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

International Nuclear Information System (INIS)

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

1993-01-01

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

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

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

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

Science.gov (United States)

2010-01-01

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

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

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

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.

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

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.

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

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

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.

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.

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

Near-surface land disposal

International Nuclear Information System (INIS)

Kittel, J.H.

1989-01-01

The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

Land disposal alternatives for low-level waste

International Nuclear Information System (INIS)

Alexander, P.; Lindeman, R.; Saulnier, G.; Adam, J.; Sutherland, A.; Gruhlke, J.; Hung, C.

1982-01-01

The objective of this project is to develop data regarding the effectiveness and costs of the following options for disposing of specific low-level nuclear waste streams; sanitary landfill; improved shallow land burial; intermediate depth disposal; deep well injection; conventional shallow land burial; engineered surface storage; deep geological disposal; and hydrofracturing. This will be accomplished through the following steps: (1) characterize the properties of the commercial low-level wastes requiring disposal; (2) evaluate the various options for disposing of this waste, characterize selected representative waste disposal sites and design storage facilities suitable for use at those sites; (3) calculate the effects of various waste disposal options on population health risks; (4) estimate the costs of various waste disposal options for specific sites; and (5) perform trade-off analyses of the benefits of various waste disposal options against the costs of implementing these options. These steps are described. 2 figures, 2 tables

Alternatives for future land disposal of radioactive waste

International Nuclear Information System (INIS)

Mallory, C.W.

1982-01-01

Shallow land burial incorporating improvements to facilitate stabilization and decommissioning will continue to be the primary method of disposing of low level waste in areas where conditions are suitable for this type of disposal. The existing disposal sites should be closely monitored to assure that continued acceptance of this method of disposal. Plans for the decommissioning of the existing sites should be closely reviewed to assure that the planning is adequate and that adequate resources will be available to implement the decommissioning plan. For these areas where geological conditions are not suitable for shallow land burial and in situations where a higher degree of containment is desired, alternative disposal methods should be considered. Technology exists or is readily attainable to provide engineered disposal facilities which provide a higher degree of containment and can be readily decommissioned. The cost of disposal using these methods can be competitive with shallow land burial when the cost of environmental and hydrogeologic investigations and decommissioning are included. Disposal of radioactive waste having low activity in secure sanitary landfills could significantly reduce the transportation and disposal requirements for low level waste

Grout Treatment Facility Land Disposal Restriction Management Plan

International Nuclear Information System (INIS)

Hendrickson, D.W.

1991-01-01

This document establishes management plans directed to result in the land disposal of grouted wastes at the Hanford Grout Facilities in compliance with Federal, State of Washington, and Department of Energy land disposal restrictions. 9 refs., 1 fig

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

International Nuclear Information System (INIS)

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

1987-01-01

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

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

Shallow land disposal of radioactive waste

International Nuclear Information System (INIS)

1987-01-01

The application of basic radiation protection concepts and objectives to the disposal of radioactive wastes requires the development of specific reference levels or criteria for the radiological acceptance of each type of waste in each disposal option. This report suggests a methodology for the establishment of acceptance criteria for the disposal of low-level radioactive waste containing long-lived radionuclides in shallow land burial facilities

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

International Nuclear Information System (INIS)

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

1992-01-01

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

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

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

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

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

Storing, Transporting and Disposing of Mercury in Your Home

Science.gov (United States)

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

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

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

Energy Technology Data Exchange (ETDEWEB)

Corbus, D

1992-09-01

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

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

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

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.

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

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.

The land impact associated with the disposal of radioactive wastes

International Nuclear Information System (INIS)

Redmond, I.G.

1983-01-01

At present, the only land being utilized for the storage of radioactive wastes in Canada is at the sites of nuclear power generating stations, for high- and low-level wastes, and the land adjacent to uranium mines and mills in the case of tailings and the land in the vicinity of the uranium refinery in Port Hope. Existing storage sites for high- and low-level wastes do not occupy large amounts of land, since the amount of materials is relatively small. Uranium mine tailings, however, need hundreds of hectares of land. In addition to land directly utilized for the storage of the wastes, there may be a need for future buffer zones to separate them from adjoining land uses once a method of permanent disposal is decided. Any land utilized for the disposal of the wastes is likely to be unsuitable for other uses for anywhere from a few years to several thousand years, depending on the waste type occupying the land. Clearly, use of land for the storage and disposal of radioactive wastes may influence it beyond site boundaries and restrict its usage for other purposes for some considerable time to come

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

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

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.

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.

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)

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

Methodology of safety evaluation about land disposal of low level radioactive wastes

International Nuclear Information System (INIS)

Suzuki, Atsuyuki

1986-01-01

Accompanying the progress of the construction project of low level radioactive waste storage facilities in Aomori Prefecture, the full scale land disposal of low level radioactive wastes shows its symptom also in Japan. In this report, the scientific methodology to explain the safety about the land disposal of low level radioactive wastes is discussed. The land disposal of general wastes by shallow burying has already had sufficient results. In the case of low level radioactive wastes, also the land disposal by shallow burying is considered. Low level radioactive wastes can be regarded as one form of industrial wastes, as there are many common parts in the scientific and theoretical base of the safety. Attention is paid most to the contamination of ground water. Low level radioactive wastes are solid wastes, accordingly the degree of contamination should be less. The space in which ground water existes, the phenomena of ground water movement, the phenomena of ground water dispersion and Fick's law, the adsorption effect of strata, and the evaluation of source term are explained. These are the method to analyze the degree of contamination from safety evaluation viewpoint. (Kako, I.)

Proceedings. NETEC workshop on shallow land disposal technology, 1997. 10. 20 - 10. 21, Taejon, Korea

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

This proceedings cover the design and operational experience of shallow land disposal facility, and safety assessment and licensing issues of shallow land disposal facility. Ten articles are submitted.

Proceedings. NETEC workshop on shallow land disposal technology, 1997. 10. 20 - 10. 21, Taejon, Korea

International Nuclear Information System (INIS)

1997-01-01

This proceedings cover the design and operational experience of shallow land disposal facility, and safety assessment and licensing issues of shallow land disposal facility. Ten articles are submitted

Radiological assessments of land disposal options: recent model developments

International Nuclear Information System (INIS)

Fearn, H.S.; Pinner, A.V.; Hemming, C.R.

1984-10-01

This report describes progress in the development of methodologies and models for assessing the radiological impact of the disposal of low and intermediate level wastes by (i) shallow land burial in simple trenches (land 1), (ii) shallow land burial in engineered facilities (land 2), and (iii) emplacement in mined repositories or existing cavities (land 3/4). In particular the report describes wasteform leaching models, for unconditioned and cemented waste, the role of engineered barriers of a shallow land burial facility in reducing the magnitude of doses arising from groundwater contact and a detailed consideration of the interactions between radioactive carbon and various media. (author)

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.

10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

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

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

Data.gov (United States)

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

Ancient tombs in China and shallow land disposal of low-intermediate level radioactive wastes

International Nuclear Information System (INIS)

Huang, Y.; Gu, C.

1987-01-01

The paper summerises the experiences of ancient tombs in China on tomb siting, configuration of tombs, backfilling materials, civil engineering techniques, sealing (or airlight) techniques, drainage system, antiseptic techniques and so on based upon site investigation. Comparison between ancient tombs in China and shallow land disposal of radioactive wastes has been made. The authors point out that the brilliant achievements of ancient tombs in China in keeping ancient corpses and funeral objects is a historical evidence for safety of shallow land disposal of radioactive wastes, and that the main experiences of ancient tombs can be used for reference to shallow land disposal of radioactive wastes

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.

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)

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

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)

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

International Nuclear Information System (INIS)

1992-08-01

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

Disposal of Draeger Tubes at Savannah River Site

International Nuclear Information System (INIS)

Malik, N.P.

2000-01-01

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

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

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

International Nuclear Information System (INIS)

1991-06-01

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

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

Impacts of hazardous waste regulation on low-level waste management

International Nuclear Information System (INIS)

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

1986-01-01

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

Disposal phase experimental program plan

International Nuclear Information System (INIS)

1997-01-01

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

Pathways to man for radionuclides released from disposal sites on land

International Nuclear Information System (INIS)

Hill, M.D.

1986-01-01

To predict the potential radiological impact on man of the disposal of radioactive wastes it is necessary to identify all the events and processes that could cause releases of radionuclides into the environment, to estimate their probabilities of occurrence and to calculate their consequences, for both individuals and populations. This paper briefly reviews the types of releases that have to be considered for land disposal sites and describes the mathematical models used to calculate rates of transport of radionuclides through the environment and doses to man. The difficulties involved in predicting environmental conditions in the far future are discussed, in the light of the ways in which the results of consequence calculations will be used. Assessments of land disposal of long-lived and highly radioactive wastes are briefly reviewed, with the aim of identifying the most important radionuclides and exposure pathways, and the areas where the models and their databases require improvement. (author)

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

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

The land disposal of organic materials in radioactive wastes: international practice and regulation

International Nuclear Information System (INIS)

Hooper, A.J.

1988-01-01

World-wide practice and regulation with regard to organic materials in radioactive wastes for land disposal have been examined with a view to establishing, where possible, their scientific justification and their relevance to disposal of organic-bearing wastes in the UK. (author)

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

Selection of Computer Codes for Shallow Land Waste Disposal in PPTA Serpong

International Nuclear Information System (INIS)

Syahrir

1996-01-01

Selection of Computer Codes for Shallow Land Waste Disposal in PPTA Serpong. Models and computer codes have been selected for safety assessment of near surface waste disposal facility. This paper provides a summary and overview of the methodology and codes selected. The methodology allows analyses of dose to individuals from offsite releases under normal conditions as well as on-site doses to inadvertent intruders. A demonstration in the case of shallow land waste disposal in Nuclear Research Establishment are in Serpong has been given for normal release scenario. The assessment includes infiltration of rainfall, source-term, ground water (well) and surface water transport, food-chain and dosimetry. The results show dose history of maximally exposed individuals. The codes used are VS2DT, PAGAN and GENII. The application of 1 m silt loam as a moisture barrier cover decreases flow in the disposal unit by a factor of 27. The selected radionuclides show variety of dose histories according to their chemical and physical characteristics and behavior in the environment

Basic concept on safety regulation for land disposal of low level radioactive solid wastes

International Nuclear Information System (INIS)

1985-01-01

As to the land disposal of low level radioactive solid wastes, to which the countermeasures have become the urgent problem at present, it is considered to be a realistic method to finally store the solid wastes concentratedly outside the sites of nuclear power stations and others, and effort has been exerted by those concerned to realize it. Besides, as for extremely low level radioactive solid wastes, the measures of disposing them corresponding to the radioactivity level are necessary, and the concrete method has been examined. The Committee on Safety Regulation for Radioactive Wastes has discussed the safety regulation for those since April, 1984, and the basic concept on the safety regulation was worked up. It is expected that the safety of the land disposal of low level radioactive solid wastes can be ensured when the safety regulation is carried out in conformity with this basic concept. The present status of the countermeasures to the land disposal of low level radioactive solid wastes is shown. As the concrete method, the disposal in shallow strate has been generally adopted. At present, the plan for the final storage in Aomori Prefecture is considered, and it will be started with the first stage of four-stage control. (Kako, I.)

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

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.

1984-06-01

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

Managing previously disposed waste to today's standards

International Nuclear Information System (INIS)

1990-01-01

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

The disposal of solid radioactive wastes to land sites in the UK

International Nuclear Information System (INIS)

Ginniff, M.E.; Phillipson, D.L.

1984-01-01

Solid radioactive waste management by land disposal, using a strategy laid down by the government, is discussed. Waste disposal at Drigg, and the proposals for the two preferred sites at Elstow (shallow burial) and Billingham (deep burial) are outlined. Nuclear Industry Radioactive Waste Executive (NIREX); safety; public acceptance; and the role of the private sector; are also described. (U.K.)

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

Science.gov (United States)

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

76 FR 55711 - Confirmatory Order Modifying License No. SNM-2001 for the Shallow Land Disposal Area, Parks...

Science.gov (United States)

2011-09-08

... NUCLEAR REGULATORY COMMISSION [Docket No. 40-8907; NRC-2011-0193] Confirmatory Order Modifying License No. SNM-2001 for the Shallow Land Disposal Area, Parks Township, Armstrong County, PA; Notice of... (SNM), pursuant to the terms and conditions of the aforementioned License, at the Shallow Land Disposal...

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

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

Report on audit of the US Department of Energy's identification and disposal of nonessential land

International Nuclear Information System (INIS)

1997-01-01

This document presents the results of an audit of four US DOE facilities to determine whether any land holdings are excess to current and anticipated future needs. Facilities audited were the Hanford Site, the Oak Ridge Reservation, the Idaho National Engineering Laboratory, and the Brookhaven Laboratory. Audit findings were that 309,000 acres at the Hanford, Oak Ridge, and Idaho sites were not essential to carrying out current and foreseeable mission requirements. It is recommended that the DOE dispose of the nonessential land holdings, reevaluate requirements for remaining land holdings and dispose of any additional nonessential land, and reevaluate the policy of defining ecosystem management as a valid basis for retaining Department real property. 2 tabs

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

Low level radioactive waste disposal: An evaluation of reports comparing ocean and land based disposal options

International Nuclear Information System (INIS)

1990-05-01

This document evaluates reports presenting comparative assessments of land and sea disposal options for low and intermediate level radioactive waste. It was performed following a request by the LDC to the IAEA. In this evaluation, IAEA Safety Series No. 65 ''Environmental Assessment Methodologies for Sea Dumping of Radioactive Wastes'', was used as the main reference in reviewing the comparative assessments made to date. IAEA Safety Series No. 65 gives guidance on the performance of comparative assessments of the different options, and provides a list and scheme of factors to be considered. 5 studies were transmitted by the Contracting Parties and considered in this review. A larger number of reports was not considered in this effort on the basis that the evaluation would be most effective if directed at those studies which specifically compared ocean disposal with land based disposal in a consistent manner. It is not the purpose of this report to state whether one document is better than another or whether one report forms a good blueprint for future assessments. This would require a different type of review and is outside the scope of this document. Indeed since the purposes of the five reports were originally so different it would not be possible to produce such a ranking and any attempts in that direction would be very misleading. 11 refs, 3 tabs

Status report on the Nuclear Regulatory Commission regulations for land disposal of low-level radioactive wastes and geologic repository disposal of high-level wastes

International Nuclear Information System (INIS)

Browning, R.E.; Bell, M.J.; Dragonette, K.S.; Johnson, T.C.; Roles, G.W.; Lohaus, P.H.; Regnier, E.P.

1984-01-01

On 27 December 1982, the United States Nuclear Regulatory Commission (NRC) amended its regulations to provide specific requirements for licensing the land disposal of low-level radioactive wastes. The regulations establish performance objectives for land disposal of waste; technical requirements for the siting, design, operations, and closure activities for a near-surface disposal facility; technical requirements concerning waste form and classification that waste generators must meet for the land disposal of waste; institutional requirements; financial assurance requirements; and administrative and procedural requirements for licensing a disposal facility. Waste generators must comply with the waste form and classification provisions of the new rule, on 27 December 1983, one year later. During this implementation period, licensees must develop programmes to ensure compliance with the new waste form and classification provisions. The NRC is also promulgating regulations specifying the technical criteria for disposal of high-level radioactive wastes in geological repositories. The proposed rule was published for public comment in July 1981. Public comments have been received and considered by the Commission staff. The Commission will soon approve and publish a revised final rule. While the final rule being considered by the Commission is fundamentally the same as the proposed rule, provisions have been added to permit flexibility in the application of numerical criteria, some detailed design requirements have been deleted, and other changes have been made in response to comments. The rule is consistent with the recently enacted Nuclear Waste Policy Act of 1982. (author)

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

Acceptance test procedure: RMW Land Disposal Facility Project W-025

International Nuclear Information System (INIS)

Roscha, V.

1994-01-01

This ATP establishes field testing procedures to demonstrate that the electrical/instrumentation system functions as intended by design for the Radioactive Mixed Waste Land Disposal Facility. Procedures are outlined for the field testing of the following: electrical heat trace system; transducers and meter/controllers; pumps; leachate storage tank; and building power and lighting

75 FR 816 - Identification of Additional Classes of Facilities for Development of Financial Responsibility...

Science.gov (United States)

2010-01-06

... land, air and surface water, including those disposed of in RCRA Subtitle C hazardous waste land... inputs, (2) chemical reactions and synthesis, and (3) recovery of reaction products through purification... or products must be isolated and purified, and this [[Page 824

Development of a treatability variance guidance document for US DOE mixed-waste streams

International Nuclear Information System (INIS)

Scheuer, N.; Spikula, R.; Harms, T.

