored volumes of radioactive, hazardous, and mixed waste, but contaminated soil and groundwater and scores of major structures slated for decontamination, decommissioning, and demolition. DOE and its contractors will need to invent the technology required to do the job on a timetable driven by negotiated milestones, public concerns, and budgetary constraints. This paper will discuss the effort at Hanford to develop an integrated, streamlined strategy for compliance with the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) in the conduct of research, development, and demonstration (RD ampersand D) of innovative cleanup technologies. The aspects that will be discussed include the following: the genesis of the RD ampersand D permitting challenge at Hanford; permitting options in the existing regulatory framework; regulatory options that offered the best fit for Hanford RD ampersand D activities, and the problems associated with them; and conclusions and recommendations made to regulatory bodies

  11. 40 CFR Appendix D to Subpart E of... - Transport and Disposal of Asbestos Waste

    Science.gov (United States)

    2010-07-01

    ...-custody form signed by the generator. A chain-of-custody form may include the name and address of the generator, the name and address of the pickup site, the estimated quantity of asbestos waste, types of... calling the RCRA hotline: 1-800-424-9346 (382-3000 in Washington, DC). Some landfill owners or operators...

  12. 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

  13. Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal.

    Science.gov (United States)

    De Feo, Giovanni; De Gisi, Sabino

    2014-11-01

    The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a "land use map of potentially suitable areas" for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the "Priority Scale") in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method. Copyright © 2014 Elsevier Ltd. All rights reserved.

  14. Preliminary site characterization at Beishan northwest China-A potential site for China's high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Wang Ju; Su Rui; Xue Weiming; Zheng Hualing

    2004-01-01

    Chinese nuclear power plants,radioactive waste and radioactive waste disposal are introduced. Beishan region (Gansu province,Northwest China)for high-level radioactive waste repository and preliminary site characterization are also introduced. (Zhang chao)

  15. On site clean up with a hazardous waste incinerator

    International Nuclear Information System (INIS)

    Cross, F.L. Jr.; Tessitore, J.L.

    1987-01-01

    The Army Corps of Engineers and the EPA have determined that on-site incineration for the detoxification of soils, sediments, and sludges is a viable, safe, and economic alternative. This paper discusses an approach to on-site incineration as a method of detoxification of soils/sediments contaminated with organic hazardous wastes. Specifically, this paper describes the procedures used to evaluate on-site incineration at a large Superfund site with extensive PCB contaminated soils and sediments. The paper includes the following: (1) a discussion of site waste quantities and properties, (2) a selection of an incineration technology with a resulting concept and design, (3) a discussion of incinerator permitting requirements, (4) discussion and rationale for an incinerator sub-scale testing approach, and (5) analysis of on-site incineration cost

  16. Microbial effects on radioactive wastes at SLB sites

    International Nuclear Information System (INIS)

    Colombo, P.

    1982-01-01

    The objectives of this study are to determine the significance of microbial degradation of organic wastes on radionuclide migration on shallow land burial for humid and arid sites, establish which mechanisms predominate and ascertain the conditions under which these mechanisms operate. Factors contolling gaseous eminations from low-level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide and possibly hydrogen from the site stems from the inclusion of tritium and/or 14 C into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste materials, primary emphasis of the study involved on examination of the biochemical pathways producing methane, carbon dioxide and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Although the methane and carbon dioxide production rate indicates the degradation rate of the organic substances in the waste, it does not predict the methane evolution rate from the trench site. Methane fluxes from the soil surface are equivalent to the net synthesis minus the quantity oxidized by the microbial community as the gas passes through the soil profile. Gas studies were performed at three commercial low-level radioactive waste disposal sites (West Valley, New York; Beatty, Nevada; Maxey Flats, Kentucky) during the period 1976 to 1978. The results of these studies are presented. 3 tables

  17. Mathematical model of the Savannah River Site waste tank farm

    International Nuclear Information System (INIS)

    Smith, F.G. III.

    1991-01-01

    A mathematical model has been developed to simulate operation of the waste tank farm and the associated evaporator systems at the Savannah River Site. The model solves material balance equations to predict the volumes of liquid waste, salt, and sludge for all of the tanks within each of the evaporator systems. Additional logic is included to model the behavior of waste tanks not directly associated with the evaporators. Input parameters include the Material Management Plan forecast of canyon operations, specification of other waste sources for the evaporator systems, evaporator operating characteristics, and salt and sludge removal schedules. The model determines how the evaporators will operate, when waste transfers can be made, and waste accumulation rates. Output from the model includes waste tank contents, summaries of systems operations, and reports of space gain and the remaining capacity to store waste materials within the tank farm. Model simulations can be made to predict waste tank capacities on a daily basis for up to 20 years. The model is coded as a set of three computer programs designed to run on either IBM compatible or Apple Macintosh II personal computers

  18. Land suitability maps for waste disposal siting

    International Nuclear Information System (INIS)

    Hrasna, M.

    1996-01-01

    The suitability of geoenvironment for waste disposal depends mainly on its stability and on the danger of groundwater pollution. Besides them, on the land suitability maps for the given purpose also those factors of the factors of the geoenvironment and the landscape should be taken into account, which enable another way of the land use, such as mineral resources, water resources, fertile soils, nature reserves, etc. On the base of the relevant factors influence evaluation - suitable, moderately suitable and unsuitable territorial units are delimited on the maps. The different way of various scale maps compilation is applied, taken into account their different representing feasibilities. (authors)

  19. Nevada Test Site 2008 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

    International Nuclear Information System (INIS)

    2009-01-01

    Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2008 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities

  20. Delegated Democracy. The Siting of Swedish Nuclear Waste

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, Hanna Sofia (Stockholm Univ., SCORE, SE-106 91 Stockholm (Sweden))

    2009-12-15

    This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

  1. Conflict resolution in low-level waste facility siting

    International Nuclear Information System (INIS)

    English, M.R.

    1989-01-01

    Siting a low-level waste facility is only one part of the low-level waste management process. But it is a crucial part, a prism that focuses many of the other issues in low-level waste management. And, as the 1990 and 1992 milestones approach, siting has a urgency that makes the use of alternative dispute resolution (ADR) techniques especially appropriate, to avoid protracted and expensive litigation and to reach creative and durable solutions. Drawing upon literature in the ADR field, this paper discusses ADR techniques as they apply to low-level waste management and the groundwork that must be laid before they can be applied. It also discusses questions that can arise concerning the terms under which negotiations are carried out. The paper then give suggestions for achieving win/win negotiations. Potential objections to negotiated agreements and potential answers to those objections are reviewed, and some requisites for negotiation are given

  2. Delegated Democracy. The Siting of Swedish Nuclear Waste

    International Nuclear Information System (INIS)

    Johansson, Hanna Sofia

    2009-12-01

    This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

  3. On-site vs off-site management of environmental restoration waste: A cost effectiveness analysis

    International Nuclear Information System (INIS)

    Morse, M.A.; Aamodt, P.L.; Cox, W.B.