1990-03-01

In response to the US Department of Energy's (DOE's) anticipated need for variances from the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs), a treatability variance guidance document was prepared. The guidance manual is for use by DOE facilities and operations offices. The manual was prepared as a part of an ongoing effort by DOE-EH to provide guidance for the operations offices and facilities to comply with the RCRA (LDRs). A treatability variance is an alternative treatment standard granted by EPA for a restricted waste. Such a variance is not an exemption from the requirements of the LDRs, but rather is an alternative treatment standard that must be met before land disposal. The manual, Guidance For Obtaining Variance From the Treatment Standards of the RCRA Land Disposal Restrictions (1), leads the reader through the process of evaluating whether a variance from the treatment standard is a viable approach and through the data-gathering and data-evaluation processes required to develop a petition requesting a variance. The DOE review and coordination process is also described and model language for use in petitions for DOE radioactive mixed waste (RMW) is provided. The guidance manual focuses on RMW streams, however the manual also is applicable to nonmixed, hazardous waste streams. 4 refs

A database for compliance with land disposal restrictions

International Nuclear Information System (INIS)

McCoy, M.W.

1990-09-01

The new restrictions on land disposal introduce additional challenges to hazardous waste managers. Laboratory waste streams consisting of small volumes of diverse waste types will be particularly difficult to manage due to the large number of possible treatment standards that could be applied. To help remedy this management problem, a user-friendly database has been developed to provide the regulatory information required for each of the hazardous wastes present in the wastes stream of a large research laboratory. 3 figs., 1 tab

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

International Nuclear Information System (INIS)

1996-02-01

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

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

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

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

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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

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.

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

Science.gov (United States)

2013-10-31

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

25 CFR 15.3 - Who can make a will disposing of trust or restricted land or trust personalty?

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Who can make a will disposing of trust or restricted land or trust personalty? 15.3 Section 15.3 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR... Introduction § 15.3 Who can make a will disposing of trust or restricted land or trust personalty? Any person...

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

1996 Hanford site report on land disposal restrictions for mixed waste

International Nuclear Information System (INIS)

Black, D.G.

1996-04-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order milestone M-26-OIF. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal-restricted mixed waste management at the Hanford Site

1996 Hanford site report on land disposal restrictions for mixed waste

Energy Technology Data Exchange (ETDEWEB)

Black, D.G.

1996-04-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order milestone M-26-OIF. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal-restricted mixed waste management at the Hanford Site.

Data quality objectives for two risk assessments at Hanford

International Nuclear Information System (INIS)

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

1996-01-01

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

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

International Nuclear Information System (INIS)

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

1994-01-01

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

Technical resource documents and technical handbooks for hazardous-wastes management

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.; Bliss, T.M.

1986-07-01

The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

Operational policy for disposal of land-derived wastewater to the marine environment of South Africa

CSIR Research Space (South Africa)

Taljaard, Susan

2006-10-01

Full Text Available , amongst others. To fulfil its legal obligation in terms of the management and control of land-derived wastewater discharges (classified as a water use under the National Water Act), DWAF adopted the operational policy for disposal of land-derived water...

Modeling of release of radionuclides from an engineered disposal facility for shallow-land disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Matsuzuru, H.; Suzuki, A.

1989-01-01

The computer code, ENBAR-1, for the simulation of radionuclide releases from an engineered disposal facility has been developed to evaluate the source term for subsequent migration of radionuclides in and through a natural barrier. The system considered here is that a waste package (waste form and container) is placed, together with backfill materials, into a concrete pit as a disposal unit for shallow-land disposal of low-level radioactive wastes. The code developed includes the following modules: water penetration into a concrete pit, corrosion of a drum as a container, leaching of radionuclides from a waste form, migration of radionuclides in backfill materials, release of radionuclides from the pit. The code has the advantage of its simplicity of operation and presentation while still allowing comprehensive evaluation of each element of an engineered disposal facility to be treated. The performance and source term of the facility might be readily estimated with a few key parameters to define the problem

State workshop on shallow land burial and alternative disposal concepts: proceedings

International Nuclear Information System (INIS)

1984-10-01

Three of the major conclusions reached by state participants were the following: (1) Significant data gaps and information needs have to be addressed before timely state decisionmaking can be accomplished. State participants felt a generic cost/risk/benefit analysis for all viable alternatives would be useful and might best be performed by the federal government on behalf of the states. (2) Recognizing the imprecision in summarizing overall attitudes of the workshop participants, alternative disposal concepts that appear to be the most favorably perceived when rank ordered by critical factors are augered holes with liners, belowground vaults, earth mounded concrete bunkers, aboveground vaults and mined cavities. (3) The public appears to place greater confidence in disposal methods that incorporate man-made engineered barriers because of some past problems at closed shallow land burial facilities. Concern was expressed by workshop participants that the public may not consider the perceived risks associated with shallow land burial to be acceptable. In addition to the four 10 CFR Part 61, Subpart C performance objectives, public acceptance of risk was considered to be a critical factor by state officials in selecting a disposal technology. The states should take the lead in pursuing development-oriented analyses, such as detailed concept engineering and economic feasibility studies. It is not within the purview of NRC responsibility to undertake such studies

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

1999 Report on Hanford Site land disposal restriction for mixed waste

International Nuclear Information System (INIS)

BLACK, D.G.

1999-01-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility

1999 Report on Hanford Site land disposal restriction for mixed waste

Energy Technology Data Exchange (ETDEWEB)

BLACK, D.G.

1999-03-25

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility.

Guidance: Demonstrating Compliance with the Land Disposal Restrictions (LDR) Alternative Soil Treatment Standards

Science.gov (United States)

This guidance provides suggestions and perspectives on how members of the regulated community, states, and the public can demonstrate compliance with the alternative treatment standards for certain contaminated soils that will be land disposed.

Unique issues concerning ''placement'' vs ''movement'' of contaminated soils at ORNL's CERCLA sites

International Nuclear Information System (INIS)

Greer, J.K. Jr.; Schrof, C.A.

1992-01-01

At Oak Ridge National Laboratory, which is owned and operated by the US Department of Energy (DOE), there are several areas where hazardous wastes and/or radioactive materials have been placed in shallow land burial trenches or ''auger'' holes for disposal. Since Oak Ridge Reservation (ORR) has been placed on the National Priority List (NPL) by the US Environmental Protection Agency (EPA), the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) applies to waste disposal sites at ORNL. Under CERCLA, the RCRA regulations, pertaining to the LDRs, apply to CERCLA activities if the regulations are deemed ''applicable or relevant and appropriate'' (ARARS) by the lead agency or by the EPA. This report discusses the following issue: Under what conditions will contaminated soil and debris generated at a Superfund site be subject to the Resource Conservation and Recovery Act (RCRA) land disposal restrictions (LDRs) treatment standards?

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

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

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

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

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)...

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

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

International Nuclear Information System (INIS)

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

1993-01-01

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

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...

75 FR 6360 - Information on Surplus Land at a Military Installation Designated for Disposal: Newport Naval...

Science.gov (United States)

2010-02-09

... Installation Designated for Disposal: Newport Naval Complex, Newport, RI--Former Naval Hospital, Newport... designation, on January 5, 2009, land and facilities at this installation were declared excess to the... the land and facilities at Newport Naval Complex: Former Naval Hospital, Newport, Former Navy Lodge...

Toxic and hazardous waste disposal. Volume 4. New and promising ultimate disposal options

International Nuclear Information System (INIS)

Pojasek, R.B.

1980-01-01

Separate abstrats were prepared for four of the eighteen chapters of this book which reviews several disposal options available to the generators of hazardous wastes. The chapters not abstracted deal with land disposal of hazardous wastes, the solidification/fixation processes, waste disposal by incineration and molten salt combustion and the use of stabilized industrial waste for land reclamation and land farming

Land application of sewage sludge: A guide for land appliers on the requirements of the federal standards for the use or disposal of sewage sludge, 40 CFR part 503

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

The U.S. Environmental Protection Agency promulgated a regulation at 40 Code of Federal Regulations (CFR) Part 503 to ensure that sewage sludge is used or disposed of in a way that protects human health and the environment. Part 503 imposes requirements for the land application, surface disposal, and incineration of sewage sludge. The manual focuses on land application, providing guidance to land appliers of sewage sludge. The purpose of the document is to provide the land applier with sufficient guidance to comply fully with all applicable Part 503 requirements. The guidance is structured to first provide a general understanding of the Rule and its underlying principles, including definitions of sewage sludge, land application, and an explanation of who under the Rule is considered a land applier.

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

International Nuclear Information System (INIS)

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

1992-02-01

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

1994 Characterization report for the state approved land disposal site

International Nuclear Information System (INIS)

Swanson, L.C.

1994-01-01

This report summarizes the results of characterization activities at the proposed state-approved land disposal site (SALDS); it updates the original characterization report with studies completed since the first characterization report. The initial characterization report discusses studies from two characterization boreholes, 699-48-77A and 699-48-77B. This revision includes data from implementation of the Groundwater Monitoring Plan and the Aquifer Test Plan. The primary sources of data are two down-gradient groundwater monitoring wells, 699-48-77C and 699-48-77D, and aquifer testing of three zones in well 699-48-77C. The SALDS is located on the Hanford Site, approximately 183 m north of the 200 West Area on the north side of the 200 Areas Plateau. The SALDS is an infiltration basin proposed for disposal of treated effluents from the 200 Areas of Hanford

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.

Response to comments background document for the Third Third land-disposal restrictions proposed rule November 22, 1989 (54 FR 48372). Volume 2-2. Capacity-related comments

International Nuclear Information System (INIS)

1990-01-01

On November 22, 1989, the Environmental Protection Agency (EPA, the Agency) proposed a rule to prohibit the land disposal of the final third of the schedule of restricted hazardous wastes, known as the Third Third (see 54 Federal Register 48372). The proposal outlined treatment standards and effective dates of prohibition for these wastes as well as for some First and Second Third soft hammer wastes, characteristic wastes, certain waste groups (e.g., multi-source leachate, radioactive mixed waste), and newly listed wastes. The proposed rule was issued pursuant to the 1984 Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act (RCRA). The Agency requested public comment on the proposal. The regulated community, environmental organizations, trade associations, State and Federal agencies, and concerned citizens submitted over 300 written letters on the proposed rule. EPA developed three volumes of a comment response document. This document (Volume 2 of 3) presents a summary of and responses to capacity-related comments received by the EPA docket clerk in response to the proposed rule. The comments have been divided into 17 chapters, each addressing specific comment categories. This volume contains Chapters 8-12. These chapters discuss mercury wastes, other metals, F, K, U, and P wastes, KO48-KO52 wastes, and deepwell injected wastes

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

Land suitability for waste disposal in metropolitan areas.

Science.gov (United States)

Baiocchi, Valerio; Lelo, Keti; Polettini, Alessandra; Pomi, Raffaella

2014-08-01

Site selection for waste disposal is a complex task that should meet the requirements of communities and stakeholders. In this article, three decision support methods (Boolean logic, index overlay and fuzzy gamma) are used to perform land suitability analysis for landfill siting. The study was carried out in one of the biggest metropolitan regions of Italy, with the objective of locating suitable areas for waste disposal. Physical and socio-economic information criteria for site selection were decided by a multidisciplinary group of experts, according to state-of-the-art guidelines, national legislation and local normative on waste management. The geographic information systems (GIS) based models used in this study are easy to apply but require adequate selection of criteria and weights and a careful evaluation of the results. The methodology is arranged in three steps, reflecting the criteria defined by national legislation on waste management: definition of factors that exclude location of landfills or waste treatment plants; classification of the remaining areas in terms of suitability for landfilling; and evaluation of suitable sites in relation to preferential siting factors (such as the presence of quarries or dismissed plants). The results showed that more than 80% of the provincial territory falls within constraint areas and the remaining territory is suitable for waste disposal for 0.72% or 1.93%, according to the model. The larger and most suitable sites are located in peripheral areas of the metropolitan system. The proposed approach represents a low-cost and expeditious alternative to support the spatial decision-making process. © The Author(s) 2014.

Draft Hanford Remedial Action Environmental Impact Statement and Comprehensive Land Use Plan: Volume 2 of 4

International Nuclear Information System (INIS)

1996-08-01

This appendix discusses the scope of actions addressed in the Draft Hanford Remedial Action Environmental Impact Statement and Comprehensive Land Use Plan. To address the purpose and need for agency action identified in Chapter 2.0 of the HRA-EIS, the scope includes an evaluation of the potential environmental impacts associated with the remedial actions to be conducted by the US Department of Energy (DOE) under the provisions of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1989). These remedial actions would bring the Hanford Site into compliance with the applicable requirements of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and the Resource Conservation and Recovery Act of 1976 (RCRA). The DOE program responsible for conducting remedial actions at the Hanford Site is referred to as the Richland Environmental Restoration (ER) Project. The Richland ER Project encompasses the following projects: radiation area remedial actions and underground storage tanks (UST); RCRA closures; single-shell tank (SST) closures; past-practice waste site operable unit (source and groundwater) remedial actions; surplus facility decommissioning; and waste storage and disposal facilities

Geomorphologic characteristic of low-intermediate level radioactive waste disposal land candidate at Lemahabang area

International Nuclear Information System (INIS)

Sucipta

1998-01-01

Geomorphological aspect is a factor should be considered on land evaluation for radioactive wastes disposal purpose. The aspect is important because geomorphological factors contribute on hydrological and erosion condition of the land. The objective of the study is to characterize the geomorphological condition of the land, i.e. land form, geomorphological processes, rock type, soil, surface water, ground water, vegetation and land use. The study was conducted by descriptive analyses from literature study and field geomorphological method, with evaluation as well as developed for terrain analyses. The study area can be divided industry for land from units, I.e. tuff undulating unit (land use: plantation), coastal deposits plain unit, silty sand fluvial plain unit (land use: wet rice field) and unconsolidated sand beach deposits plain unit (opened land without vegetation). Hydrologically, the study area can be divided indus tri three small river stream area (RSA). Detailed description of geomorfological condition is showed by table and geomorphological map. (author)

Shallow land disposal technology

Energy Technology Data Exchange (ETDEWEB)

Pillette-Cousin, L. [Nuclear Environment Technology Insitute, Taejon (Korea, Republic of Korea )

1997-12-31

This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L`Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs.

Shallow land disposal technology

International Nuclear Information System (INIS)

Pillette-Cousin, L.

1997-01-01

This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L'Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs

Implications of stillage land disposal: a critical review on the impacts of fertigation.

Science.gov (United States)

Fuess, Lucas Tadeu; Garcia, Marcelo Loureiro

2014-12-01

Stillage is the main wastewater from ethanol production, generated specifically in the step of distillation. Regardless the feedstock, stillage contains high concentrations of organic matter, potassium and sulfates, as well as acidic and corrosive characteristics. Currently almost the entire volume of stillage generated in Brazilian distilleries is directed to the fertigation of sugarcane fields, due to its fertilizer character. However, the polluting potential of stillage characterizes its land disposal as problematic, considering probable negative impacts on the soil structure and water resources in case of excessive dosages. Since the literature lacks critical content describing clearly the cons related to the reuse of stillage in agriculture in the long-term, this review aimed to assess the real polluting potential of stillage, and the implications of its land disposal and/or discharge into water bodies. Evidence from the literature indicate that the main obstacles to reuse stillage in natura include risks of soil salinization; clogging of pores, reduction in the microbial activity and the significant depletion of dissolved oxygen concentrations in water bodies; contamination per nitrates and eutrophication; soil structure destabilization due to high concentrations of potassium and sodium; and, possible acidification of soil and water resources, considering the low pH of stillage (∼4,5). Toxic metals, such as cadmium, lead, copper, chromium and nickel, were also identified in concentrations above the recommended limits in stillage samples, increasing risks to human health (e.g. carcinogenic potential) and to crops (e.g. productivity loss). In short, although some studies report benefits from the land application of stillage, its treatment prior to disposal is essential to make fertigation an environmentally suitable practice. Copyright © 2014 Elsevier Ltd. All rights reserved.

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

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.

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.

Reducing biosolids disposal costs using land application in forested areas

International Nuclear Information System (INIS)

Huffines, R.L.