    1996-01-01

    The Sandia National Laboratories Environmental Restoration Project is expected to generate relatively large volumes of hazardous waste as a result of cleanup operations. These volumes will exceed the Laboratories existing waste management capacity. This paper presents four options for managing remediation wastes, including three alternatives for on-site waste management utilizing a corrective action management unit (CAMU). Costs are estimated for each of the four options based on current volumetric estimates of hazardous waste. Cost equations are derived for each of the options with the variables being waste volumes, the major unknowns in the analysis. These equations provide a means to update cost estimates as volume estimates change. This approach may be helpful to others facing similar waste management decisions

  4. Siting of a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Alvarado, R.A.

    1983-01-01

    The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

  5. Assessment of mixed hazardous and radioactive waste sites at Hanford

    International Nuclear Information System (INIS)

    McLaughlin, T.J.; Cramer, K.H.; Lamar, D.A.; Sherwood, D.R.; Stenner, R.D.; Schulze, W.B.

    1987-10-01

    The US Department of Energy and Pacific Northwest Laboratory recently completed a preliminary assessment of 685 inactive hazardous waste sites located on the Hanford Site. The preliminary assessment involved collecting historical data and individual site information, conducting site inspections, and establishing an environmental impact priority, using the Hazard Ranking System, for each of these 685 sites. This preliminary assessment was the first step in the remediation process required by the Comprehensive Environmental Response, Compensation and Liability Act. This paper presents the results of that preliminary assessment. 10 refs., 4 figs., 1 tab

  6. Remaining Sites Verification Package for the 128-B-3 Burn Pit Site, Waste Site Reclassification Form 2006-058

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-11-17

    The 128-B-3 waste site is a former burn and disposal site for the 100-B/C Area, located adjacent to the Columbia River. The 128-B-3 waste site has been remediated to meet the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results of sampling at upland areas of the site also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  7. Savannah River Site waste management. Final environmental impact statement - addendum

    International Nuclear Information System (INIS)

    1995-07-01

    The purpose of this environmental impact statement is to help DOE decide how to manage over the next 30 years liquid high-level radioactive, low-level radioactive, mixed, hazardous, and transuranic wastes generated during 40 years of past operations and on-going activities (including management of wastes received from offsite) at Savannah River Site (SRS) in southwestern South Carolina. The wastes are currently stored at SRS. DOE seeks to dispose of the wastes in a cost-effective manner that protects human health and the environment. In this document, DOE assesses the cumulative environmental impacts of storing, treating, and disposing of the wastes, examines the impacts of alternatives, and identifies measures available to reduce adverse impacts. Evaluations of impacts on water quality, air quality, ecological systems, land use, geologic resources, cultural resources, socio-economics, and the health and safety of onsite workers and the public are included in the assessment

  8. Savannah River Site Waste Management Final Environmental Impact Statement Addendum

    International Nuclear Information System (INIS)

    1995-07-01

    The purpose of this environmental impact statement is to help DOE decide how to manage over the next 30 years liquid high-level radioactive, low-level radioactive, mixed, hazardous, and transuranic wastes generated during 40 years of past operations and on-going activities (including management of wastes received from offsite) at Savannah River Site (SRS) in southwestern South Carolina. The wastes are currently stored at SRS. DOE seeks to dispose of the wastes in a cost-effective manner that protects human health and the environment. In this document, DOE assesses the cumulative environmental impacts of storing, treating, and disposing of the wastes, examines the impacts of alternatives, and identifies measures available to reduce adverse impacts. Evaluations of impacts on water quality, air quality, ecological systems, land use, geologic resources, cultural resources, socio-economic, and the health and safety of onsite workers and the public are included in the assessment

  9. Yucca Mountain Site Characterization Project Waste Package Plan

    International Nuclear Information System (INIS)

    Harrison-Giesler, D.J.; Jardine, L.J.

    1991-02-01

    The goal of the US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package program is to develop, confirm the effectiveness of, and document a design for a waste package and associated engineered barrier system (EBS) for spent nuclear fuel and solidified high-level nuclear waste (HLW) that meets the applicable regulatory requirements for a geologic repository. The Waste Package Plan describes the waste package program and establishes the technical approach against which overall progress can be measured. It provides guidance for execution and describes the essential elements of the program, including the objectives, technical plan, and management approach. The plan covers the time period up to the submission of a repository license application to the US Nuclear Regulatory Commission (NRC). 1 fig

  10. Waste Tank Corrosion Program at Savannah River Site

    International Nuclear Information System (INIS)

    Chandler, J.R.; Hsu, T.C.; Hobbs, D.T.; Iyer, N.C.; Marra, J.E.; Zapp, P.E.

    1993-01-01

    The Savannah River Site (SRS) has approximately 30 million gallons of high level radioactive waste stored in 51 underground tanks. SRS has maintained an active corrosion research and corrosion control and monitoring program throughout the operating history of SRS nuclear waste storage tanks. This program is largely responsible for the successful waste storage experience at SRS. The program has consisted of extensive monitoring of the tanks and surrounding environment for evidence of leaks, extensive research to understand the potential corrosion processes, and development and implementation of corrosion chemistry control. Current issues associated with waste tank corrosion are primarily focused on waste processing operations and are being addressed by a number of active programs and initiatives

  11. Contaminant fluxes through site containment barriers: Performance assessment and illustrative results

    International Nuclear Information System (INIS)

    Vita, C.L.

    1994-01-01

    Contaminant mass flux by advective and diffusive transport is predicted for five containment barriers that use one or more clay liners, flexible membrane liners (FMLs), or liquid collection and removal systems (LCRS)s. Barriers are engineered systems intended to contain and isolate site contaminants from the environment. Barriers include liners, caps, and cutoff walls. Barriers may be used in contaminated-site cleanups (including CERCLA and RCRA), RCRA landfills, or other RCRA TSDFs. Concepts are provided for barrier performance assessment, including analysis and optimization, for meeting performance requirements and controlling risk at minimum cost. Concepts and results can help in planning, designing, or evaluating and communicating, the use or effectiveness of proposed or existing barriers for site cleanups or waste containment. 15 refs., 6 figs., 5 tabs

  12. RCRA Personnel Training, Course 7488

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, Lewis Edward [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-30

    Federal and state regulations require hazardous and mixed waste facility workers at treatment and storage facilities (TSFs) and <90-day accumulation areas to be trained in hazardous and mixed waste management. This course will refamiliarize and update <90-day accumulation area workers, TSF workers, and supervisors of TSF workers regarding waste identification, pollution prevention, storage area requirements, emergency response procedures, and record-keeping requirements.

  13. Radioactive waste will be stored at desolate Cape site

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    High, intermediate and low-level radioactive waste will be stored at the Vaalputs nuclear waste dump site near Springbok. This area is sparsely populated, there are no mineral deposits of any value, the agricultural potential is minimal. It is a typical semi-desert area. Geologically it lends itself towards the ground-storage of used nuclear fuel, because of the remote possibility of earthquakes

  14. Management of radioactive wastes at power reactor sites in India

    International Nuclear Information System (INIS)

    Amalraj, R.V.; Balu, K.

    Indian nuclear power programme, at the present stage, is based on natural uranium fuelled heavy water moderated CANDU type reactors except for the first nuclear power station consisting of two units of enriched uranium fuelled, light water moderated, BWR type of reactors. Some of the salient aspects of radioactive waste management at power reactor sites in India are discussed. Brief reviews are presented on treatment of wastes, their disposal and environmental aspects. Indian experience in power reactor waste management is also summarised identifying some of the areas needing further work. (auth.)