1995-01-01

Switching biosolids land application from a reclamation site to a forested site significantly reduced the cost of biosolids disposal at the Savannah River Site. Previous beneficial reuse programs focused on reclamation of existing borrow pits. While extremely beneficial, this program became very costly due to the regulatory requirements for groundwater monitoring, soil monitoring and frequent biosolids analyses. A new program was developed to reuse biosolids in forested areas where the biosolids could be used as a soil conditioner and fertilizer to enhance timber yield. The forested land application site was designed so that groundwater monitoring and soil monitoring could be eliminated while biosolids monitoring and site maintenance were minimized. Monitoring costs alone were reduced by 80%. Capital costs for site preparation were also significantly reduced since there was no longer a need for expensive groundwater monitoring wells

Disposal facilities on land for low and intermediate-level radioactive wastes: draft principles for the protection of the human environment

International Nuclear Information System (INIS)

1983-10-01

This document gives the views of the authorising [United Kingdom] Departments under the Radioactive Substances Act 1960 about the principles which those Departments should follow in assessing proposals for land disposal facilities for low and intermediate-level radioactive wastes. It is based on relevant research findings and reports by international bodies; but has been prepared at this stage as a draft on which outside comments are sought, and is subject to revision in the light of those comments. That process of review will lead to the preparation and publication of a definitive statement of principles, which will be an important background document for public inquiries into proposals to develop sites for land disposal facilities. Headings are: authorisation of disposal; other legislation governing new disposal facilities; basic radiological requirements; general principles; information requirements. (author)

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.

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

Science.gov (United States)

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

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

1994-05-01

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

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

International Nuclear Information System (INIS)

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

1994-05-01

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

76 FR 34200 - Land Disposal Restrictions: Revision of the Treatment Standards for Carbamate Wastes

Science.gov (United States)

2011-06-13

... to meet numeric concentration limits before they can be land disposed. However, the lack of readily available analytical standards makes it difficult to measure whether the numeric LDR concentration limits...-0332, by one of the following methods: http://www.regulations.gov : Follow the on-line instructions for...

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-03-01

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

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

International Nuclear Information System (INIS)

Palmer, E.

1996-03-01

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

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

International Nuclear Information System (INIS)

Ludowise, J. D.

1999-01-01

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

Potential for effects of land contamination on human health. 2. The case of waste disposal sites.

Science.gov (United States)

Kah, Melanie; Levy, Len; Brown, Colin

2012-01-01

This review of the epidemiological literature shows that evidence for negative impacts of land contaminated by waste disposal on human health is limited. However, the potential for health impacts cannot be dismissed. The link between residence close to hazardous waste disposal sites and heightened levels of stress and anxiety is relatively well established. However, studies on self-reported outcomes generally suffer from interpretational problems, as subjective symptoms may be due to increased perception and recall. Several recent multiple-site studies support a plausible linkage between residence near waste disposal sites and reproductive effects (including congenital anomalies and low birth weight). There is some conflict in the literature investigating links between land contamination and cancers; the evidence for and against a link is equally balanced and is insufficient to make causal inferences. These are difficult to establish because of lack of data on individual exposures, and other socioeconomic and lifestyle factors that may confound a relationship with area of residence. There is no consistently occurring risk for any specific tumor across multiple studies on sites expected to contain similar contaminants. Further insights on health effects of land contamination are likely to be gained from studies that consider exposure pathways and biomarkers of exposure and effect, similar to those deployed with some success in investigating impacts of cadmium on human health.

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

Low-level waste shallow land disposal source term model: Data input guides

International Nuclear Information System (INIS)

Sullivan, T.M.; Suen, C.J.

1989-07-01

This report provides an input guide for the computational models developed to predict the rate of radionuclide release from shallow land disposal of low-level waste. Release of contaminants depends on four processes: water flow, container degradation, waste from leaching, and contaminant transport. The computer code FEMWATER has been selected to predict the movement of water in an unsaturated porous media. The computer code BLT (Breach, Leach, and Transport), a modification of FEMWASTE, has been selected to predict the processes of container degradation (Breach), contaminant release from the waste form (Leach), and contaminant migration (Transport). In conjunction, these two codes have the capability to account for the effects of disposal geometry, unsaturated/water flow, container degradation, waste form leaching, and migration of contaminants releases within a single disposal trench. In addition to the input requirements, this report presents the fundamental equations and relationships used to model the four different processes previously discussed. Further, the appendices provide a representative sample of data required by the different models. 14 figs., 27 tabs

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

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

Household hazardous waste disposal to landfill: Using LandSim to model leachate migration

International Nuclear Information System (INIS)

Slack, Rebecca J.; Gronow, Jan R.; Hall, David H.; Voulvoulis, Nikolaos

2007-01-01

Municipal solid waste (MSW) landfill leachate contains a number of aquatic pollutants. A specific MSW stream often referred to as household hazardous waste (HHW) can be considered to contribute a large proportion of these pollutants. This paper describes the use of the LandSim (Landfill Performance Simulation) modelling program to assess the environmental consequences of leachate release from a generic MSW landfill in receipt of co-disposed HHW. Heavy metals and organic pollutants were found to migrate into the zones beneath a model landfill site over a 20,000-year period. Arsenic and chromium were found to exceed European Union and US-EPA drinking water standards at the unsaturated zone/aquifer interface, with levels of mercury and cadmium exceeding minimum reporting values (MRVs). The findings demonstrate the pollution potential arising from HHW disposal with MSW. - Aquatic pollutants linked to the disposal of household hazardous waste in municipal landfills have the potential to exist in soil and groundwater for many years

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

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

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

International Nuclear Information System (INIS)

1997-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

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

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.

Low level waste disposal

International Nuclear Information System (INIS)

Barthoux, A.

1985-01-01

Final disposal of low level wastes has been carried out for 15 years on the shallow land disposal of the Manche in the north west of France. Final participant in the nuclear energy cycle, ANDRA has set up a new waste management system from the production center (organization of the waste collection) to the disposal site including the setting up of a transport network, the development of assessment, additional conditioning, interim storage, the management of the disposal center, records of the location and characteristics of the disposed wastes, site selection surveys for future disposals and a public information Department. 80 000 waste packages representing a volume of 20 000 m 3 are thus managed and disposed of each year on the shallow land disposal. The disposal of low level wastes is carried out according to their category and activity level: - in tumuli for very low level wastes, - in monoliths, a concrete structure, of the packaging does not provide enough protection against radioactivity [fr

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

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

International Nuclear Information System (INIS)

Case, J.T.; Rhoderick, J.

1994-01-01

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

Calendar Year 2002 Hanford Site mixed waste land disposal restrictions report (section 1 thru 3)

International Nuclear Information System (INIS)

MISKHO, A.G.

2003-01-01

Volume 1 presents information concerning the storage and minimization of mixed waste and the potential sources for the generation of additional mixed waste. This information, presented in accordance with ''Hanford Federal Facility Agreement and Consent Order'' (Tri-Party Agreement) (Ecology et al. 2001) Milestone M-26-01M, is Volume 1 of a two-volume report on the status of Hanford Site land disposal restricted mixed waste, other mixed waste, and other waste that the U.S. Department of Energy (DOE), Washington State Department of Ecology (Ecology), and US. Environmental Protection Agency (EPA) have agreed to include in this report. This volume contains the approval page for both volumes and includes the storage report. Information pertaining to waste characterization and treatment are addressed in Volume 2. Appendix A lists the land disposal restrictions (LDR) reporting requirements and explains where the requirements are addressed in this report. The reporting period for this document is from January 1, 2002, to December 31, 2002. Clearance form only sent to RHA

Overview of EPA's environmental standards for the land disposal of LLW and NARM waste - 1988

International Nuclear Information System (INIS)

Gruhlke, J.M.; Galpin, F.L.; Holcomb, W.F.

1988-01-01

The Environmental Protection Agency program to develop proposed generally applicable environmental standards for land disposal of low-level radioactive waste (LLW) and certain naturally occurring and accelerator-produced radioactive wastes has been completed. The elements of the proposed standards include the following: (a) exposure limits for predisposal management and storage operations, (b) criteria for other regulatory agencies to follow in specifying wastes that are below regulatory concern; (c) postdisposal exposure limits, (d) groundwater protection requirements, and (e) qualitative implementation requirements. In addition to covering those radioactive wastes subject to the Atomic Energy Act, the Agency also intends to propose a standard to require the disposal of high concentration, naturally occurring and accelerator-produced radioactive materials wastes exceeding 2 nCi/g, excluding a few consumer items, in regulated LLW disposal facilities

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

Shallow land disposal, the french system

International Nuclear Information System (INIS)

Barthoux, A.; Marque, Y.

1986-01-01

Since 1969, low and medium activity waste are disposed of in France at the Centre Manche. The management system set up covers the whole of the operations, from the sorting of the wastes and their conditioning to the final disposal. Safety standards and technical issues were found satisfactory by the National Safety Authority and they are the basis of the program for the realization of two new disposal sites which should take over from the Centre Manche loaded towards 1990. ANDRA, a National Agency, is responsible for the long term management of radioactive waste, in France [fr

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

Household hazardous waste disposal to landfill: using LandSim to model leachate migration.

Science.gov (United States)

Slack, Rebecca J; Gronow, Jan R; Hall, David H; Voulvoulis, Nikolaos

2007-03-01

Municipal solid waste (MSW) landfill leachate contains a number of aquatic pollutants. A specific MSW stream often referred to as household hazardous waste (HHW) can be considered to contribute a large proportion of these pollutants. This paper describes the use of the LandSim (Landfill Performance Simulation) modelling program to assess the environmental consequences of leachate release from a generic MSW landfill in receipt of co-disposed HHW. Heavy metals and organic pollutants were found to migrate into the zones beneath a model landfill site over a 20,000-year period. Arsenic and chromium were found to exceed European Union and US-EPA drinking water standards at the unsaturated zone/aquifer interface, with levels of mercury and cadmium exceeding minimum reporting values (MRVs). The findings demonstrate the pollution potential arising from HHW disposal with MSW.

The disposal of radioactive waste on land

Energy Technology Data Exchange (ETDEWEB)

None

1957-09-01

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

Glossary of CERCLA, RCRA and TSCA related terms and acronyms

International Nuclear Information System (INIS)

1993-10-01

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

1995 Report on Hanford site land disposal restrictions for mixed waste

International Nuclear Information System (INIS)

Black, D.G.

1995-04-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order Milestone M-26-01E. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal restricted mixed waste at the Hanford Site. The U.S. Department of Energy, its predecessors, and contractors at the Hanford Site were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 and Atomic Energy Act of 1954. This report covers mixed waste only. The Washington State Department of Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (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 (LDRs) plan and its annual updates to comply with LDR requirements for radioactive mixed waste. This report is the fifth update of the plan first issued in 1990. Tri-Party Agreement negotiations completed in 1993 and approved in January 1994 changed and added many new milestones. Most of the changes were related to the Tank Waste Remediation System and these changes are incorporated into this report

1995 Report on Hanford site land disposal restrictions for mixed waste

Energy Technology Data Exchange (ETDEWEB)

Black, D.G.

1995-04-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order Milestone M-26-01E. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal restricted mixed waste at the Hanford Site. The U.S. Department of Energy, its predecessors, and contractors at the Hanford Site were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 and Atomic Energy Act of 1954. This report covers mixed waste only. The Washington State Department of Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (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 (LDRs) plan and its annual updates to comply with LDR requirements for radioactive mixed waste. This report is the fifth update of the plan first issued in 1990. Tri-Party Agreement negotiations completed in 1993 and approved in January 1994 changed and added many new milestones. Most of the changes were related to the Tank Waste Remediation System and these changes are incorporated into this report.

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

International Nuclear Information System (INIS)

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

1995-10-01

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

Preliminary criteria for shallow-land storage/disposal of low-level radioactive solid waste in an arid environment

International Nuclear Information System (INIS)

Shord, A.L.

1979-09-01

Preliminary criteria for shallow land storage/disposal of low level radioactive solid waste in an arid environment were developed. Criteria which address the establishment and operation of a storage/disposal facility for low-level radioactive solid wastes are discussed. These were developed from the following sources: (1) a literature review of solid waste burial; (2) a review of the regulations, standards, and codes pertinent to the burial of radioactive wastes; (3) on site experience; and (4) evaluation of existing burial grounds and practices

Guidance documents relating to landfills and contaminants

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.; Zunt, D.A.

1990-01-01

The Environmental Protection Agency is developing and updating a series of Technical Guidance Documents to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA), respectively. These documents are the compilation of the research efforts to date relating to containment of pollutants from waste disposal to the land as relates to residuals management. The specific areas of research being conducted under the RCRA land disposal program relates to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The specific areas of research being conducted under the CERCLA uncontrolled waste sites (Superfund) program relate to in situ treatment, solidification/stabilization for treating hazardous waste, combustion technologies, best demonstrated available technology (BDAT), on-site treatment technologies, emerging biosystems, expert systems, personnel health protection equipment, and site and situation assessment. The Guidance Documents are intended to assist both the regulated community and the permitting authorities, as well as the Program Offices, and Regions, as well as the states and other interested parties, with the latest information relevant to waste management.

WRAP module 1 treatment plan

International Nuclear Information System (INIS)

Mayancsik, B.A.

1995-05-01

This document provides the methodology to treat waste in the Waste Receiving and Processing Module 1 facility to meet the Resource Conservation and Recovery Act (RCRA) land disposal restrictions or the Waste Isolation and Pilot Plant waste acceptance criteria. This includes Low-Level Mixed Waste, Transuranic Waste, and Transuranic Mixed Waste

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

International Nuclear Information System (INIS)

1992-11-01

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

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.

Analysis of the impacts of the 1984 Resource Conservation and Recovery Act amendments on the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Falconer, K.L.; Davis, K.D.; Johnson, R.D.; Nishimoto, D.D.; Wallace, M.T.

1986-02-01

The November 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) have had, and will continue to have, a significant impact on the management of hazardous and radioactive mixed waste at the Idaho National Engineering Laboratory (INEL). These Amendments include new requirements specific to federal facilities such as the INEL. In this paper, areas of direct impact and associated INEL plans for complying with the 1984 RCRA Amendments will be described. The specific areas to be covered are the following: (1) changes in RCRA Part B permitting, including requirements for addressing past hazardous waste TSD sites; (2) the effects of increased restrictions on land disposal; (3) new requirements for undergrond tanks; (4) requirements for federal facilities; and (5) mandatory minimization of waste generation

Development activities on shallow land disposal of solid radioactive waste. Progress report, January--December 1976

International Nuclear Information System (INIS)

1977-06-01

Progress on projects focused on problems of shallow land burial of radioactively contaminated solid waste is summarized. Developments on a system to evaluate the containment adequacy of existing burial sites are described. Efforts to describe the environmental factors in monitoring the LASL disposal sites are discussed. The aim of a new program on radioactive waste burial technology is outlined

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

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.

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

International Nuclear Information System (INIS)

1990-01-01

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

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

Science.gov (United States)

Nancarrow, D J; White, M M

2004-03-01

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land

International Nuclear Information System (INIS)

Nancarrow, D J; White, M M

2004-01-01

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950 000 m 3 ). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

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

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.

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

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.

Corrective action management unit application for the Environmental Restoration Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Evans, G.C.

1994-06-01

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

Corrective action management unit application for the Environmental Restoration Disposal Facility

International Nuclear Information System (INIS)

Evans, G.C.

1994-06-01

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

The disposal of low-level radioactive waste into the sea

International Nuclear Information System (INIS)

Saruhashi, Katsuko

1979-01-01

Disposal of low-level radioactive wastes is made both on land and in sea. Though the land disposal has been already carried out in the U.S.A. and the U.S.S.R., it is impossible in the narrow land of Japan. In the United States, the wastes solidified with cement in drums were previously abandoned in deep seas of the Pacific and the Atlantic. This is no longer done presently; instead, the land disposal is employed due to its lower costs. In European countries, the sea disposal is performed under OECDNEA, trial disposal in 1961 and full-scale disposal since 1967, in the Atlantic. Meanwhile, in Japan, test sea disposal will be carried out in the near future in deep sea of the northern Pacific, the important sea area for fisheries. The international trends of the deep sea disposal of low-level wastes and the correspondent trends of the same in Japan, in the past years are described. (J.P.N.)

US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

International Nuclear Information System (INIS)

Roach, J.A.; Gombert, D.

1996-01-01

The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE's mixed waste problems

ROCTECtm STABILIZATION TREATMENT OF WERF ASH

Energy Technology Data Exchange (ETDEWEB)

Paul A. Lessing; William J. Quapp; Gary Renlund; Bob Clark; Colin Hundley; James Cornwell; Dave Schlier; John Bulko; Gene Pollack

1998-10-01

The objective of this project is to demonstrate a process to stabilize mixed waste flyash generated by the combustion of mixed waste at the Idaho National Engineering & Environmental Laboratory's (INEEL's) Waste Experimental Reduction Facility (WERF) incinerator such that it will meet Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs) Universal Treatment Standards.

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

Energy Technology Data Exchange (ETDEWEB)

Corbus, D.

1992-09-01

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

No-migration variance petition for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Duff, M.; Carnes, R.; Hart, J.; Hansen, R.

1991-01-01

The US Department of Energy (DOE) is petitioning the US Environmental Protection Agency (EPA) to allow the emplacement of hazardous wastes subject to the Resource Conservation and Recovery Act (RCRA) land disposal restrictions in the Waste Isolation Pilot Plant (WIPP). The basis of the petition is that there will be no migration of hazardous constituents from the repository for as long as the wastes remain hazardous. The EPA regulations in 40 CFR Section 268.6 identify specific criteria that must be addressed in making a demonstration of no migration. EPA's approval of this petition will allow the WIPP facility to accept wastes otherwise prohibited or restricted from land disposal. 5 refs

Radioactive waste disposal in W.A

International Nuclear Information System (INIS)

Hartley, B.M.

1983-01-01

Radioactive waste in Western Australia arises primarily from medical diagnosis and treatment and from scientific research mainly with a medical orientation. Waste is classified before disposal depending on its level and type of radioactivity and then disposed of either to municipal land fill sites, to the sewerage system or by incineration. The amounts of radioactive materials which may be disposed of to the sewers and air are set by the Radiation Safety Act (1975) Regulations, and the land fill operations are controlled to ensure isolation of the material. Other waste such as unwanted sources used in industrial applications are stored for future disposal. Discussions are being held between officers of the State and Australian Governments aimed at providing suitable disposal methods for sources of this kind

Readiness assessment plan for the Radioactive Mixed Waste Land Disposal Facility (Trench 31)

International Nuclear Information System (INIS)

Irons, L.G.

1994-01-01

This document provides the Readiness Assessment Plan (RAP) for the Project W-025 (Radioactive Mixed Waste Land Disposal Facility) Readiness Assessment (RA). The RAP documents prerequisites to be met by the operating organization prior to the RA. The RAP is to be implemented by the RA Team identified in the RAP. The RA Team is to verify the facility's compliance with criteria identified in the RAP. The criteria are based upon the open-quotes Core Requirementsclose quotes listed in DOE Order 5480.31, open-quotes Startup and Restart of Nuclear Facilitiesclose quotes

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

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

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

Science.gov (United States)

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

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

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

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

Field study to assess the feasibility of disposing of diesel invert-based cuttings residues using land application

International Nuclear Information System (INIS)

Ashworth, J.

1990-08-01

The use of diesel oil-based invert drilling muds in oil and gas well drilling has become widespread in Alberta. The safe disposal of the residue (DIMR) has become an issue of concern to environmentalists and energy producers. A study was conducted on land treatment as a disposal option in which DIMR was rototilled into the surface soil of small plots in June 1986 and various soil amendments were employed before seeding with a mixture of grasses. Due to the CaCl 2 component of the DIMR used, all treated plots were too saline for effective revegetation in the season of application. However, the salts were mostly leached away in 1986 and 1987, and oil degradation was rapid on fertilized plots, especially those given a surface mulch of manure. Plots which were fertilized and cultivated required an extra season for complete revegetation when treated with 300 or 450 m 3 /hectare of DIMR. Fertilization alone was not successful for revegetation. Unfertilized plots showed some oil degradation but little or no growth. Polyaromatic hydrocarbons (PAH) in the DIMR had half-lives of only a few months in soil; all hydrocarbons were retained near the surface and there was very little leaching. Only background concentrations of PAH were found in healthy plants on plots successfully revegetated. Results from the test site indicate that land treatment is a practical and environmentally acceptable disposal option for DIMR, provided that rates of application are not excessive and the level of site management needed for successful revegetation and safe degradation of hydrocarbons can be sustained for several seasons. Desirable soil properties for DIMR land treatment include adequate permeability, organic content, and microbiological activity. 18 refs., 12 figs., 5 tabs

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

No-migration variance petition for the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

Carnes, R.G.; Hart, J.S. (Benchmark Environmental Corp., Albuquerque, NM (USA)); Knudtsen, K. (International Technology Corp., Albuquerque, NM (USA))

1990-01-01

The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) project to provide a research and development facility to demonstrate the safe disposal of radioactive waste resulting from US defense activities and programs. The DOE is developing the WIPP facility as a deep geologic repository in bedded salt for transuranic (TRU) waste currently stored at or generated by DOE defense installations. Approximately 60 percent of the wastes proposed to be emplaced in the WIPP are radioactive mixed wastes. Because such mixed wastes contain a hazardous chemical component, the WIPP is subject to requirements of the Resource Conservation and Recovery Act (RCRA). In 1984 Congress amended the RCRA with passage of the Hazardous and Solid Waste Amendments (HSWA), which established a stringent regulatory program to prohibit the land disposal of hazardous waste unless (1) the waste is treated to meet treatment standards or other requirements established by the Environmental Protection Agency (EPA) under {section}3004(n), or (2) the EPA determines that compliance with the land disposal restrictions is not required in order to protect human health and the environment. The DOE WIPP Project Office has prepared and submitted to the EPA a no-migration variance petition for the WIPP facility. The purpose of the petition is to demonstrate, according to the requirements of RCRA {section}3004(d) and 40 CFR {section}268.6, that to a reasonable degree of certainty, there will be no migration of hazardous constituents from the WIPP facility for as long as the wastes remain hazardous. This paper provides an overview of the petition and describes the EPA review process, including key issues that have emerged during the review. 5 refs.

No-migration variance petition for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Carnes, R.G.; Hart, J.S.; Knudtsen, K.

1990-01-01

The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) project to provide a research and development facility to demonstrate the safe disposal of radioactive waste resulting from US defense activities and programs. The DOE is developing the WIPP facility as a deep geologic repository in bedded salt for transuranic (TRU) waste currently stored at or generated by DOE defense installations. Approximately 60 percent of the wastes proposed to be emplaced in the WIPP are radioactive mixed wastes. Because such mixed wastes contain a hazardous chemical component, the WIPP is subject to requirements of the Resource Conservation and Recovery Act (RCRA). In 1984 Congress amended the RCRA with passage of the Hazardous and Solid Waste Amendments (HSWA), which established a stringent regulatory program to prohibit the land disposal of hazardous waste unless (1) the waste is treated to meet treatment standards or other requirements established by the Environmental Protection Agency (EPA) under section 3004(n), or (2) the EPA determines that compliance with the land disposal restrictions is not required in order to protect human health and the environment. The DOE WIPP Project Office has prepared and submitted to the EPA a no-migration variance petition for the WIPP facility. The purpose of the petition is to demonstrate, according to the requirements of RCRA section 3004(d) and 40 CFR section 268.6, that to a reasonable degree of certainty, there will be no migration of hazardous constituents from the WIPP facility for as long as the wastes remain hazardous. This paper provides an overview of the petition and describes the EPA review process, including key issues that have emerged during the review. 5 refs

Economic impacts of 10 CFR part 61 on the land disposal of low-level radioactive waste (LLRW)

International Nuclear Information System (INIS)

Gaynor, R.K.

1984-01-01

The new regulations for land disposal of radioactive waste, 10 CFR Part 61, as promulgated by the United States Nuclear Regulatory Commission (NRC) are effective as of December 27, 1983. These new rules have required modifications to the previous practices in commercial burial of LLRW which increased the costs associated with disposal. This paper addresses the requirements of the new regulations, and describes the efforts of one burial site operator to minimize the economic impact of the regulations. Each of the requirements addressed has economic impacts relative to increased paperwork and documentation, increased inspection time, increased labor and equipment costs, increased site construction requirements and decreased disposal efficiency. Discussed in the paper are the relative cost impacts, and the actions and the degree of success of US Ecology, Inc., to minimize cost increases through license negotiations, computerized record keeping and reporting, computerized class verification, and site management and operating procedures

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)

Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

International Nuclear Information System (INIS)

Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

1993-01-01

The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

Long-Term Performance of Transuranic Waste Inadvertently Disposed in a Shallow Land Burial Trench at the Nevada Test Site

International Nuclear Information System (INIS)

Shott, Gregory J.; Yucel, Vefa

2009-01-01

In 1986, 21 m3 of transuranic (TRU) waste was inadvertently disposed in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site. U.S. Department of Energy (DOE) TRU waste must be disposed in accordance with Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes. The Waste Isolation Pilot Plant is the only facility meeting these requirements. The National Research Council, however, has found that exhumation of buried TRU waste for disposal in a deep geologic repository may not be warranted when the effort, exposures, and expense of retrieval are not commensurate with the risk reduction achieved. The long-term risks of leaving the TRU waste in-place are evaluated in two probabilistic performance assessments. A composite analysis, assessing the dose from all disposed waste and interacting sources of residual contamination, estimates an annual total effective dose equivalent (TEDE) of 0.01 mSv, or 3 percent of the dose constraint. A 40 CFR 191 performance assessment also indicates there is reasonable assurance of meeting all requirements. The 40 CFR 191.15 annual mean TEDE for a member of the public is estimated to reach a maximum of 0.055 mSv at 10,000 years, or approximately 37 percent of the 0.15 mSv individual protection requirement. In both assessments greater than 99 percent of the dose is from co-disposed low-level waste. The simulated probability of the 40 CFR 191.13 cumulative release exceeding 1 and 10 times the release limit is estimated to be 0.0093 and less than 0.0001, respectively. Site characterization data and hydrologic process modeling support a conclusion of no groundwater pathway within 10,000 years. Monte Carlo uncertainty analysis indicates that there is reasonable assurance of meeting all regulatory requirements. Sensitivity analysis indicates that the results

Hazardous waste landfill research

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.

1983-05-01

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

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

1998 report on Hanford Site land disposal restrictions for mixed waste

International Nuclear Information System (INIS)

Black, D.G.

1998-01-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility 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 mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities

1998 report on Hanford Site land disposal restrictions for mixed waste

Energy Technology Data Exchange (ETDEWEB)

Black, D.G.

1998-04-10

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility 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 mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities

Reference values on safety regulation of land disposal of low level radioactive solid waste (the second interim report) and its incorporation into legal regulations

International Nuclear Information System (INIS)

Aoki, Terumi

1994-01-01

Safety regulation of land disposal of low level radioactive solid waste in Japan is based on 'the basic philosophy on the safety regulation of land disposal of low level radioactive solid waste' determined by the Nuclear safety Committee (October 1985). The basic philosophy on the upper limit of radioactivity of disposed wastes was published as the reference values in the interim report (February 1987) and in the second interim report (June 1992). In the second interim report, the upper limits of radioactivity are established for three types of solid radioactive wastes: 1) metals, incombustible or flame resistant wastes generated nuclear reactor facilities and solidified in vessels, 2) large metallic structures generated from decommissioning of reactor facilities and difficult to solidify in vessels, and 3) radioactive concrete waste generated from decommissioning of reactor facilities. The upper limits of radioactivity are presented for C-14, Co-60, Ni-63, Sr-90, Cs-137, alfa-emmitters, Ca-41 (for concrete) and Eu-152 (for concrete). Related laws and regulations in Japan on safe disposal of low level wastes are explained. (T.H.)

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

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

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...

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

International Nuclear Information System (INIS)

Morris, M.I.

2001-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Morris, M.I.

2001-01-11

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

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.

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

International Nuclear Information System (INIS)

Connolly, M.J.; Sayer, D.L.

1993-11-01

EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

Hazardous-materials waste disposal: Land, January 1988-July 1991 (Citations from the NTIS Data Base). Rept. for Jan 88-Jul 91

International Nuclear Information System (INIS)

1991-06-01

The bibliography contains citations concerning the disposal of hazardous industrial and municipal wastes, chemical agents, and a variety of other dangerous substances into and from the land. Topics include restoration operations, contamination abatement studies, appropriate regulation and legislation, and remedial response strategies. Considerable attention is given to waste disposal sites at military installations and to incineration operations. Citations pertaining specifically to radioactive waste disposal, state by state toxic release inventories, Best Demonstrated Available Technology as defined by Environmental Protection Agency, Health Assessments for individual companies sponsored by the Toxic Substances and Disease Registry, Atlanta, GA., and the Superfund Record of Decisions are excluded. (The bibliography contains 153 citations with a subject index.)

Development of computer model for radionuclide released from shallow-land disposal facility

International Nuclear Information System (INIS)

Suganda, D.; Sucipta; Sastrowardoyo, P.B.; Eriendi

1998-01-01

Development of 1-dimensional computer model for radionuclide release from shallow land disposal facility (SLDF) has been done. This computer model is used for the SLDF facility at PPTA Serpong. The SLDF facility is above 1.8 metres from groundwater and 150 metres from Cisalak river. Numerical method by implicit method of finite difference solution is chosen to predict the migration of radionuclide with any concentration.The migration starts vertically from the bottom of SLDF until the groundwater layer, then horizontally in the groundwater until the critical population group. Radionuclide Cs-137 is chosen as a sample to know its migration. The result of the assessment shows that the SLDF facility at PPTA Serpong has the high safety criteria. (author)

Vegetation and moisture performance on a Resource Conservation and Recovery Act-equivalent landfill cap at the Hanford site

International Nuclear Information System (INIS)

Kemp, C.J.; Sackschewsky, M.R.

1997-03-01

Landfills, as defined under the Resource Conservation and Recovery Act of 1976 (RCRA) can receive waste materials from commercial and industrial operations, residences, and other sources. Sanitary landfills that are used to dispose of solid waste require a landfill cover that meets RCRA requirements to prevent leaching of water through buried wastes and to isolate the waste for a period of 30 years. The purpose of a RCRA landfill cover is to 'protect public health, to prevent land, air, and water pollution, and conserve the state's natural, economic, and energy resources' (Washington Administrative Code [WAC] 173-304). The hypothesis of this study were as follows: (1) amending soil nitrogen would enhance perennial grass biomass; (2) the amount of biomass produced by commercially-available wheatgrass species would be similar to bluebunch wheatgrass; and (3) the vegetative biomass, as required by WAC-173-304, would not be produced in a semiarid climate

Rocky Flats Solar Evaporation Ponds RCRA hybrid-closure case study

International Nuclear Information System (INIS)

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

1994-01-01

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

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

Land application for disposal of excess water: an overview

International Nuclear Information System (INIS)

Riley, G.H.

1992-01-01

Water management is an important factor in the operation of uranium mines in the Alligator Rivers Region, located in the Wet-Dry tropics. For many project designs, especially open cut operations, sole reliance on evaporative disposal of waste water is ill-advised in years where the Wet season is above average. Instead, spray irrigation, or the application of excess water to suitable areas of land, has been practised at both Nabarlek and Ranger. The method depends on water losses by evaporation from spray droplets, from vegetation surfaces and from the ground surface; residual water is carried to the groundwater system by percolation. The solutes are largely transferred to the soils where heavy metals and metallic radionuclides attach to particles in the soil profile with varying efficiency depending on soil type. Major solutes that can occur in waste water from uranium mines are less successfully immobilised in soil. Sulphate is essentially conservative and not bound within the soil profile; ammonia is affected by soil reactions leading to its decomposition. The retrospective viewpoint of history indicates the application of a technology inadequately researched for local conditions. The consequences at Nabarlek have been the death of trees on one application area and the creation of contaminated groundwater which has moved into the biosphere down gradient and affected the ecology of a local stream. At Ranger, the outcome of land application has been less severe in the short term but the effective adsorption of radionuclides in surface soils has lead to dose estimates which will necessitate restrictions on future public access unless extensive rehabilitation is carried out. 2 refs., 1 tab

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

Radiological protection criteria risk assessments for waste disposal options

International Nuclear Information System (INIS)

Hill, M.D.

1982-01-01

Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

Hydrogeologic factors in the selection of shallow land burial sites for the disposal of low-level radioactive waste

Science.gov (United States)

Fischer, John N.