  15. A Short History of Waste Management at the Hanford Site

    International Nuclear Information System (INIS)

    Gephart, Roy E.

    2010-01-01

    The world's first full-scale nuclear reactors and chemical reprocessing plants built at the Hanford Site in the desert of eastern Washington State produced two-thirds of the plutonium generated in the United States for nuclear weapons. Operating these facilities also created large volumes of radioactive and chemical waste, some of which was released into the environment exposing people who lived downwind and downstream. Hanford now contains the largest accumulation of nuclear waste in the Western Hemisphere. Hanford's last reactor shut down in 1987 followed by closure of the last reprocessing plant in 1990. Today, Hanford's only mission is cleanup. Most onsite radioactive waste and nuclear material lingers inside underground tanks or storage facilities. About half of the chemical waste remains in tanks while the rest persists in the soil, groundwater, and burial grounds. Six million dollars each day, or nearly two billion dollars each year, are spent on waste management and cleanup activities. There is significant uncertainty in how long cleanup will take, how much it will cost, and what risks will remain for future generations. This paper summarizes portions of the waste management history of the Hanford Site published in the book 'Hanford: A Conversation about Nuclear Waste and Cleanup.'

  16. Detecting hot spots at hazardous-waste sites

    International Nuclear Information System (INIS)

    Zirschky, J.; Gilbert, R.O.

    1984-01-01

    Evaluating the need for remedial cleanup at a waste site involves both finding the average contaminant concentration and identifying highly contaminated areas, or hot spots. A nomographic procedure to determine the sample configuration needed to locate a hot spot is presented. The technique can be used to develop a waste-site sampling plant - to determine either the grid spacing required to detect a hot spot at a given level of confidence, or the probability of finding a hot spot of a certain size, given a particular grid spacing. The method and computer program (ELIPGRID) were developed for locating geologic deposits, but the basic procedure can also be used to detect hot spots at chemical- or nuclear-waste disposal sites. Nomographs based on the original program are presented for three sampling-grid configurations - square, rectangular and triangular

  17. Siting simulation for low-level waste disposal facilities

    International Nuclear Information System (INIS)

    Roop, R.D.; Rope, R.C.

    1985-01-01

    The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

  18. Application of neural networks to waste site screening

    International Nuclear Information System (INIS)

    Dabiri, A.E.; Garrett, M.; Kraft, T.; Hilton, J.; VanHammersveld, M.

    1993-02-01

    Waste site screening requires knowledge of the actual concentrations of hazardous materials and rates of flow around and below the site with time. The present approach consists primarily of drilling boreholes near contaminated sites and chemically analyzing the extracted physical samples and processing the data. This is expensive and time consuming. The feasibility of using neural network techniques to reduce the cost of waste site screening was investigated. Two neural network techniques, gradient descent back propagation and fully recurrent back propagation were utilized. The networks were trained with data received from Westinghouse Hanford Corporation. The results indicate that the network trained with the fully recurrent technique shows satisfactory generalization capability. The predicted results are close to the results obtained from a mathematical flow prediction model. It is possible to develop a new tool to predict the waste plume, thus substantially reducing the number of the bore sites and samplings. There are a variety of applications for this technique in environmental site screening and remediation. One of the obvious applications would be for optimum well siting. A neural network trained from the existing sampling data could be utilized to decide where would be the best position for the next bore site. Other applications are discussed in the report

  19. Characterization of radionuclude behavior in low-level waste sites

    International Nuclear Information System (INIS)

    Toste, A.P.; Kirby, L.J.; Robertson, D.E.; Abel, K.H.; Perkins, R.W.

    1982-10-01

    Our laboratory is investigating the subsurface migration of radionuclides in groundwater at the Maxey Flats, Kentucky, shallow land-burial site and at a low-level aqueous waste disposal facility. At Maxey Flats, radionuclide and tracer data indicate groundwater communication between a waste trench and an adjacent experimental study area. Areal distributions of radionuclides in surface soil confirm that contamination at Maxey Flats has been largely contained on site. Of the radionuclides detected in the surface soil, only 3 H and 60 Co concentrations appear to be derived from waste. Plutonium exists in the anoxic subsurface waters at Maxey Flats as a reduced, anionic complex; some of the plutonium appears to be complexed with EDTA, whereas organic acids seem to be associated with 137 Cs and 90 Sr. At the aqueous waste disposal site, 3 H and mainly anionic species of certain radionuclides, including 60 Co, 106 Ru, 99 Tc, 131 I, and traces of 238 239 240 Pu, appear to migrate from a trench through soil adjacent to the trench. Radionuclides in the particulate and cationic forms appear to be efficiently retained by the soil. In general, observations indicate that the physicochemical form of the radionuclides mediates their subsurface migration in groundwater at both waste disposal sites

  20. 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

  1. 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

  2. Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    1987-10-01

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

  3. The Hanford Site Tank Waste Remediation System: An update

    International Nuclear Information System (INIS)

    Alumkal, W.T.; Babad, H.; Harmon, H.D.; Wodrich, D.D.

    1994-01-01

    The U.S. Department of Energy's Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of highly radioactive waste in the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m 3 (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have 137 Cs accumulated in 177 tanks. In addition, significant amounts of 90 Sr and were removed from the tank waste, converted to salts, doubly encapsulated in metal containers., and stored in water basins. A Tank Waste Remediation System Program was established by the U.S. Department of Energy in 1991 to safely manage and immobilize these wastes in anticipation of permanent disposal of the high-level waste fraction in a geologic repository. Since 1991, progress has been made resolving waste tank safety issues, upgrading Tank Farm facilities and operations, and developing a new strategy for retrieving, treating, and immobilizing the waste for disposal

  4. Protective barrier systems for final disposal of Hanford Waste Sites

    International Nuclear Information System (INIS)

    Phillips, S.J.; Hartley, J.N.

    1986-01-01

    A protecting barrier system is being developed for potential application in the final disposal of defense wastes at the Hanford Site. The functional requirements for the protective barrier are control of water infiltration, wind erosion, and plant and animal intrusion into the waste zone. The barrier must also be able to function without maintenance for the required time period (up to 10,000 yr). This paper summarizes the progress made and future plans in this effort to design and test protective barriers at the Hanford Site

  5. 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)

  6. Site characterization data for Solid Waste Storage Area 6

    International Nuclear Information System (INIS)

    Boegly, W.J. Jr.