1986-01-01

In the United States, low-level radioactive waste is disposed of by shallow land burial. Commercial low-level radioactive waste has been buried at six sites, and low-level radioactive waste generated by the Federal Government has been buried at nine major and several minor sites. Several existing low-level radioactive waste sites have not provided expected protection of the environment. These shortcomings are related, at least in part, to an inadequate understanding of site hydrogeology at the time the sites were selected. To better understand the natural systems and the effect of hydrogeologic factors on long-term site performance, the U.S. Geological Survey has conducted investigations at five of the six commercial low-level radioactive waste sites and at three Federal sites. These studies, combined with those of other Federal and State agencies, have identified and confirmed important hydrogeologic factors in the effective disposal of low-level radioactive waste by shallow land burial. These factors include precipitation, surface drainage, topography, site stability, geology, thickness of the host soil-rock horizon, soil and sediment permeability, soil and water chemistry, and depth to the water table.

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

Energy Technology Data Exchange (ETDEWEB)

J. L. Smith

2001-08-01

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

Alternatives for definse waste-salt disposal

International Nuclear Information System (INIS)

Benjamin, R.W.; McDonell, W.R.

1983-01-01

Alternatives for disposal of decontaminated high-level waste salt at Savannah River were reviewed to estimate costs and potential environmental impact for several processes. In this review, the reference process utilizing intermediate-depth burial of salt-concrete (saltcrete) monoliths was compared with alternatives including land application of the decontaminated salt as fertilizer for SRP pine stands, ocean disposal with and without containment, and terminal storage as saltcake in existing SRP waste tanks. Discounted total costs for the reference process and its modifications were in the same range as those for most of the alternative processes; uncontained ocean disposal with truck transport to Savannah River barges and storage as saltcake in SRP tanks had lower costs, but presented other difficulties. Environmental impacts could generally be maintained within acceptable limits for all processes except retention of saltcake in waste tanks, which could result in chemical contamination of surrounding areas on tank collapse. Land application would require additional salt decontamination to meet radioactive waste disposal standards, and ocean disposal without containment is not permitted in existing US practice. The reference process was judged to be the only salt disposal option studied which would meet all current requirements at an acceptable cost

Hazardous constituent source term. Revision 2

International Nuclear Information System (INIS)

1994-01-01

The Department of Energy (DOE) has several facilities that either generate and/or store transuranic (TRU)-waste from weapons program research and production. Much of this waste also contains hazardous waste constituents as regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA). Toxicity characteristic metals in the waste principally include lead, occurring in leaded rubber gloves and shielding. Other RCRA metals may occur as contaminants in pyrochemical salt, soil, debris, and sludge and solidified liquids, as well as in equipment resulting from decontamination and decommissioning activities. Volatile organic compounds (VOCS) contaminate many waste forms as a residue adsorbed on surfaces or occur in sludge and solidified liquids. Due to the presence of these hazardous constituents, applicable disposal regulations include land disposal restrictions established by Hazardous and Solid Waste Amendments (HSWA). The DOE plans to dispose of TRU-mixed waste from the weapons program in the Waste Isolation Pilot Plant (WIPP) by demonstrating no-migration of hazardous constituents. This paper documents the current technical basis for methodologies proposed to develop a post-closure RCRA hazardous constituent source term. For the purposes of demonstrating no-migration, the hazardous constituent source term is defined as the quantities of hazardous constituents that are available for transport after repository closure. Development of the source term is only one of several activities that will be involved in the no-migration demonstration. The demonstration will also include uncertainty and sensitivity analyses of contaminant transport

Trees as indicators of subterranean migration of tritium at a commercial shallow land radioactive waste disposal site

International Nuclear Information System (INIS)

Rickard, W.H.; Kirby, L.J.

1984-09-01

Leaf water and tree sap collected from deciduous trees in a natural forest growing outside the fenced exclusion area of the Maxey Flats Waste Disposal Facility in eastern Kentucky, USA were radiochemically analyzed to detect movement of tritium via subterranean flows of water at depths of three meters. These data indicate that trees can be used to detect the subterranean migration of tritium from shallow land burial sites. 4 references, 5 figures, 1 table

An evaluation on the disposal alternatives for low- and intermediate- level radwaste (II)

International Nuclear Information System (INIS)

Park, Hun Hwee; Han, Kyung Won; Hahn, Pil Soo; Lee, Han Soo; Cho, Won Jin; Lee, Jae Dwan; Park, Chung Kyun; Lee, Myung Joo; Choi, Heui Joo; Lee, Youn Myoung

1988-02-01

An evaluation on the radioactive waste disposal alternatives for the low-and intermediate level wastes being produced from nuclear power generation and radioisotope application was carried out in view of the radiological safety, socio-political aspects and repository construction economics. Three types of possible alternatives-sample shallow land disposal method, engineered shallow land disposal method and engineered rock cavern disposal method are investigated. The safety assessment consists of radiological dose calculation and nonradiological impacts which is expressed as total number of injuries and fatalities during construction, operation and transportation. The sociopolitical assessment is done in terms of site conditions including easiness for land acquisition, technical feasibility and public acceptance. The economic assessment is performed by cost comparison regarding land acquisition, construction, operation and closure for each alternatives. The evaluation shows that engineered rock cavern disposal method has remarkable favour in safety than others. And also an integrated evaluation using AHP results the engineered rock cavern disposal method as the most favorable option

Tritium waste disposal technology in the US

International Nuclear Information System (INIS)

Albenesius, E.L.; Towler, O.A.

1983-01-01

Tritium waste disposal methods in the US range from disposal of low specific activity waste along with other low-level waste in shallow land burial facilities, to disposal of kilocurie amounts in specially designed triple containers in 65' deep augered holes located in an aird region of the US. Total estimated curies disposed of are 500,000 in commercial burial sites and 10 million curies in defense related sites. At three disposal sites in humid areas, tritium has migrated into the ground water, and at one arid site tritium vapor has been detected emerging from the soil above the disposal area. Leaching tests on tritium containing waste show that tritium in the form of HTO leaches readily from most waste forms, but that leaching rates of tritiated water into polymer impregnated concrete are reduced by as much as a factor of ten. Tests on improved tritium containment are ongoing. Disposal costs for tritium waste are 7 to 10 dollars per cubic foot for shallow land burial of low specific activity tritium waste, and 10 to 20 dollars per cubic foot for disposal of high specific activity waste. The cost of packaging the high specific activity waste is 150 to 300 dollars per cubic foot. 18 references

Survey of microbiological effects in low-level radioactive waste disposed of to land

International Nuclear Information System (INIS)

McGahan, D.J.

1987-01-01

An evaluation of published literature was mounted to determine the current position of research into microbiological effects in low-level radioactive waste disposal sites and to assess the need for further research. It is concluded from the survey that the microbial activity present in domestic landfills also occurs in shallow land burial low-level radioactive waste disposal sites. The microbial activity results in the release of tritium as tritiated methane to the atmosphere and tritiated components to the leachate. Carbon-14 migration is also enhanced. It also accelerates the corrosion of steel and concrete used to contain the wastes. There is little evidence for enhanced migration of radionuclides as a result of their incorporation in bacteria but there is considerable evidence for enhancement resulting from the presence of complexing agents (such as ethylenediamine-tetraacetic acid and tributyl phosphate) in the waste. Research in this field has been observed to be very active in the United States. Its objective is to predict with more certainty the important parameters for future low-level radioactive waste site designs. Quantitative prediction of microbial effects and their magnitude is not easy to deduce from the published literature, and new site designs will differ markedly from those that have been in operation over the last thirty years. (author)

25 CFR 700.727 - Impoundment and disposal of unauthorized livestock.

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false Impoundment and disposal of unauthorized livestock. 700... RELOCATION PROCEDURES New Lands Grazing § 700.727 Impoundment and disposal of unauthorized livestock. Unauthorized livestock within any range unit of the New Lands which are not removed therefrom within the...

25 CFR 168.16 - Impoundment and disposal of unauthorized livestock.

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Impoundment and disposal of unauthorized livestock. 168... REGULATIONS FOR THE HOPI PARTITIONED LANDS AREA § 168.16 Impoundment and disposal of unauthorized livestock. Unauthorized livestock within any range unit of the Hopi Partitioned Lands which are not removed therefrom...

Pathway analysis for alternate low-level waste disposal methods

International Nuclear Information System (INIS)

Rao, R.R.; Kozak, M.W.; McCord, J.T.; Olague, N.E.

1992-01-01

The purpose of this paper is to evaluate a complete set of environmental pathways for disposal options and conditions that the Nuclear Regulatory Commission (NRC) may analyze for a low-level radioactive waste (LLW) license application. The regulations pertaining In the past, shallow-land burial has been used for the disposal of low-level radioactive waste. However, with the advent of the State Compact system of LLW disposal, many alternative technologies may be used. The alternative LLW disposal facilities include below- ground vault, tumulus, above-ground vault, shaft, and mine disposal This paper will form the foundation of an update of the previously developed Sandia National Laboratories (SNL)/NRC LLW performance assessment methodology. Based on the pathway assessment for alternative disposal methods, a determination will be made about whether the current methodology can satisfactorily analyze the pathways and phenomena likely to be important for the full range of potential disposal options. We have attempted to be conservative in keeping pathways in the lists that may usually be of marginal importance. In this way we can build confidence that we have spanned the range of cases likely to be encountered at a real site. Results of the pathway assessment indicate that disposal methods can be categorized in groupings based on their depth of disposal. For the deep disposal options of shaft and mine disposal, the key pathways are identical. The shallow disposal options, such as tumulus, shallow-land, and below-ground vault disposal also may be grouped together from a pathway analysis perspective. Above-ground vault disposal cannot be grouped with any of the other disposal options. The pathway analysis shows a definite trend concerning depth of disposal. The above-ground option has the largest number of significant pathways. As the waste becomes more isolated, the number of significant pathways is reduced. Similar to shallow-land burial, it was found that for all

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

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

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.

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

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

Recycling And Disposal Of Waste

Energy Technology Data Exchange (ETDEWEB)

Choi, Ui So

1987-01-15

This book introduces sewage disposal sludge including properties of sludge and production amount, stabilization of sludge by anaerobic digestion stabilization of sludge by aerobic digestion, stabilization of sludge by chemical method, and dewatering, water process sludge, human waste and waste fluid of septic tank such as disposal of waste fluid and injection into the land, urban waste like definition of urban waste, collection of urban waste, recycling, properties and generation amount, and disposal method and possibility of injection of industrial waste into the ground.

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

International Nuclear Information System (INIS)

Shevenell, L.; Switek, J.

1992-02-01

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

Cost effective disposal of whey

Energy Technology Data Exchange (ETDEWEB)

Zall, R R

1980-01-01

Means of reducing the problem of whey disposal are dealt with, covering inter alia the pre-treatment of cheese milk e.g., by ultrafiltration to lower the whey output, utilization of whey constituents, use of liquid whey for feeding, fermenting whey to produce methane and alcohol, and disposal of whey by irrigation of land or by purification in sewage treatment plants.

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

Regulatory barriers to hazardous waste technology innovation

International Nuclear Information System (INIS)

Kuusinen, T.L.; Siegel, M.R.

1991-02-01

The primary federal regulatory programs that influence the development of new technology for hazardous waste are the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA, also commonly known as Superfund). Two important aspects of RCRA that can create barriers to hazardous waste technology innovation are technology-based waste pre-treatment standards and a cumbersome permitting program. By choosing a technology-based approach to the RCRA land disposal restrictions program, the US Environmental Protection Agency (EPA) has simultaneously created tremendous demand for the technologies specified in its regulations, while at the same time significantly reduced incentives for technology innovation that might have otherwise existed. Also, the RCRA hazardous waste permitting process can take years and cost hundreds of thousands of dollars. The natural tendency of permit writers to be cautious of unproven (i.e., innovative) technology also can create a barrier to deployment of new technologies. EPA has created several permitting innovations, however, to attempt to mitigate this latter barrier. Understanding the constraints of these permitting innovations can be important to the success of hazardous waste technology development programs. 3 refs

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

Program criteria for subseabed disposal of radioactive waste: research strategies and review processes

International Nuclear Information System (INIS)

1981-09-01

The Subseabed Disposal Program follows the policies and criteria of the National Waste Terminal Storage program for the development of land-based repositories, except where the technical differences between land and ocean geologic disposal make different approaches or criteria necessary. This is the first of a series of documents describing the procedures and criteria for the Subseabed Disposal Program

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.

Effects of land disposal of municipal sewage sludge on soil, streambed sediment, and ground- and surface-water quality at a site near Denver, Colorado

Energy Technology Data Exchange (ETDEWEB)

Gaggiani, N.G.

1991-01-01

The report describes the effects of burial and land application of municipal sewage sludge on soil and streambed sediment and water quality in the underlying aquifers and surface water within and around the Lowry sewage-sludge-disposal area. The existing ground-water observation-well network at the disposal area was expanded for the study. Surface-water-sampling sites were selected so that runoff could be sampled from intense rainstorms or snowmelt. The sampling frequency for ground-water and surface-water runoff was changed from yearly to quarterly, and soil samples were collected. Four years of data were collected from 1984 to 1987 during the expanded monitoring program at the Lowry sewage-sludge-disposal area. These data, in addition to the data collected by the U.S. Geological Survey from 1981 to 1983, were used to determine effects of sewage-sludge-disposal on soil and streambed sediment and surface- and ground-water quality at the disposal area.

Safe Disposal of Pesticides

Science.gov (United States)

... Toxics Environmental Information by Location Greener Living Health Land, Waste, and Cleanup Lead Mold Pesticides Radon Science ... or www.earth911.com . Think before disposing of extra pesticides and containers: Never reuse empty pesticide containers. ...

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

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles (mi)) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and 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 has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 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 NTS (Figure 2), 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. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan

Background studies: climatic and geomorphological aspects of the evolution of shallow land burial sites for radioactive waste disposal

International Nuclear Information System (INIS)

1988-04-01

This report presents the results of a programme of background research into some climatic and geomorphological aspects of the evolution of shallow land disposal environments for radioactive wastes in Britain. The work has supported development of the TIME2 simulation code. Modelling approaches are presented and discussed, along with supporting data, for climatic change, ice sheet growth and decay, groundwater effects and denudation. The potential effects of periglacial processes on a repository are also briefly discussed. (author)

Study of parameters for safety assessment of sub-surface disposal. Tunnel-excavating speed and thickness of additional soil in residential land development by filling

International Nuclear Information System (INIS)

Ishitoya, Kimihide; Sugaya, Toshikatsu; Funabashi, Hideyuki

2012-02-01

Japan Atomic Energy Agency (JAEA) is making preparations for the sub-surface disposal of own low level radioactive wastes. In order to carry out the disposal, it is necessary to confirm the safety of the disposal. Nuclear Safety Commission of Japan (NSC) issued 'Policy of the Safety Assessment of Sub-surface Disposal after the Period for Active Control' (April 1, 2010). Then, we investigated the parameters for dose assessment in tunnel excavation scenario and large-scale land use scenario which were described in the 'Policy of the Safety Assessment', in order to perform the assessment based on actual conditions. To be concrete, we investigated the tunnel excavating speeds in Japan for the former scenario, and investigated technical standards of the filling for the latter scenario. We studied the realistic parameters for the dose assessment with the results of those investigations. (author)

Modularized system for disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Mallory, C.W.; DiSibio, R.

1985-01-01

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

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

International Nuclear Information System (INIS)

1995-08-01

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

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.

Economic aspects related to the shallow land disposal of nuclear waste: The Belgian case

International Nuclear Information System (INIS)

Kunsch, P.L.; Zaccai, H.; Miegroet, J. van

1993-01-01

The Belgian concept for shallow land disposal of low-level short-lived waste is approaching maturity. The paper presents its main design features, the construction and operating phases, and the economics of the project. The conclusion is that this concept is economically interesting when compared to the geological option. The financial approach adopted by Belgium is presented. Pros and cons of timely operation are discussed. Although it may look economically attractive to adopt a slow pace in implementing the concept, the paper shows that deferring decisions would be a risky attitude, in contradiction with fairness to future consumers. Such a conclusion derives from economic and financial arguments, considering that cost uncertainties, especially in the front-end, and financial management risk might be of overwhelming importance

A new procedure for deep sea mining tailings disposal

OpenAIRE

Ma, W.; Schott, D.L.; Lodewijks, G.

2017-01-01

Deep sea mining tailings disposal is a new environmental challenge related to water pollution, mineral crust waste handling, and ocean biology. The objective of this paper is to propose a new tailings disposal procedure for the deep sea mining industry. Through comparisons of the tailings disposal methods which exist in on-land mining and the coastal mining fields, a new tailings disposal procedure, i.e., the submarine–backfill–dam–reuse (SBDR) tailings disposal procedure, is proposed. It com...

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

Draft no-migration variance petition. Volume 1

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is Volume 1 which discusses the regulatory frame work, site characterization, facility description, waste description, environmental impact analysis, monitoring, quality assurance, long-term compliance analysis, and regulatory compliance assessment

Draft no-migration variance petition. Volume 7, Appendices: SUM, SURV, VOC, WAP

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 7 of the petition which presents details about the waste analysis plan for WIPP. VOC screening methodologies; and a summary of the site characterization studies conducted from 1983 through 1987 at WIPP

Draft no-migration variance petition. Volume 6, Appendices: QAPD, REG, RM, SCR, SER

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This is Volume 6 of the petition which presents details about the 1993 site environmental report; metorite impact; damage from rock mechanics; regulatory interpretations; and the quality assurance program

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

International Nuclear Information System (INIS)

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

1997-06-01

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

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

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.

The disposal of orphan wastes using the greater confinement disposal concept

International Nuclear Information System (INIS)

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

1991-01-01

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

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

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

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

Science.gov (United States)

2011-12-06

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

State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site

International Nuclear Information System (INIS)

1993-08-01

Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS

43 CFR 16.1 - Agreements to dispose of helium in natural gas.

Science.gov (United States)

2010-10-01

... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Agreements to dispose of helium in natural gas. 16.1 Section 16.1 Public Lands: Interior Office of the Secretary of the Interior CONSERVATION OF HELIUM § 16.1 Agreements to dispose of helium in natural gas. (a) Pursuant to his authority and...

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

Underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-08-15

Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

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.

Disposal of solid radioactive waste of nuclear power plant

International Nuclear Information System (INIS)

YU Shichen.

1986-01-01

The contaminations of marine enviroment by the disposal of radwastes should not been expected, then ocean disposal has been stoped in some countries, and land disposal of solid radwastes should been a better method for mankind and environment protection. Ground burial near the surface is currently considered to be feasible. Storage in spent pit or in plant area also should been adapted in several countries

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.

Oil ''rig'' disposal

International Nuclear Information System (INIS)

Anon.

1996-01-01

A comparison of the environmental impacts of disposing of the Brent Spar oil platform on land and at sea is presented, with a view to establishing the best decommissioning option in the light of recent controversy. The document is presented as an aid to comprehension of the scientific and engineering issues involved for Members of Parliament. (UK)

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-31

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site.

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site

Disposal options for radioactive waste

International Nuclear Information System (INIS)

Olivier, J.P.

1991-01-01

On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

Limited risk assessment and some cost/benefit considerations for greater confinement disposal compared to shallow land burial

International Nuclear Information System (INIS)

Hunter, P.H.; Lester, D.H.; Robertson, L.D.; Spaeth, M.E.; Stoddard, J.A.; Dickman, P.T.

1984-09-01

A limited risk assessment and some cost/benefit considerations of greater confinement disposal (GCD) compared to shallow land burial (SLB) are presented. This study is limited to an analysis of the postclosure phase of hypothetical GCD and SLB facilities. Selected release scenarios are used which bound the range of risks to a maximally exposed individual and a hypothetical population. Based on the scenario assessments, GCD had a significant risk advantage over SLB for normal exposure pathways at both humid and arid sites, particularly for the human intrusion scenario. Since GCD costs are somewhat higher than SLB, it is necessary to weigh the higher costs of GCD against the higher risks of SLB. In this regard, GCD should be pursued as an alternative to SLB for certain types of low-level waste, and as an alternative to processing for wastes requiring improved stabilization or higher integrity packaging to be compatible with SLB. There are two reasons for this conclusion. First, GCD might diminish public apprehension regarding the disposal of wastes perceived to be too hazardous for SLB. Second, GCD may be a relatively cost-effective alternative to various stabilization and packaging schemes required to meet 10 CFR 61 near-surface requirements as well as being a cost-effective alternative to deep geologic disposal. Radionuclide transport through the biosphere and resultant dose consequences were determined using the RADTRAN radionuclide transport code. 19 references, 4 figures, 5 tables

Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste

International Nuclear Information System (INIS)

1982-11-01

The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

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

International Nuclear Information System (INIS)

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

1994-01-01

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

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.

Analysis of scenarios for the direct disposal of spent nuclear fuel disposal conditions as expected in Germany

International Nuclear Information System (INIS)

Ashton, P.; Mehling, O.; Mohn, R.; Wingender, H.J.

1990-01-01

This report contains an investigation of aspects of the waste management of spent light water reactor fuel by direct disposal in a deep geological formation on land. The areas covered are: interim dry storage of spent fuel with three options of pre-conditioning; conditioning of spent fuel for final disposal in a salt dome repository; disposal of spent fuel (heat-generating waste) in a salt dome repository; disposal of medium and low-level radioactive wastes in the Konrad mine. Dose commitments, effluent discharges and potential incidents were not found to vary significantly for the various conditioning options/salt dome repository types. Due to uncertainty in the cost estimates, in particular the disposal cost estimates, the variation between the three conditioning options examined is not considered as being significant. The specific total costs for the direct disposal strategy are estimated to lie in the range ECU 600 to 700 per kg hm (basis 1988)

CY2000 Hanford Site Mixed Waste Land Disposal Restrictions Report Vol. 1 Storage Report and Vol 2: Characterization and Treatment Report [SEC 1 thru SEC 4

International Nuclear Information System (INIS)

MCDONALD, K.M.

2001-01-01

This volume presents information about the storage and minimization of mixed waste and potential sources for the generation of additional mixed waste. This information is presented in accordance with Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1996) Milestone M-26-01K. It is Volume 1 of a two-volume report on the status of Hanford Site land-disposal-restricted mixed waste, other mixed waste, and other waste that the parties have agreed to include in this report. This volume also contains the approval page for both volumes and assumptions, accomplishments, and some other information that also pertains to waste characterization and treatment, which are addressed in Volume 2. Appendix A lists the land disposal restriction (LDR) reporting requirements and explains where they are addressed in this report. The reporting period for this document is from January 1, 2000, to December 31, 2000

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

Seabed disposal of high-level nuclear wastes: an alternative viewpoint

International Nuclear Information System (INIS)

Glasby, G.P.

1985-01-01

Various comments on a published article on subseabed disposal of nuclear wastes are presented. These include the scale of the proposed operation, the technical problems of canister retrievability, the feasibility of the free-fall penetrometer disposal method, canister lifetime, the possible contravention of the 1972 London Dumping Convention and land-based geological repositories as an alternative method of disposal. (author)

Rokkasho low-level radioactive waste disposal in Japan

International Nuclear Information System (INIS)

Takahashi, Y.

1994-01-01

Japan Nuclear Fuel Limited commenced the operation of the shallow land disposal of low-level radioactive waste from reactor operation, in 1992 at Rokkasho site in Aomori Prefecture. JNFL is private company whose main activities within the responsibility of JNFL are: 1) Disposal of low-level radioactive waste, 2) Uranium enrichment, 3) Reprocessing of spent nuclear fuels, 4) Temporary storage of returned wastes from COGEMA and BNFL by reprocessing contracts, prior to disposal. JNFL selected the site for the disposal of LLW at Rokkasho in Aomori Prefecture, then bought land of 3.4 million m 2 . Among waste spectrum, LLWs from nuclear power plants, from uranium enrichment and from reprocessing are to be managed by JNFL, including dismantling of these facilities, and JNFL has plan to dispose about 600 thousand m 3 of wastes ultimately. On the middle of November 1990 JNFL got the permission of the application for 40 thousand m 3 (equivalent to 200,000 drums each with a 200-liter capacity) of reactor operating wastes which is solidified with cement, bitumen or plastics as a first stage. And after the construction work for about 2 years, the operations started at Dec. 8th, 1992. The Disposal center has already accepted about 24,000 LLW drums as of the end of February, 1994. (author)

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

International Nuclear Information System (INIS)

Evans, S.K.

2002-01-01

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

Greater-confinement disposal

International Nuclear Information System (INIS)

Trevorrow, L.E.; Schubert, J.P.

1989-01-01

Greater-confinement disposal (GCD) is a general term for low-level waste (LLW) disposal technologies that employ natural and/or engineered barriers and provide a degree of confinement greater than that of shallow-land burial (SLB) but possibly less than that of a geologic repository. Thus GCD is associated with lower risk/hazard ratios than SLB. Although any number of disposal technologies might satisfy the definition of GCD, eight have been selected for consideration in this discussion. These technologies include: (1) earth-covered tumuli, (2) concrete structures, both above and below grade, (3) deep trenches, (4) augered shafts, (5) rock cavities, (6) abandoned mines, (7) high-integrity containers, and (8) hydrofracture. Each of these technologies employ several operations that are mature,however, some are at more advanced stages of development and demonstration than others. Each is defined and further described by information on design, advantages and disadvantages, special equipment requirements, and characteristic operations such as construction, waste emplacement, and closure

Processing and waste disposal needs for fusion breeder blankets system

International Nuclear Information System (INIS)

Finn, P.A.; Vogler, S.

1988-01-01

We evaluated the waste disposal and recycling requirements for two types of fusion breeder blanket (solid and liquid). The goal was to determine if breeder blanket waste can be disposed of in shallow land burial, the least restrictive method under U.S. Nuclear Regulatory Commission regulations. Described in this paper are the radionuclides expected in fusion blanket materials, plans for reprocessing and disposal of blanket components, and estimates for the operating costs involved in waste disposal. (orig.)

An Exploration of Mercury Soils Treatment Technologies for the Y-12 Plant - 13217

International Nuclear Information System (INIS)

Wrapp, John; Julius, Jonathon; Browning, Debbie; Kane, Michael; Whaley, Katherine; Estes, Chuck; Witzeman, John

2013-01-01

There are a number of areas at the Y-12 National Security Complex (Y-12) that have been contaminated with mercury due to historical mercury use and storage. Remediation of these areas is expected to generate large volumes of waste that are Resource Conservation and Recovery Act (RCRA) characteristically hazardous. These soils will require treatment to meet RCRA Land Disposal Restrictions (LDR) prior to disposal. URS - CH2M Oak Ridge LLC (UCOR) performed a feasibility assessment to evaluate on-site and off-site options for the treatment and disposal of mercury-contaminated soil from the Y-12 Site. The focus of the feasibility assessment was on treatment for disposal at the Environmental Management Waste Management Facility (EMWMF) located on the Oak Ridge Reservation. A two-phase approach was used in the evaluation process of treatment technologies. Phase 1 involved the selection of three vendors to perform treatability studies using their stabilization treatment technology on actual Y-12 soil. Phase II involved a team of waste management specialists performing an in-depth literature review of all available treatment technologies for treating mercury contaminated soil using the following evaluation criteria: effectiveness, feasibility of implementation, and cost. The result of the treatability study and the literature review revealed several viable on-site and off-site treatment options. This paper presents the methodology used by the team in the evaluation of technologies especially as related to EMWMF waste acceptance criteria, the results of the physical treatability studies, and a regulatory analysis for obtaining regulator approval for the treatment/disposal at the EMWMF. (authors)

An Exploration of Mercury Soils Treatment Technologies for the Y-12 Plant - 13217

Energy Technology Data Exchange (ETDEWEB)

Wrapp, John [UCOR, P.O. Box 4699, Oak Ridge, TN 37831 (United States); Julius, Jonathon [DOE Oak Ridge (United States); Browning, Debbie [Strata-G, LLC, 2027 Castaic Lane, Knoxville, TN, 37932 (United States); Kane, Michael [RSI, P.O. Box 4699, Oak Ridge, TN 37831 (United States); Whaley, Katherine [RSI, P.O. Box 4699, Oak Ridge, TN 37831 (United States); Estes, Chuck [EnergySolutions, P.O. Box 4699, Oak Ridge, TN 37831 (United States); Witzeman, John [RSI, P.O. Box 4699, Oak Ridge, TN, 37831 (United States)

2013-07-01

There are a number of areas at the Y-12 National Security Complex (Y-12) that have been contaminated with mercury due to historical mercury use and storage. Remediation of these areas is expected to generate large volumes of waste that are Resource Conservation and Recovery Act (RCRA) characteristically hazardous. These soils will require treatment to meet RCRA Land Disposal Restrictions (LDR) prior to disposal. URS - CH2M Oak Ridge LLC (UCOR) performed a feasibility assessment to evaluate on-site and off-site options for the treatment and disposal of mercury-contaminated soil from the Y-12 Site. The focus of the feasibility assessment was on treatment for disposal at the Environmental Management Waste Management Facility (EMWMF) located on the Oak Ridge Reservation. A two-phase approach was used in the evaluation process of treatment technologies. Phase 1 involved the selection of three vendors to perform treatability studies using their stabilization treatment technology on actual Y-12 soil. Phase II involved a team of waste management specialists performing an in-depth literature review of all available treatment technologies for treating mercury contaminated soil using the following evaluation criteria: effectiveness, feasibility of implementation, and cost. The result of the treatability study and the literature review revealed several viable on-site and off-site treatment options. This paper presents the methodology used by the team in the evaluation of technologies especially as related to EMWMF waste acceptance criteria, the results of the physical treatability studies, and a regulatory analysis for obtaining regulator approval for the treatment/disposal at the EMWMF. (authors)

Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

1982-08-01

An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables

76 FR 18244 - Public Land Order No. 7760; Extension of Public Land Order No. 6839; Alaska

Science.gov (United States)

2011-04-01

... (1991)), which modified Public Land Order No. 2344 (26 FR 3701 (1961)), transferred jurisdiction of... land laws, including the mining and mineral leasing laws, but not disposal of materials under the Act...

Safety assessment for radwaste disposal in Korea: Pt. 1

International Nuclear Information System (INIS)

Suh, I.S.; Park, H.H.; Han, K.W.; Hahn, P.S.

1986-01-01

A simplified safety analysis code has been established in order to provide a basic methodology for the preliminary selection of a disposal method. The disposal type selection is prerequisite to meet the requirements of low and intermediate level radwaste management program in Korea. The code covers resaturation and leaching, migration through fracture-porous media transport such that the rock cavern disposal option can be evaluated compared with that of shallow land burial

Microbial activity of trench leachates from shallow-land, low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Francis, A.J.; Dobbs, S.; Nine, B.J.

1980-01-01

Trench leachate samples collected anoxically from shallow-land, low-level radioactive waste disposal sites were analyzed for total aerobic and anaerobic populations, sulfate reducers, denitrifiers, and methanogens. Among the several aerobic and anaerobic bacteria isolated, only Bacillus sp., Pseudomonas sp., Citrobacter sp., and Clostridium sp. were identified. Mixed bacterial cultures isolated from the trench leachates were able to grow anaerobically in trench leachates, which indicates that the radionuclides and organic chemicals present were not toxic to these bacteria. Changes in concentrations of several of the organic constituents of the waste leachate samples were observed due to anaerobic microbial activity. Growth of a mixed culture of trench-water bacteria in media containing a mixture of radionuclides, 60 Co, 85 Sr, and 134 137 Cs, was not affected at total activity concentrations of 2.6 x 10 2 and 2.7 x 10 3 pCi/ml

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

International Nuclear Information System (INIS)

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

1996-01-01

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

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...

Disposal alternatives and recommendations for waste salt management for repository excavation in the Palo Duro Basin, Texas

International Nuclear Information System (INIS)

1987-01-01

This report documents an evaluation of five alternatives for the disposal of waste salt that would be generated by the construction of a repository for radioactive waste in underground salt deposits at either of two sites in the Palo Duro Basin, Texas. The alternatives include commercial disposal, offsite deep-well injection, disposal in abandoned mines, ocean disposal, and land surface disposal on or off the site. For each alternative a reference case was rated - positive, neutral, or negative - in terms of environmental and dependability factors developed specifically for Texas sites. The factors constituting the environmental checklist relate to water quality impact, water- and land-use conflicts, ecological compatibility, conformity with air quality standards, and aesthetic impact. Factors on the dependability check-list relate to public acceptance, the adequacy of site characterization, permit and licensing requirements, technological requirements, and operational availability. A comparison of the ratings yielded the following viable alternatives, in order of preference: (1) land surface disposal, specifically disposal on tailings piles associated with abandoned potash mines; (2) disposal in abandoned mines, specifically potash mines; and (3) commercial disposal. Approaches to the further study of these three salt management techniques are recommended

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

Making waves with undersea (radioactive waste) disposal

International Nuclear Information System (INIS)

Milne, Roger.