    1984-12-01

    Currently, the only operating shallow land burial site for low-level radioactive waste at the Oak Ridge National Laboratory (ORNL) is Solid Waste Storage Area No. 6 (SWSA-6). In 1984, the US Department of Energy (DOE) issued Order 5820.2, Radioactive Waste Management, which establishes policies and guidelines by which DOE manages its radioactive waste, waste by-products, and radioactively contaminated surplus facilities. The ORNL Operations Division has given high priority to characterization of SWSA-6 because of the need for continued operation under DOE 5820.2. The purpose of this report is to compile existing information on the geologic and hydrologic conditions in SWSA-6 for use in further studies related to assessing compliance with 5820.2. Burial operations in SWSA-6 began in 1969 on a limited scale, and full operation was initiated in 1973. Since that time, ca. 29,100 m 3 of low-level waste containing ca. 251,000 Ci of activity has been buried in SWSA-6. No transuranic waste has been disposed of in SWSA-6; rather this waste is retrievably stored in SWSA-5. Estimates of the remaining usable space in SWSA-6 vary; however, in 1982 sufficient useful land was reported for about 10 more years of operation. Analysis of the information available on SWSA-6 indicates that more information is required to evaluate the surface water hydrology, the geology at depths below the burial trenches, and the nature and extent of soils within the site. Also, a monitoring network will be required to allow detection of potential contaminant movement in groundwater. Although these are the most obvious needs, a number of specific measurements must be made to evaluate the spatial heterogeneity of the site and to provide background information for geohydrological modeling. Some indication of the nature of these measurements is included

  7. Sociological perspective on the siting of hazardous waste facilities

    International Nuclear Information System (INIS)

    Mileti, D.S.; Williams, R.G.

    1985-01-01

    The siting of hazardous waste facilities has been, and will likely continue to be, both an important societal need and a publically controversial topic. Sites have been denounced, shamed, banned, and moved at the same time that the national need for their installation and use has grown. Despite available technologies and physical science capabilities, the effective siting of facilitites stands more as a major contemporary social issue than it is a technological problem. Traditional social impact assessment approaches to the siting process have largely failed to meaningfully contribute to successful project implementation; these efforts have largely ignored the public perception aspects of risk and hazard on the success or failure of facility siting. This paper proposes that the siting of hazardous waste facilities could well take advantage of two rich but somewhat disparate research histories in the social sciences. A convergent and integrated approach would result from the successful blending of social impact assessment, which seeks to define and mitigate problems, with an approach used in hazards policy studies, which has sought to understand and incorporate public risk perceptions into effective public decision-making. It is proposed in this paper that the integration of these two approaches is necessary for arriving at more readily acceptable solutions to siting hazardous waste facilities. This paper illustrates how this integration of approaches could be implemented

  8. 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

  9. Hazardous-waste analysis plan for LLNL operations

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, R.S.

    1982-02-12

    The Lawrence Livermore National Laboratory is involved in many facets of research ranging from nuclear weapons research to advanced Biomedical studies. Approximately 80% of all programs at LLNL generate hazardous waste in one form or another. Aside from producing waste from industrial type operations (oils, solvents, bottom sludges, etc.) many unique and toxic wastes are generated such as phosgene, dioxin (TCDD), radioactive wastes and high explosives. One key to any successful waste management program must address the following: proper identification of the waste, safe handling procedures and proper storage containers and areas. This section of the Waste Management Plan will address methodologies used for the Analysis of Hazardous Waste. In addition to the wastes defined in 40 CFR 261, LLNL and Site 300 also generate radioactive waste not specifically covered by RCRA. However, for completeness, the Waste Analysis Plan will address all hazardous waste.

  10. Hazardous-waste analysis plan for LLNL operations

    International Nuclear Information System (INIS)

    Roberts, R.S.

    1982-01-01

    The Lawrence Livermore National Laboratory is involved in many facets of research ranging from nuclear weapons research to advanced Biomedical studies. Approximately 80% of all programs at LLNL generate hazardous waste in one form or another. Aside from producing waste from industrial type operations (oils, solvents, bottom sludges, etc.) many unique and toxic wastes are generated such as phosgene, dioxin (TCDD), radioactive wastes and high explosives. One key to any successful waste management program must address the following: proper identification of the waste, safe handling procedures and proper storage containers and areas. This section of the Waste Management Plan will address methodologies used for the Analysis of Hazardous Waste. In addition to the wastes defined in 40 CFR 261, LLNL and Site 300 also generate radioactive waste not specifically covered by RCRA. However, for completeness, the Waste Analysis Plan will address all hazardous waste

  11. Calcination/dissolution testing for Hanford Site tank wastes

    International Nuclear Information System (INIS)

    Colby, S.A.; Delegard, C.H.; McLaughlin, D.F.; Danielson, M.J.

    1994-07-01

    Thermal treatment by calcination offers several benefits for the treatment of Hanford Site tank wastes, including the destruction of organics and ferrocyanides and an hydroxide fusion that permits the bulk of the mostly soluble nonradioactive constituents to be easily separated from the insoluble transuranic residue. Critical design parameters were tested, including: (1) calciner equipment design, (2) hydroxide fusion chemistry, and (3) equipment corrosion. A 2 gal/minute pilot plant processed a simulated Tank 101-SY waste and produced a free flowing 700 C molten calcine with an average calciner retention time of 20 minutes and >95% organic, nitrate, and nitrite destruction. Laboratory experiments using actual radioactive tank waste and the simulated waste pilot experiments indicate that 98 wt% of the calcine produced is soluble in water, leaving an insoluble transuranic fraction. All of the Hanford Site tank wastes can benefit from calcination/dissolution processing, contingent upon blending various tank waste types to ensure a target of 70 wt% sodium hydroxide/nitrate/nitrite fluxing agent. Finally, corrosion testing indicates that a jacketed nickel liner cooled to below 400 C would corrode <2 mil/year (0.05 mm/year) from molten calcine attack

  12. Interim reclamation report: Basalt Waste Isolation Project exploration shaft site

    International Nuclear Information System (INIS)

    Brandt, C.A.; Rickard, W.H. Jr.; Hefty, M.G.

    1990-02-01

    In 1968, a program was started to assess the feasibility of storing Hanford Site defense waste in deep caverns constructed in basalt. This program was expanded in 1976 to include investigations of the Hanford Site as a potential location for a mined commercial nuclear waste repository. Extensive studies of the geotechnical aspects of the site were undertaken, including preparations for drilling a large diameter Exploratory Shaft. This report describes the development of the reclamation program for the Exploratory Shaft Facility, its implementation, and preliminary estimates of its success. The goal of the reclamation program is to return sites disturbed by the repository program as nearly as practicable to their original conditions using native plant species. 43 refs., 19 figs., 9 tabs

  13. Closure Report for Corrective Action Unit 537: Waste Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure

  14. Ranking system for mixed radioactive and hazardous waste sites

    International Nuclear Information System (INIS)

    Hawley, K.A.; Napier, B.A.

    1985-01-01

    The Environmental Protection Agency's Hazard Ranking System (HRS) is a simplified management decision tool that provides a common basis for evaluating a multitude of hazardous waste sites. A deficiency in the HRS for application to Department of Energy mixed radioactive and hazardous waste sites is its inability to explicitly handle radioactive material. A modification to the basic HRS to add the capability to consider radioactivity is described. The HRS considers the exposure routes of direct contact, fire/explosion, atmospheric release, surface-water release, and ground-water release. Each exposure route is further divided into release, route, containment, waste, and target characteristics. To maintain the basic HRS structure, only the waste characteristics section of each exposure route was modified. A ranking system was developed, using radiation dose pathway analysis, to group radionuclides by dose factors. For mixed waste sites, the ranking factor derived for radionuclides is compared with the ranking factor obtained for hazardous chemicals and the most restrictive is used in the overall ranking. The modified HRS has the advantages of being compatible with the original HRS, has reasonable information requirements, and provides scientifically defensible conclusions. 17 references, 2 figures, 6 tables

  15. Annual Report RCRA Post-Closure Monitoring and Inspections for Corrective Action Unit 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the Period October 2001 - October 2002

    International Nuclear Information System (INIS)

    Richardson, G.