1987-01-01

Following the Government's decision to halt the search for land-based disposal sites for low-level radioactive wastes, the search for alternative means of disposal of low- and intermediate-level wastes continues. Off-shore sites now seems to be the most likely. Two approaches are mentioned. The first is that proposed by Consolidated Environmental Technologies Ltd., to sink a shaft 15 metre in diameter under the seabed in an area of tectonic stability, possibly off Lincolnshire. The shaft could be 3000 metres deep. Waste packages and large decommissioning items would be lowered in from a giant barge. This would be expensive but environmentally more acceptable than the other approach. That is to tunnel out from the land and store the waste offshore, below the seabed. (U.K.)

Shallow land burial handbook

International Nuclear Information System (INIS)

Stinton, L.H.

1983-01-01

The facility development phases (preliminary analysis, site selection, facility design and construction, facility operation, and facility closure/post-closure) are systematically integrated into a logical plan for developing near surface disposal plans. The Shallow Land Burial Handbook provides initial guidance and concepts for understanding the magnitude and the complexity of developing new low-level radioactive waste disposal facilities

Preparing sewage sludge for land application or surface disposal: A guide for preparers of sewage sludge on the monitoring, record keeping, and reporting requirements of the federal standards for the use of disposal of sewage sludge, 40 CFR part 503

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The document focuses on the monitoring, recordkeeping, and reporting requirements that apply to persons who prepare sewage sludge or a material derived from sewage sludge. It defines persons who prepare sewage sludge and then summarizes their general responsibilities. USEPA promulgated at 40 CFR Part 503 Phase 1 of the risk-based regulations that govern the final use or disposal of sewage sludge. The intent of the Federal program is to ensure that the use or disposal of sewage sludge occurs in a way that protects both human health and the environment. The Part 503 regulation establishes general requirements, pollutant limits, operational standards, and management practices, as well as monitoring, recordkeeping, and reporting requirements. These requirements apply to sewage sludge that is land applied, placed on a surface disposal site, or incinerated in a sewage sludge-only incinerator.

Economics of low-level radioactive waste disposal

International Nuclear Information System (INIS)

Schafer, J.; Jennrich, E.

1983-01-01

Regardless of who develops new low-level radioactive waste disposal sites or when, economics will play a role. To assist in this area the Department of Energy's Low-Level Radioactive Waste Management Program has developed a computer program, LLWECON, and data base for projecting disposal site costs. This program and its non-site specific data base can currently be used to compare the costs associated with various disposal site development, financing, and operating scenarios. As site specific costs and requirements are refined LLWECON will be able to calculate exact life cycle costs for each facility. While designed around shallow land burial, as practiced today, LLWECON is flexible and the input parameters discrete enough to be applicable to other disposal options. What the program can do is illustrated

Determining the future for irradiated graphite disposal

International Nuclear Information System (INIS)

Neighbour, G.B.; Wickham, A.J.; Hacker, P.J.

2000-01-01

In recent years, proposals have been made for the long-term treatment of radioactive graphite waste which have ranged from sea dumping through incineration to land-based disposal, sometimes preceded by a variable period of 'safe storage' within the original reactor containment. Nuclear regulators are challenging the proposed length of 'safe storage' on the basis that essential knowledge may be lost. More recently, political constraints have further complicated the issue by eliminating disposal at sea and imposing a 'near-zero release' philosophy, while public opinion is opposed to land-based disposal and has induced a continual drive towards minimizing radioactivity release to the environment from disposal. This paper proposes that, despite various international agreements, it is time to review technically all options for disposal of irradiated graphite waste as a framework for the eventual decision-making process. It is recognized that the socio-economic and political pressures are high and therefore, given that all currently identified options satisfy the present safety limits, the need to minimize the objective risk is shown to be a minor need in comparison to the public's want of demonstrable control, responsiveness and ability to reverse/change the disposal options in the future. Further, it is shown that the eventual decision-making process for a post-dismantling option for graphite waste must optimize the beneficial attributes of subjective risk experienced by the general public. In addition, in advocating and preferred option to the general public, it is recommended that the industry should communicate at a level commensurate with the public understanding and initiate a process of facilitation which enables the public to arrive at their own solution and constituting a social exchange. Otherwise it is concluded that if the indecision over disposal options is allowed to continue then, by default, graphite will remain in long-term supervised storage. (author)

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.

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

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

Selecting reasonable future land use scenarios

Energy Technology Data Exchange (ETDEWEB)

Allred, W.E.; Smith, R.W. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1995-12-31

This paper examines a process to help select the most reasonable future land use scenarios for hazardous waste and/or low-level radioactive waste disposal sites. The process involves evaluating future land use scenarios by applying selected criteria currently used by commercial mortgage companies to determine the feasibility of obtaining a loan for purchasing such land. The basis for the process is that only land use activities for which a loan can be obtained will be considered. To examine the process, a low-level radioactive waste site, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, is used as an example. The authors suggest that the process is a very precise, comprehensive, and systematic (common sense) approach for determining reasonable future use of land. Implementing such a process will help enhance the planning, decisionmaking, safe management, and cleanup of present and future disposal facilities.

Selecting reasonable future land use scenarios

International Nuclear Information System (INIS)

Allred, W.E.; Smith, R.W.

1995-01-01

This paper examines a process to help select the most reasonable future land use scenario for hazardous waste and/or low-level radioactive waste disposal sites. The process involves evaluating future land use scenarios ab applying selected criteria currently used by commercial mortgage companies to determine the feasibility of obtaining a loan for purchasing such land. The basis for the process is that only land use activities for which a loan can be obtained well be considered. To examine the process, a low-level radioactive waste site, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, is used as an example. The authors suggest that the process is a very precise, comprehensive, and systematic approach for determining reasonable future use of land. Implementing such a process will help enhance the planning, decisionmaking, safe management, and cleanup of present and future disposal facilities

Selecting reasonable future land use scenarios

International Nuclear Information System (INIS)

Allred, W.E.; Smith, R.W.

1995-01-01

This paper examines a process to help select the most reasonable future land use scenarios for hazardous waste and/or low-level radioactive waste disposal sites. The process involves evaluating future land use scenarios by applying selected criteria currently used by commercial mortgage companies to determine the feasibility of obtaining a loan for purchasing such land. The basis for the process is that only land use activities for which a loan can be obtained will be considered. To examine the process, a low-level radioactive waste site, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, is used as an example. The authors suggest that the process is a very precise, comprehensive, and systematic (common sense) approach for determining reasonable future use of land. Implementing such a process will help enhance the planning, decisionmaking, safe management, and cleanup of present and future disposal facilities

The AMES Laboratory chemical disposal site removal action: Source removal, processing, and disposal

International Nuclear Information System (INIS)

Shirley, R.S.

1996-01-01

The Ames Laboratory has historically supported the U.S. Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, chemical wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the U.S. Army Corps of Engineers (USACE), OHM Remediation Services Corp (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

The Ames Laboratory Chemical Disposal Site removal action: Source removal, processing, and disposal

International Nuclear Information System (INIS)

Shirley, R.S.

1995-01-01

The Ames Laboratory has historically supported the US Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, mixed wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the US Army Corps of Engineers (USACE), OHM Remediation Services Corp. (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

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

International Nuclear Information System (INIS)

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

1993-06-01

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

Development of the safety assessment technology for the radioactive waste disposal

International Nuclear Information System (INIS)

Kim, Chang Lak; Choi, Kwang Sub; Cho, Chan Hee; Lee, Myung Chan; Kim, Jhin Wung

1992-03-01

The major goal of this project is to develop a source-term model for the safety assessment of a low- and intermediate-level radioactive waste repository as follows: 1) estimation of the arising of low- and intermediate-level radioactive wastes, 2) development of inventory data base, 3) development of a source-term code for shallow-land disposal, and 4) improvement of the REPS source-term code for rock cavern type disposal developed already in 1990 and conservative safety assessment for an imaginary repository. In addition, the source of C-14 in the inventory is assessed by two methods: decontamination factor and scaling factor. The source-term code for shallow-land disposal include the following submodels: surface water penetration into the repository, concrete degradation, corrosion of container drums, leaching of radionuclides from waste forms, and migration of radionuclides from engineered disposal facility is estimated by this code. (Author)

Sewage sludge disposal in Austria

International Nuclear Information System (INIS)

Koch, F.

1997-01-01

Sewage systems serve about 70% of the Austrian population, producing 6 million m 3 of sewage sludge per year with a dry matter content of 4-5%. At present about 52% of this sludge is disposed of in land fills, 33% is incinerated, and only about 15 % is used in agriculture. Although agricultural utilization is becoming increasingly important, several problems, especially those related to public opinion, need to be resolved before increased use will be possible. In this paper, wastewater treatment and sewage-sludge production in Austria, and problems associated with sludge disposal are discussed. (author)

Land Use Management for Solid Waste Programs

Science.gov (United States)

Brown, Sanford M., Jr.

1974-01-01

The author discusses the problems of solid waste disposal and examines various land use management techniques. These include the land use plan, zoning, regionalization, land utilities, and interim use. Information concerning solid waste processing site zoning and analysis is given. Bibliography included. (MA)

Evaluation of alternative methods for the disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Macbeth, P.; Wehmann, G.; Thamer, B.J.; Card, D.H.

1979-07-01

A comparative analysis of the most viable alternatives for disposal of solid low-level radioactive wastes is presented to aid in evaluating national waste management options. Four basic alternative methods are analyzed and compared to the present practice of shallow land burial. These include deeper burial, disposal in mined cavities, disposal in engineered structures, and disposal in the oceans. Some variations in the basic methods are also presented. Technical, socio-political, and economic factors are assigened relative importances (weights) and evaluated for the various alternatives. Based on disposal of a constant volume of waste with given nuclear characteristics, the most desirable alternatives to shallow land burial in descending order of desirability appear to be: improving present practices, deeper burial, use of acceptable abandoned mines, new mines, ocean dumping, and structural disposal concepts. It must be emphasized that the evaluations reported here are generic, and use of other weights or different values for specific sites could change the conclusions and ordering of alternatives determined in this study. Impacts and costs associated with transportation over long distances predominate over differences among alternatives, indicating the desireability of establishing regional waste disposal locations. The impacts presented are for generic comparisons among alternatives, and are not intended to be predictive of the performance of any actual waste disposal facility

The borehole disposal of spent sources (BOSS)

International Nuclear Information System (INIS)

Heard, R.G.

2002-01-01

During the International Atomic Energy Agency (IAEA) Regional Training Course on 'The Management of Low-Level Radioactive Waste from Hospitals and Other Nuclear Applications' hosted by the Atomic Energy Corporation of SA Ltd. (AEC), now NECSA, during July/August 1995, the African delegates reviewed their national radioactive waste programmes. Among the issues raised, which are common to most African countries, were the lack of adequate storage facilities, lack of disposal solutions and a lack of equipment to implement widely used disposal concepts to dispose of their spent sources. As a result of this meeting, a Technical Co-operation (TC) project was launched to look at the technical feasibility and economic viability of such a concept. Phase I and II of the project have been completed and the results can be seen in three reports produced by NECSA. The Safety Assessment methodology used in the evaluation of the concept was that developed during the ISAM programme and detailed in Van Blerk's PhD thesis. This methodology is specifically developed for shallow land repositories, but was used in this case as the borehole need not be more than 100m deep and could fit into the definition of a shallow land disposal system. The studies found that the BOSS concept would be suitable for implementation in African countries as the borehole has a large capacity for sources and it is possible that an entire country's disused sources can be placed in a single borehole. The costs are a lot lower than for a shallow land trench, and the concept was evaluated using radium (226) sources as the most limiting inventory. The conclusion of the initial safety assessment was that the BOSS concept is robust, and provides a viable alternative for the disposal of radium needles. The concept is expected to provide good assurance of safety at real sites. The extension of the safety assessment to other types of spent sources is expected to be relatively straightforward. Disposal of radium needles

Disposal of radioactive waste in the Atlantic

International Nuclear Information System (INIS)

1982-06-01

An operation to dispose of low-level radioactive waste in the North Atlantic deeps is undertaken each year. This leaflet seeks to answer questions which are sometimes asked about the operation. It deals with origin, composition, quantity, reason for sea- rather than land-disposal, packaging, transport (rail, road), route of transport, safety precautions, radiation protection, personnel, contamination, site of dump, international regulations, neutral observers, safety standards of containers and control of level of radioactivity of wastes. (U.K.)

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

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

International Nuclear Information System (INIS)

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

1988-04-01

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

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

Alternative concepts for Low-Level Radioactive Waste Disposal: Conceptual design report

International Nuclear Information System (INIS)

1987-06-01

This conceptual design report is provided by the Department of Energy's Nuclear Energy Low-Level Waste Management Program to assist states and compact regions in developing new low-level radioactive waste (LLW) disposal facilities in accordance with the Low-Level Radioactive Waste Policy Amendment Act of 1985. The report provides conceptual designs and evaluations of six widely considered concepts for LLW disposal. These are shallow land disposal (SLD), intermediate depth disposal (IDD), below-ground vaults (BGV), above-ground vaults (AGV), modular concrete canister disposal (MCCD), earth-mounded concrete bunker (EMCB). 40 refs., 45 figs., 77 tabs

Disposal and reclamation of southwestern coal and uranium wastes

International Nuclear Information System (INIS)

Wewerka, E.M.

1979-01-01

The types of solid wastes and effluents produced by the southwestern coal and uranium mining and milling industries are considered, and the current methods for the disposal and reclamation of these materials discussed. The major means of disposing of the solid wastes from both industries is by land fill or in some instances ponding. Sludges or aqueous wastes are normally discharged into settling and evaporative ponds. Basic reclamation measures for nearly all coal and uranium waste disposal sites include solids stabilization, compacting, grading, soil preparation, and revegetation. Impermeable liners and caps are beginning to be applied to disposal sites for some of the more harmful coal and uranium waste materials

Technical concept for a greater-confinement-disposal test facility

International Nuclear Information System (INIS)

Hunter, P.H.

1982-01-01

Greater confinement disposal (GCO) has been defined by the National Low-Level Waste Program as the disposal of low-level waste in such a manner as to provide greater containment of radiation, reduce potential for migration or dispersion or radionuclides, and provide greater protection from inadvertent human and biological intrusions in order to protect the public health and safety. This paper discusses: the need for GCD; definition of GCD; advantages and disadvantages of GCD; relative dose impacts of GCD versus shallow land disposal; types of waste compatible with GCD; objectives of GCD borehole demonstration test; engineering and technical issues; and factors affecting performance of the greater confinement disposal facility

Assessment of impacts from different waste treatment and waste disposal technologies: Regional Management Plan

International Nuclear Information System (INIS)

Robertson, B.C.; Sutherland, A.A.

1986-01-01

This report presents assessments of treatment and disposal technologies that appear to be appropriate for use in regional facilities in the Midwest Compact Region. The treatment technologies assessed: compaction with a supercompactor; incineration; and incineration followed by solidfication of the incinerator ash. The disposal technologies assessed are: shallow land burial, considered a baseline for comparison of other technologies; below-ground vaults; abov-groudn vaults; the earth mounded concrete bunker, a technology developed in France; improved shallow land burial, essentially deeper burial; modular concrete canister disposal; mined cavities (both new and existing); and unlined augered holes; and lined augered holes. The teatment technologies are assessed primarily in terms of the their impact on the waste management system, and generally not comparatively. The dispoal technologies are assessed relative to the present standard practice shallow land burial; shallow land burial was slected as a frame of reference because it has an experience base spanning several decades, not because of any preferential characteristics. 20 refs., 5 tabs

Waste Disposal: Long-term Performance Studies for Radioactive Waste Disposal and Hydrogeological Modelling

Energy Technology Data Exchange (ETDEWEB)

Marivoet, J

2000-07-01

The main objectives of SCK-CEN's R and D programme on long-term performance studies are: (1) to develop a methodology and associated tools for assessing the long-term safety of geological disposal of all types of radioactive waste in clay formations and of the shallow-land burial of low-level waste; (2) to assess the performance and to identify the most influential elements of integrated repository systems for the disposal of radioactive waste; (3) to collect geological, piezometric and hydraulic data required for studying the hydrogeological system in north-eastern Belgium; (4) to develop a regional aquifer model for north-easter Belgium and to apply it in the performance assessments for the Mol site; (5) to test, verify and improve computer codes used in the performance assessment calculations of waste disposal concepts and contaminated sites (the computer codes simulate water flow and transport of radionuclides in engineered barriers, aquifers and contaminated sites). The scientific programme and achievements in 1999 are described.

Mechanisms of long-term concrete degradation in LLW disposal facilities

International Nuclear Information System (INIS)

Rogers, V.C.