    2003-01-01

    This annual monitoring and inspection report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Injection Well during the October 2001 to October 2002 period. The U-3fi Injection Well is located in Area 3 of the Nevada Test Site (NTS), Nye County, Nevada. Inspections of the Area 3 U-3fi Injection Well are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste disposal unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 128-meter (m) (420-feet [ft]) ER3-3 monitoring well and detect changes that may be indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft)

  16. Technology needs and trends for hazardous waste site remediation

    International Nuclear Information System (INIS)

    Kovalick, W.W. Jr.

    1995-01-01

    Over the next few decades, federal, state, and local governments and private industry will commit billions of dollars annually to clean up sites contaminated with hazardous waste and petroleum products. While these needs represent an obligation for society, they also represent an important business opportunity for vendors of remediation services. This presentation assesses the remediation market by characterizing sites that comprise the demand for cleanup services, observing remedy selection trends in the Superfund program, and discussing gaps in the supply of technologies

  17. Geoelectrical Evaluation of Waste Dump Sites at Warri and its ...

    African Journals Online (AJOL)

    The existing waste dump sites in Delta State were investigated without soil disturbance by using the vertical electrical sounding (VES).The soil overlying the aquifer at Ovwian-Aladja dump site has resistively values, 11.84-85.50 Ohm-m, thicknesses,21.10-31.83m and at depths less than 1m, while at Warri it has resistively ...

  18. Groundwater quality assessment plan for single-shell tank waste management Area U at the Hanford Site

    International Nuclear Information System (INIS)

    FN Hodges; CJ Chou

    2000-01-01

    Waste Management Area U (WMA U) includes the U Tank Farm, is currently regulated under RCRA interim-status regulations, and is scheduled for closure probably post-2030. Groundwater monitoring has been under an evaluation program that compared general contaminant indicator parameters from downgradient wells to background values established from upgradient wells. One of the indicator parameters, specific conductance, exceeded its background value in one downgradient well triggering a change from detection monitoring to a groundwater quality assessment program. The objective of the first phase of this assessment program is to determine whether the increased concentrations of nitrate and chromium in groundwater are from WMA U or from an upgradient source. Based on the results of the first determination, if WMA U is not the source of contamination, then the site will revert to detection monitoring. If WMA U is the source, then a second part of the groundwater quality assessment plan will be prepared to define the rate and extent of migration of contaminants in the groundwater and their concentrations

  19. Application of neural networks to waste site screening

    Energy Technology Data Exchange (ETDEWEB)

    Dabiri, A.E.; Kraft, T.; Hilton, J.M. [Science Applications International Corp., San Diego, CA (United States)

    1993-03-01

    Waste site screening requires knowledge of the actual concentrations of hazardous materials and rates of flow around and below the site with time. The present approach to site screening consists primarily of drilling, boreholes near contaminated site and chemically analyzing the extracted physical samples and processing the data. In addition, hydraulic and geochemical soil properties are obtained so that numerical simulation models can be used to interpret and extrapolate the field data. The objective of this work is to investigate the feasibility of using neural network techniques to reduce the cost of waste site screening. A successful technique may lead to an ability to reduce the number of boreholes and the number of samples analyzed from each borehole to properly screen the waste site. The analytic tool development described here is inexpensive because it makes use of neural network techniques that can interpolate rapidly and which can learn how to analyze data rather than having to be explicitly programmed. In the following sections, data collection and data analyses will be described, followed by a section on different neural network techniques used. The results will be presented and compared with mathematical model. Finally, the last section will summarize the research work performed and make several recommendations for future work.

  20. 76 FR 6594 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S...

  1. 77 FR 60963 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Johnson, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division...

  2. Environmental waste site characterization utilizing aerial photographs and satellite imagery: Three sites in New Mexico, USA

    International Nuclear Information System (INIS)

    Van Eeckhout, E.; Pope, P.; Becker, N.; Wells, B.; Lewis, A.; David, N.

    1996-01-01

    The proper handling and characterization of past hazardous waste sites is becoming more and more important as world population extends into areas previously deemed undesirable. Historical photographs, past records, current aerial satellite imagery can play an important role in characterizing these sites. These data provide clear insight into defining problem areas which can be surface samples for further detail. Three such areas are discussed in this paper: (1) nuclear wastes buried in trenches at Los Alamos National Laboratory, (2) surface dumping at one site at Los Alamos National Laboratory, and (3) the historical development of a municipal landfill near Las Cruces, New Mexico

  3. Characteristics and suitability of waste dump sites in Owerri, Nigeria ...

    African Journals Online (AJOL)

    A five point criteria screening of the three major waste dumpsites in Owerri Municipality was identified, and a ranking procedure adopted to determine the suitability or otherwise of the dumpsites. The sites were screened and ranked hydro-geologically and geo-technically in order of suitable, moderately suitable, and not ...

  4. Site suitability criteria for solidified high level waste repositories

    International Nuclear Information System (INIS)

    Heckman, R.A.; Holdsworth, T.; Towse, D.F.

    1979-01-01

    Activities devoted to development of regulations, criteria, and standards for storage of solidified high-level radioactive wastes are reported. The work is summarized in sections on site suitability regulations, risk calculations, geological models, aquifer models, human usage model, climatology model, and repository characteristics. Proposed additional analytical work is also summarized

  5. Solid waste dumping site suitability analysis using geographic ...

    African Journals Online (AJOL)

    Solid waste dumping site suitability analysis using geographic information system (GIS) and remote sensing for Bahir Dar Town, North Western Ethiopia. ... The PDF file you selected should load here if your Web browser has a PDF reader plug-in installed (for example, a recent version of Adobe Acrobat Reader).

  6. High-level radioactive waste repositories site selection plan

    International Nuclear Information System (INIS)

    Castanon, A.; Recreo, F.

    1985-01-01

    A general vision of the high level nuclear waste (HLNW) and/or nuclear spent fuel facilities site selection processes is given, according to the main international nuclear safety regulatory organisms quidelines and the experience from those countries which have reached a larger development of their national nuclear programs. (author)

  7. Final storage site for radioactive waste. Gorleben mine

    International Nuclear Information System (INIS)

    1995-02-01

    Out of more than 20 salt stocks, the Gorleben salt stock was chosen. In addition to the preliminary information available on its size and depth, detailed exploratory investigations were carried out in order to test its suitability as a site for ultimate storage of all types of radioactive waste. (orig.) [de

  8. 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

  9. Alternate cap designs under RCRA regulations

    International Nuclear Information System (INIS)

    Manrod, W.E. III; Yager, R.E.; Craig, P.M.

    1988-01-01

    Low-level radioactive waste and mixed wastes have been disposed of in several sites in the vicinity of the Oak Ridge Y-12 Plant in Tennessee. Most of these materials have been placed in shallow land burial pits (SLB). Closure plans have been developed and approved by appropriate regulatory agencies for several of these sites. A variety of cap (final cover) designs for closure of these sites were investigated to determine their ability to inhibit infiltration of precipitation to the waste. The most effective designs are those that use synthetic materials as drainage layers and/or impermeable liners. The more complex, multi-layer systems perform no better than simpler covers and would complicate construction and increase costs. Despite the successful analytical results described in this paper, additional considerations must be factored into use of geosynthetic as well as natural materials

  10. Human Health and Ecological Risk Assessment for the Operation of the Explosives Waste Treatment Facility at Site 300 of the Lawrence Livermore National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, G; Daniels, J; Wegrecki, A

    2007-10-01

    This document contains the human health and ecological risk assessment for the Resource Recovery and Conservation Act (RCRA) permit renewal for the Explosives Waste Treatment Facility (EWTF). Volume 1 is the text of the risk assessment, and Volume 2 (provided on a compact disc) is the supporting modeling data. The EWTF is operated by the Lawrence Livermore National Laboratory (LLNL) at Site 300, which is located in the foothills between the cities of Livermore and Tracy, approximately 17 miles east of Livermore and 8 miles southwest of Tracy. Figure 1 is a map of the San Francisco Bay Area, showing the location of Site 300 and other points of reference. One of the principal activities of Site 300 is to test what are known as 'high explosives' for nuclear weapons. These are the highly energetic materials that provide the force to drive fissionable material to criticality. LLNL scientists develop and test the explosives and the integrated non-nuclear components in support of the United States nuclear stockpile stewardship program as well as in support of conventional weapons and the aircraft, mining, oil exploration, and construction industries. Many Site 300 facilities are used in support of high explosives research. Some facilities are used in the chemical formulation of explosives; others are locations where explosive charges are mechanically pressed; others are locations where the materials are inspected radiographically for such defects as cracks and voids. Finally, some facilities are locations where the machined charges are assembled before they are sent to the onsite test firing facilities, and additional facilities are locations where materials are stored. Wastes generated from high-explosives research are treated by open burning (OB) and open detonation (OD). OB and OD treatments are necessary because they are the safest methods for treating explosives wastes generated at these facilities, and they eliminate the requirement for further handling

  11. Closure Strategy Nevada Test Site Area 5 Radioactive Waste Management Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2007-03-01

    This paper presents an overview of the strategy for closure of part of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada (Figure 1). The Area 5 RWMS is in the northern part of Frenchman Flat, approximately 14 miles north of Mercury. The Area 5 RWMS encompasses 732 acres subdivided into quadrants, and is bounded by a 1,000-foot (ft)-wide buffer zone. The northwest and southwest quadrants have not been developed. The northeast and southeast quadrants have been used for disposal of unclassified low-level radioactive waste (LLW) and indefinite storage of classified materials. This paper focuses on closure of the 38 waste disposal and classified material storage units within the southeast quadrant of the Area 5 RWMS, called the ''92-Acre Area''. The U.S Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is currently planning to close the 92-Acre Area by 2011. Closure planning for this site must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. For ease of discussion, the 92-Acre Area has been subdivided into six closure units defined by waste type, location, and similarity in regulatory requirements. Each of the closure units contains one or more waste disposal units; waste disposal units are also called waste disposal cells. The paper provides a brief background of the Area 5 RWMS, identifies key closure issues for the 92-Acre Area, recommends actions to address the issues, and provides the National Security Technologies, LLC (NSTec), schedule for closure.

  12. Method of draining water through a solid waste site without leaching

    Science.gov (United States)

    Treat, Russell L.; Gee, Glendon W.; Whyatt, Greg A.

    1993-01-01

    The present invention is a method of preventing water from leaching solid waste sites by preventing atmospheric precipitation from contacting waste as the water flows through a solid waste site. The method comprises placing at least one drain hole through the solid waste site. The drain hole is seated to prevent waste material from entering the drain hole, and the solid waste site cover material is layered and graded to direct water to flow toward the drain hole and to soil beneath the waste site.

  13. Nevada test site defense waste acceptance criteria, certification, and transfer requirements

    International Nuclear Information System (INIS)

    1988-10-01

    The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

  14. Guidelines for hazardous-waste treatment sites. Hearing before the Subcommittee on Commerce, Transportation, and Tourism of the Committee on Energy and Commerce, House of Representatives, Ninety-Ninth Congress, Second Session, August 5, 1986

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    Representatives of a variety of environmental agencies and citizen organizations as well as officials from all levels of government testified on proposed amendments to the Resource Conservation and Recovery Act (RCRA) that call for the Environmental Protection Agency (EPA) to develop criteria guidelines for siting hazardous waste facilities. Uncertainty issues were raised because the guidelines would apply to existing as well as new facilities. The 16 witnesses examined whether the guidelines would be adequate to protect public health. The testimony of critics focused on specific situations involving PCB plants and other hazards in which the site selection standards proved inadequate. EPA representatives described siting relationships which EPA considers to be important. Additional material submitted for the record follows the testimony.

  15. Environmental Planning Strategies for Optimum Solid Waste Landfill Siting

    International Nuclear Information System (INIS)

    Sumiani, Y.; Onn, C.C.; Mohd, M.A.D.; Wan, W.Z.J.

    2009-01-01

    The use of environmental planning tools for optimum solid waste landfill siting taking into account all environmental implications was carried out by applying Life Cycle Analysis (LCA) to enhance the research information obtained from initial analysis using Geographical Information Systems (GIS). The objective of this study is to identify the most eco-friendly landfill site by conducting a LCA analysis upon 5 potential GIS generated sites which incorporated eleven important criteria related to the social, environmental, and economical factors. The LCA analysis utilized the daily distance covered by collection trucks among the 5 selected landfill sites to generate inventory data on total energy usage for each landfill sites. The planning and selection of the potential sites were facilitated after conducting environmental impact analysis upon the inventory data which showed the least environmental impact. (author)

  16. Incentives and the siting of radioactive waste facilities

    Energy Technology Data Exchange (ETDEWEB)

    Carnes, S.A.; Copenhaver, E.D.; Reed, J.H.; Soderstrom, E.J.; Sorensen, J.H.; Peelle, E.; Bjornstad, D.J.

    1982-08-01

    The importance of social and institutional issues in the siting of nuclear waste facilities has been recognized in recent years. Limited evidence from a survey of rural Wisconsin residents in 1980 indicates that incentives may help achieve the twin goals of increasing local support and decreasing local opposition to hosting nuclear waste facilities. Incentives are classified according to functional categories (i.e., mitigation, compensation, and reward) and the conditions which may be prerequisites to the use of incentives are outlined (i.e., guarantee of public health and safety, some measure of local control, and a legitimation of negotiations during siting). Criteria for evaluating the utility of incentives in nuclear waste repository siting are developed. Incentive packages may be more useful than single incentives, and nonmonetary incentives, such as independent monitoring and access to credible information, may be as important in eliciting support as monetary incentives. Without careful attention to prerequisites in the siting process it is not likely that incentives will facilitate the siting process.

  17. Incentives and the siting of radioactive waste facilities

    International Nuclear Information System (INIS)

    Carnes, S.A.; Copenhaver, E.D.; Reed, J.H.; Soderstrom, E.J.; Sorensen, J.H.; Peelle, E.; Bjornstad, D.J.

    1982-08-01

    The importance of social and institutional issues in the siting of nuclear waste facilities has been recognized in recent years. Limited evidence from a survey of rural Wisconsin residents in 1980 indicates that incentives may help achieve the twin goals of increasing local support and decreasing local opposition to hosting nuclear waste facilities. Incentives are classified according to functional categories (i.e., mitigation, compensation, and reward) and the conditions which may be prerequisites to the use of incentives are outlined (i.e., guarantee of public health and safety, some measure of local control, and a legitimation of negotiations during siting). Criteria for evaluating the utility of incentives in nuclear waste repository siting are developed. Incentive packages may be more useful than single incentives, and nonmonetary incentives, such as independent monitoring and access to credible information, may be as important in eliciting support as monetary incentives. Without careful attention to prerequisites in the siting process it is not likely that incentives will facilitate the siting process

  18. Remaining Sites Verification Package for the 128-B-2, 100-B Burn Pit No.2 Waste Site. Attchment to Waste Site Reclassification Form 2005-038

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2005-01-01

    The 128-B-2 waste site was a burn pit historically used for the disposal of combustible and noncombustible wastes, including paint and solvents, office waste, concrete debris, and metallic debris. This site has been remediated by removing approximately 5,627 bank cubic meters of debris, ash, and contaminated soil to the Environmental Restoration Disposal Facility. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  19. Geotechnical site assessment for underground radioactive waste disposal in rock

    International Nuclear Information System (INIS)

    Hudson, J.A.

    1986-05-01

    This report contains a state-of-the-art review of the geotechnical assessment of Land 3 and Land 4 repository sites (at 100 - 300 m depth in rock) for intermediate level radioactive waste disposal. The principles established are also valid for the disposal of low and high level waste in rock. The text summarizes the results of 21 DoE research contract reports, firstly 'in series' by providing a technical review of each report and then 'in parallel' by considering the current state of knowledge in the context of the subjects in an interaction matrix framework. 1214 references are cited. It is concluded that four further research projects are required for site assessment procedures to be developed or confirmed. These are coupled modelling, mechanical properties, water flow and establishment of 2 phase site assessment procedures. (author)

  20. Financing a new low-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Dressen, A.L.; Serie, P.J.; McGarvey, R.S.; Lemmon, R.A.

    1982-01-01

    No new commercial low-level radioactive waste disposal site has been licensed in the past decade. During the time, inflation has wreaked havoc on the costs for the labor, equipment, and buildings that will be necessary to develop and operate new sites. The regulatory environment has become much more complex with enactment of the National Environmental Policy Act (NEPA) and the recent issuance by the Nuclear Regulatory Commission (NRC) of a draft set of comprehensive regulations for land disposal of low-level waste (10 CFR Part 61). Finally, the licensing process itself has become much lengthier as both the site developers and regulators respond to the public's desire to be more involved in decisions that may affect their lives

  1. High-level wastes: DOE names three sites for characterization

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    DOE announced in May 1986 that there will be there site characterization studies made to determine suitability for a high-level radioactive waste repository. The studies will include several test drillings to the proposed disposal depths. Yucca Mountain, Nevada; Deaf Smith Country, Texas, and Hanford, Washington were identified as the study sites, and further studies for a second repository site in the East were postponed. The affected states all filed suits in federal circuit courts because they were given no advance warning of the announcement of their selection or the decision to suspend work on a second repository. Criticisms of the selection process include the narrowing or DOE options

  2. Conflict, location, and politics: Siting a nuclear waste repository

    International Nuclear Information System (INIS)

    Jacob, G.R.

    1988-01-01

    Nuclear power and the management of high-level radioactive waste is examined with the goal of explaining the forces driving the formulation of the 1982 Nuclear Waste Policy Act and a subsequent decision to site a nuclear waste repository at Yucca Mountain, Nevada. The study draws upon geographic, political, economic, and organizational factors to examine the commitment to dispose of spent fuel in a geologic repository located in Nevada or in Utah, Texas, Mississippi, Louisiana, or at Hanford Washington. Special attention is given to the impact of location, science and technology on the definition of the nuclear waste problem and political agendas, public participation, and the power of the nuclear establishment. The study finds that the choice of a Yucca Mountain Nevada as the preferred site for a repository was based more on technological precedent and political-economic expediency than on the demonstrated superiority of that site's geology. Conflict over a repository location is interpreted as a symptom of more fundamental conflicts concerning: the credibility of nuclear science, the legitimacy of federal authority and administration, and the priorities of environmental protection and a nuclear economy

  3. Projecting future solid waste management requirements on the Hanford Site

    International Nuclear Information System (INIS)

    Shaver, S.R.; Stiles, D.L.; Holter, G.M.; Anderson, B.C.

    1990-09-01

    The problem of treating and disposing of hazardous transuranic (TRU), low-level radioactive, and mixed waste has become a major concern of the public and the government. At the US Department of Energy's Hanford Site in Washington state, the problem is compounded by the need to characterize, retrieve, and treat the solid waste that was generated and stored for retrieval during the past 20 years. This paper discusses the development and application of a Solid Waste Projection Model that uses forecast volumes and characteristics of existing and future solid waste to address the treatment, storage, and disposal requirements at Hanford. The model uses a data-driven, object-oriented approach to assess the storage and treatment throughout requirements for each operation for each of the distinct waste classes and the accompanying cost of the storage and treatment operations. By defining the elements of each alternative for the total waste management system, the same database can be used for numerous analyses performed at different levels of detail. This approach also helps a variety of users with widely varying information requirements to use the model and helps achieve the high degree of flexibility needed to cope with changing regulations and evolving treatment and disposal technologies. 2 figs

  4. Techniques for site investigations for underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    1985-01-01

    The report provides a more detailed description of the capabilities and applications of the various earth science investigation techniques outlined in the IAEA Technical Reports Series Nos. 177, 215 and 216. These methods are generally appropriate during at least one of the stages of the assessment or selection of a site for any type of waste disposal facility, in shallow ground or in deep geological formations. This report is addressed to technical authorities responsible for or involved in planning, approving, executing and reviewing national waste disposal programmes. It may also help administrative authorities in this field to select appropriate techniques for obtaining the majority of the required information at minimum cost

  5. Negotiating the voluntary siting of nuclear waste facilities

    International Nuclear Information System (INIS)

    Mussler, R.M.

    1992-01-01

    This paper discusses the Office of the Nuclear Waste Negotiator which was created by Congress with the purpose of seeking a voluntary host State or Indian tribe for a high level nuclear waste repository or monitored retrievable storage facility. Given the history of the Federal government's efforts at siting such facilities, this would appear to be an impossible mission. Since commencing operations in August 1990, the Office has accomplished perhaps more than had been expected. Some of the approaches it has taken to implementing this mission may be applicable to other endeavors

  6. Haiti: Feasibility of Waste-to-Energy Options at the Trutier Waste Site

    Energy Technology Data Exchange (ETDEWEB)

    Conrad, M. D.; Hunsberger, R.; Ness, J. E.; Harris, T.; Raibley, T.; Ursillo, P.

    2014-08-01

    This report provides further analysis of the feasibility of a waste-to-energy (WTE) facility in the area near Port-au-Prince, Haiti. NREL's previous analysis and reports identified anaerobic digestion (AD) as the optimal WTE technology at the facility. Building on the prior analyses, this report evaluates the conceptual financial and technical viability of implementing a combined waste management and electrical power production strategy by constructing a WTE facility at the existing Trutier waste site north of Port-au-Prince.

  7. Site specific plan. [Environmental Restoration and Waste Management, Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Hutchison, J.; Jernigan, G.

    1989-12-01

    The Environmental Restoration and Waste Management Five-Year Plan (FYP) covers the period for FY 1989 through FY 1995. The plan establishes a Department of Energy -- Headquarters (DOE-HQ) agenda for cleanup and compliance against which overall progress can be measured. The FYP covers three areas: Corrective Activities, Environmental Restoration, and Waste Management Operations. Corrective Activities are those activities necessary to bring active or standby facilities into compliance with local, state, and federal environmental regulations. Environmental restoration activities include the assessment and cleanup of surplus facilities and inactive waste sites. Waste management operations includes the treatment, storage, and disposal of wastes which are generated as a result of ongoing operations. This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show how environmental restoration and waste management activities that were identified during the preparation of the FYP will be implemented, tracked, and reported. The SSP describes DOE Savannah River (DOE-SR) and operating contractor, Westinghouse Savannah River Company (WSRC), organizations that are responsible, for undertaking the activities identified in this plan. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. 8 refs., 46 figs., 23 tabs.

  8. 1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta`s K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports.

  9. 1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

    International Nuclear Information System (INIS)

    1994-02-01

    This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta's K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports

  10. Final Hanford Site Transuranic (TRU) Waste Characterization Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP

  11. 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

  12. Designing chemical soil characterization programs for mixed waste sites

    International Nuclear Information System (INIS)

    Meyers, K.A. Jr.

    1989-01-01

    The Weldon Spring Site Remedial Action Project is a remedial action effort funded by the U.S. Department of Energy. The Weldon Spring Site, a former uranium processing facility, is located in east-central Missouri on a portion of a former ordnance works facility which produced trinitrotoluene during World War II. As a result of both uranium and ordnance production, the soils have become both radiologically and chemically contaminated. As a part of site characterization efforts in support of the environmental documentation process, a chemical soil characterization program was developed. This program consisted of biased and unbiased sampling program which maximized areal coverage, provided a statistically sound data base and maintained cost effectiveness. This paper discusses how the general rationale and processes used at the Weldon Spring Site can be applied to other mixed and hazardous waste sites

  13. Soil characterization methods for unsaturated low-level waste sites

    International Nuclear Information System (INIS)

    Wierenga, P.J.; Young, M.H.; Hills, R.G.

    1993-01-01

    To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies

  14. Characterization of the atmospheric pathway at hazardous waste sites

    International Nuclear Information System (INIS)

    Droppo, J.G. Jr.; Buck, J.W.

    1988-10-01

    Evaluation of potential health effects for populations surrounding hazardous waste sites requires consideration of all potential contaminant transport pathways through groundwater, surface water, and the atmosphere. A comprehensive pathway model that includes emission, dispersion, and deposition computations has been developed as a component of the Remedial Action Priority System (RAPS). RAPS is designed to assess the relative potential risks associated with hazardous and radioactive mixed-waste disposal sites. The atmospheric component includes optional volatilization and suspension emission routines. Atmospheric transport, dispersion, and deposition are computed using relatively standard modeling techniques expanded to incorporate topographical influences. This sector-averaged Gaussian model accounts for local channeling, terrain heights, and terrain roughness effects. Long-term total deposition is computed for the terrain surrounding the hazardous waste site. An example is given of applications at a US Department of Energy site, where atmospheric emissions are potentially important. The multiple applications of RAPS have provided information on the relative importance of different constitutent transport pathways from a potential population risk basis. Our results show that the atmospheric pathway is often equally as important as other pathways such as groundwater and direct soil ingestion. 6 refs., 3 figs., 4 tabs

  15. Expeditious Methods for Site Characterization and Risk Assessment at Department of Defense Hazardous Waste Sites in the Republic of Korea

    National Research Council Canada - National Science Library

    Hartman, Dean

    1999-01-01

    ...) with preferred innovative site characterization technologies and risk assessment methods to meet their needs in obtaining hazardous waste site data and then prioritizing those sites for remediation based upon risk...

  16. Alternatives to land disposal of solid radioactive mixed wastes on the Hanford Site

    International Nuclear Information System (INIS)

    Jacobsen, P.H.

    1992-03-01

    This report is a detailed description of the generation and management of land disposal restricted mixed waste generated, treated, and stored at the Hanford Site. This report discusses the land disposal restricted waste (mixed waste) managed at the Hanford Site by point of generation and current storage locations. The waste is separated into groups on the future treatment of the waste before disposal. This grouping resulted in the definition of 16 groups or streams of land disposal restricted waste

  17. Chemodynamics of EDTA in a simulated mixed waste: the Hanford Site's complex concentrate waste

    International Nuclear Information System (INIS)

    Toste, A.P.; Ohnuki, Toshihiko

    1999-01-01

    Enormous stockpiles of mixed wastes at the USDOE's Hanford Site, the original US plutonium production facility, await permanent disposal. One mixed waste derived from reprocessing spent fuel was found to contain numerous nuclear related organics including chelating agents like EDTA and complexing agents, which have been used as decontamination agents, etc. Their presence in actual mixed wastes indicates that the organic content of nuclear wastes is dynamic and complicate waste management efforts. The subjects of this report is the chemo-degradation of EDTA degradation in a simulant Hanford's complex concentrate waste. The simulant was prepared by adding EDTA to an inorganic matrix, which was formulated based on past analyses of the actual waste. Aliquots of the EDTA simulant were withdrawn at different time points, derivatized via methylation and analyzed by gas chromatography and Gc/MS to monitor the disappearance of EDTA and the appearance of its' degradation products. This report also compares the results of EDTA's chemo-degradation to the g-radiolysis of EDTA in the simulant, the subject of a recently published article. Finally based on the results of these two studies, an assesment of the potential impact of EDTA degradation on the management of mixed wastes is offered. (J.P.N.)

  18. Nuclear waste and social peace - Strategies of site selection for radioactive waste disposal. Proceeding

    International Nuclear Information System (INIS)

    Dally, A.

    2003-01-01

    In February 1999, BMU appointed a working party to establish site selection procedures for repositories (AkEnd) which was to develop a transparent procedure of finding and selecting sites for the final storage of all kinds of radioactive waste in Germany. The procedure finally proposed by AkEnd implies considerable uncertainty, inter alia, about its legal implementability, the time required, and funding. The discussion papers of the meeting ''atomic waste and social peace'' show a tightrope walk between society, clerical aspects and scientists taking into account also a right of say for critical citizens. (GL)

  19. 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

  20. Nevada Test Site waste acceptance criteria [Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-08-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.