1987-01-01

Most low-level waste (LLW) disposal alternatives, except shallow land burial and improved shallow land burial, involve the use of concrete as an extra barrier for containment. Because concrete is a porous-type material, its moisture retention and transport properties can be characterized with parameters that are also used to characterize the geohydrologic properties of soils. Several processes can occur with the concrete to degrade it and to increase both the movement of water and contaminants through the disposal facility. The effect of these processes must be quantified in designing and estimating the long-term performance of disposal facilities. Modeling the long-term performance of LLW disposal technologies involves, first, estimating the degradation rate of the concrete in a particular facility configuration and environmental setting; second, calculating the water flow through the facility as a function of time; third, calculating the contaminant leaching usually by diffusion or dissolution mechanisms, and then coupling the facility water and contaminant outflow to a hydrogeological and environmental uptake model for environmental releases or doses

Nuclear power and radioactive waste: a sub-seabed disposal option

International Nuclear Information System (INIS)

Deese, D.A.

1978-01-01

The radioactive waste disposal programs of most countries are still focused on investigation of land-based geologic formations as possible containment media for radioactive wastes. Important discoveries in geological oceanography and amazing advances in ocean engineering over the past decade have, however, led several countries to investigate another promising possibility for geologic disposal of radioactive waste--isolation within the deep seabed or sub-seabed disposal. Beyond the various technical advantages and disadvantages involved, use of the international seabed for radioactive waste disposal raises a multitude of social, economic, political, legal, institutional, and ethical issues. These issues are analyzed in this volume

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

Energy Technology Data Exchange (ETDEWEB)

Jungers, D.K.

1993-10-01

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

Progress toward disposal of LLRW in Canada

Energy Technology Data Exchange (ETDEWEB)

Charlesworth, D. H.

1989-08-15

Low-level radioactive wastes are managed in Canada currently by interim storage methods operated by the major generators of the wastes. The potential benefits of permanent disposal have led Atomic Energy of Canada Limited to undertake a development and demonstration program to make the transition from storage to disposal at its Chalk River Nuclear Laboratories. The first stages of the demonstration are based on an enhanced version of shallow land burial for the least hazardous wastes, and a unique design of a belowground concrete vault. The program includes the development and testing of the auxiliary equipment, processes and procedures necessary to support the disposal system, as well as the performance assessment methods and information needed to assure its safety.

Progress toward disposal of LLRW in Canada

International Nuclear Information System (INIS)

Charlesworth, D.H.

1989-08-01

Low-level radioactive wastes are managed in Canada currently by interim storage methods operated by the major generators of the wastes. The potential benefits of permanent disposal have led Atomic Energy of Canada Limited to undertake a development and demonstration program to make the transition from storage to disposal at its Chalk River Nuclear Laboratories. The first stages of the demonstration are based on an enhanced version of shallow land burial for the least hazardous wastes, and a unique design of a belowground concrete vault. The program includes the development and testing of the auxiliary equipment, processes and procedures necessary to support the disposal system, as well as the performance assessment methods and information needed to assure its safety

Processing and waste disposal representative for fusion breeder blanket systems

International Nuclear Information System (INIS)

Finn, P.A.; Vogler, S.

1987-01-01

This study is an evaluation of the waste handling concepts applicable to fusion breeder systems. Its goal is to determine if breeder blanket waste can be disposed of in shallow land burial, the least restrictive method under US Nuclear Regulatory regulations. The radionuclides expected in the materials used in fusion reactor blankets are described, as are plans for reprocessing and disposal of the components of different breeder blankets. An estimate of the operating costs involved in waste disposal is made

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

International Nuclear Information System (INIS)

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

1993-10-01

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

Plans and Progress on Hanford MLLW Treatment and Disposal

International Nuclear Information System (INIS)

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

2003-01-01

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

Groundwater quality sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

This Sampling and Analysis Plan addresses groundwater quality sampling and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of energy and managed by martin Marietta Energy Systems, Inc. (Energy Systems). Groundwater sampling will be conducted by Energy Systems at 45 wells within WAG 6. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the groundwater quality monitoring, sampling, and analysis will aid in evaluating relative risk associated with contaminants migrating off-WAG, and also will fulfill Resource Conservation and Recovery Act (RCRA) interim permit monitoring requirements. The sampling steps described in this plan are consistent with the steps that have previously been followed by Energy Systems when conducting RCRA sampling.

Groundwater Quality Sampling and Analysis Plan for Environmental Monitoring Waste Area Grouping 6 at Oak Ridge National Laboratory. Environmental Restoration Program

International Nuclear Information System (INIS)

1995-09-01

This Sampling and Analysis Plan addresses groundwater quality sampling and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. (Energy Systems). Groundwater sampling will be conducted by Energy Systems at 45 wells within WAG 6. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the groundwater quality monitoring, sampling, and analysis will aid in evaluating relative risk associated with contaminants migrating off-WAG, and also will fulfill Resource Conservation and Recovery Act (RCRA) interim permit monitoring requirements. The sampling steps described in this plan are consistent with the steps that have previously been followed by Energy Systems when conducting RCRA sampling

Groundwater quality sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1994-03-01

This Sampling and Analysis Plan addresses groundwater quality sampling and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of energy and managed by martin Marietta Energy Systems, Inc. (Energy Systems). Groundwater sampling will be conducted by Energy Systems at 45 wells within WAG 6. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the groundwater quality monitoring, sampling, and analysis will aid in evaluating relative risk associated with contaminants migrating off-WAG, and also will fulfill Resource Conservation and Recovery Act (RCRA) interim permit monitoring requirements. The sampling steps described in this plan are consistent with the steps that have previously been followed by Energy Systems when conducting RCRA sampling

Groundwater Monitoring and Tritium-Tracking Plan for the 200 Area State-Approved Land Disposal Site

Energy Technology Data Exchange (ETDEWEB)

Barnett, D. Brent

2000-08-31

The 200 Area State-Approved Land Disposal Site (SALDS) is a drainfield which receives treated wastewater, occasionally containing high levels of tritium from treatment of Hanford Site liquid wastes. Only the SALDS proximal wells (699-48-77A, 699-48-77C, and 699-48-77D) have been affected by tritium from the facility thus far; the highest activity observed (2.1E+6 pCi/L) occurred in well 699-48-77D in February 1998. Analytical results of groundwater geochemistry since groundwater monitoring began at the SALDS indicate that all constituents with permit enforcement limits have been below those limits with the exception of one measurement of total dissolved solids (TDS) in 1996. The revised groundwater monitoring sampling and analysis plan eliminates chloroform, acetone, tetrahydrofuran, benzene, and ammonia as constituents. Replicate field measurements will replace laboratory measurements of pH for compliance purposes. A deep companion well to well 699-51-75 will be monitored for tritium deeper in the uppermost aquifer.

Groundwater Monitoring and Tritium-Tracking Plan for the 200 Area State-Approved Land Disposal Site

Energy Technology Data Exchange (ETDEWEB)

DB Barnett

2000-08-31

The 200 Area State-Approved Land Disposal Site (SALDS) is a drainfield which receives treated wastewater, occasionally containing tritium from treatment of Hanford Site liquid wastes at the 200 Area Effluent Treatment Facility (ETF). Since operation of the SALDS began in December 1995, discharges of tritium have totaled {approx}304 Ci, only half of what was originally predicted for tritium quantity through 1999. Total discharge volumes ({approx}2.7E+8 L) have been commensurate with predicted volumes to date. This document reports the results of all tritium analyses in groundwater as determined from the SALDS tritium-tracking network since the first SALDS wells were installed in 1992 through July 1999, and provides interpretation of these results as they relate to SALDS operation and its effect on groundwater. Hydrologic and geochemical information are synthesized to derive a conceptual model, which is in turn used to arrive at an appropriate approach to continued groundwater monitoring at the facility.

200 West Groundwater Aggregate Area management study report

International Nuclear Information System (INIS)

1993-01-01

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

200 North Aggregate Area source AAMS report

International Nuclear Information System (INIS)

1993-06-01

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

PUREX source Aggregate Area management study report

International Nuclear Information System (INIS)

1993-03-01

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

200 North Aggregate Area source AAMS report

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

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

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

An interim report of the Subcommittee on Radioactive Waste Countermeasures: measures for radioactive waste treatment and disposal

International Nuclear Information System (INIS)

1984-01-01

The Subcommittee on Radioactive Waste Countermeasures has studied on the measures for land disposal of low-level radioactive wastes and ultra-low-level radioactive wastes and the measures for treatment and disposal of high-level radioactive wastes and transuranium wastes. The results of studies so far are presented as an interim report. In disposal of low-level radioactive wastes, the land disposal is being required increasingly. The measures according to the levels of radioactivity are necessary. For the ultra-low-level radioactive wastes, their occurrence in large quantities is expected along with reactor decommissioning. In disposal of the high-level radioactive wastes, the present status is a transition toward the practical stages. Transuranium wastes should increase in their arising in the future. (Mori, K.)

Summary report of working group I CO{sub 2} capture, fixation/utilization, and disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-12-31

The topics of our working group were divided into four key areas: CO{sub 2} Capture, Utilization/Fixation, Ocean Disposal, and Land Disposal. Fourteen presentations were made as follows: CO{sub 2} Capture: Toshikatsu Hakuta (Japan) and Rod Judkins, Bruce St. John, and Alan Wolsky (US). Utilization/Fixation: Hironori Arakawa, Yasuo Asada, and Takashi lbusuki (Japan) and Ed Lipinsky (US). Ocean Disposal: Yuji Shindo (Japan) and Eric Adams, Gerard Nihous, and Wheeler North (US). Land Disposal: Shoichi Tanaka (Japan) and Roger Bailey (US/Canada). Co-chairs for this working group were Toshikatsu Hakuta (Japan) and Howard Herzog (US). This document contains only a summary outline of research needs in the area of CO{sub 2} capture and sequestration. It should be used in conjunction with other assessments made in this area. For the U.S., a DOE report entitled A Research Needs Assessment for the Capture, Utilization and Disposal of Carbon Dioxide from Fossil Fuel-Fired Power Plants will be forthcoming in 1993.

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-06-01

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

Economic analysis of alternative LLW disposal methods

International Nuclear Information System (INIS)

Foutes, C.E.

1987-01-01

The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were developed and input into the analysis. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. Total costs of each level of a standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, was calculated for each alternative standard. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis

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.

Technical support document for the surface disposal of sewage sludge. Final report

International Nuclear Information System (INIS)

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed

Technical support document for the surface disposal of sewage sludge. Final report

Energy Technology Data Exchange (ETDEWEB)

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed.

Safety assessments for centralized waste treatment and disposal facility in Puspokszilagy Hungary

International Nuclear Information System (INIS)

Berci, K.; Hauszmann, Z.; Ormai, P.

2002-01-01

The centralized waste treatment and disposal facility Puspokszilagy is a shallow land, near surface engineered type disposal unit. The site, together with its geographic, geological and hydrogeological characteristics, is described. Data are given on the radioactive inventory. The operational safety assessment and the post-closure safety assessment is outlined. (author)

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

Disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Hendee, W.R.

1986-01-01

The generation of low-level radioactive waste is a natural consequence of the societal uses of radioactive materials. These uses include the application of radioactive materials to the diagnosis and treatment of human disease and to research into the causes of human disease and their prevention. Currently, low level radioactive wastes are disposed of in one of three shallow land-burial disposal sites located in Washington, Nevada, and South Carolina. With the passage in December 1980 of Public Law 96-573, The Low-Level Radioactive Waste Policy Act, the disposal of low-level wastes generated in each state was identified as a responsibility of the state. To fulfill this responsibility, states were encouraged to form interstate compacts for radioactive waste disposal. At the present time, only 37 states have entered into compact agreements, in spite of the clause in Public Law 96-573 that established January 1, 1986, as a target date for implementation of state responsibility for radioactive wastes. Recent action by Congress has resulted in postponement of the implementation date to January 1, 1993

Advances in poultry litter disposal technology--a review.

Science.gov (United States)

Kelleher, B P; Leahy, J J; Henihan, A M; O'Dwyer, T F; Sutton, D; Leahy, M J

2002-05-01

The land disposal of waste from the poultry industry and subsequent environmental implications has stimulated interest into cleaner and more useful disposal options. The review presented here details advances in the three main alternative disposal routes for poultry litter, specifically in the last decade. Results of experimental investigations into the optimisation of composting, anaerobic digestion and direct combustion are summarised. These technologies open up increased opportunities to market the energy and nutrients in poultry litter to agricultural and non-agricultural uses. Common problems experienced by the current technologies are the existence and fate of nitrogen as ammonia, pH and temperature levels, moisture content and the economics of alternative disposal methods. Further advancement of these technologies is currently receiving increased interest, both academically and commercially. However, significant financial incentives are required to attract the agricultural industry.

Hydrologic information needs for evaluating waste disposal options

Energy Technology Data Exchange (ETDEWEB)

Huff, D.D.

1983-01-01

Before waste disposal options can be assessed, an objective or set of criteria for evaluation must be established. For hydrologists, the objective is to ensure that ground water and surface water do not become contaminated beyond acceptable limits as a result of waste disposal operations. The focus here is on the information required to quantify hydrologic transport of potential contaminants from the disposal site. It is important to recognize that the composition of the waste, its physical and chemical form, and the intended disposal methods (e.g., surface spreading, incineration, shallow land burial, or interment in a deep geologic repository) must either be specified a priori or set forth as specific options for evaluation, because these factors influence the nature of the hydrologic data needs. The hydrologic information needs of major importance are given together with specific measurable variables to be determined.

Focus on land reclamation

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

Various aspects of land reclamation, i.e. returning disturbed land to a state where, at minimum, it is at least capable of supporting the same kinds of land uses as before the disturbance, are discussed. Activities which disturb the land such as surface mining of coal, surface mining and extraction of oil sands, drilling for oil and natural gas, waste disposal sites, including sanitary landfills, clearing timber for forestry, excavating for pipelines and transportation are described, along with land reclamation legislation in Alberta, and indications of future developments in land reclamation research, legislation and regulation. Practical guidelines for individuals are provided on how they might contribute to land reclamation through judicious and informed consumerism, and through practicing good land management, inclusive of reduced use of herbicides, composting of household wastes, and planting of native species or ground cover in place of traditional lawns.

Developing a LLW disposal facility in California

International Nuclear Information System (INIS)

Romano, S.A.; Gaynor, R.K.; Hanrahan, T.P.

1988-01-01

US Ecology has been designated by the State of California to site and operate a low-level radioactive waste disposal facility. The firm identified three sites for detailed characterization work in February, 1987. Ecological and archaeological studies and related environmental assessments were undertaken to obtain land use permits from the Bureau of Land Management, which holds title to the sites. Geophysics investigations, exploratory borings, well drilling and weather station installation followed. Local Committees were established for each site to assist US Ecology in evaluating socio-economic impacts, and Native Americans were consulted regarding cultural resources. The project's Citizens Advisory Committee assisted in evaluating the three candidate sites. US Ecology systematically integrated citizen involvement into the technical studies leading to selection of the two site finalists. This approach furthered two objectives. Community leaders and the public received accurate information on the nature of low-level radioactive waste and the environmental conditions appropriate for its disposal

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

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

International Nuclear Information System (INIS)

Evans, S.K.

2002-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

1994-09-17

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

Geohydrological considerations in land disposal of LLW

International Nuclear Information System (INIS)

Yeh, G.T.; Tamura, T.

1981-01-01

The geohydrological and geochemical factors that affect the transport, transfer, and transformation of the waste in the aquifer system as a result of shallow land burial practices are discussed. They include surface topography and its character, the extent of the aquifer, nearby surface water bodies, groundwater basin divide, watershed boundaries, rainfall rate, infiltration from surface water bodies, potential evapotranspiration, hydraulic conductivity, water capacity, porosity, compressibility of the matrix, dispersivity, hydrolysis, photolysis, oxidation, volatilization, biolysis, precipitation, mineral comosition, and flow dynamics. Depending on the availability of data and the detail of information desired, three levels of analyses may be undertaken. Two examples are used to illustrate these three levels of analyses using hypothetical parameters. The examples are constructed to represent the leaching from wet water body and shallow burials, respectively. The former typifies a class of problems of groundwater contamination from coal-catching basins and uranium mill tailings. The latter represents classical examples of shallow land burials such as coal solid wastes, chemical dumping and sanitary landfill

Acquisition of public lands for disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Dawson, J.H.

1983-09-01

It is clear that the Federal Land Policy Management Act (FLPMA) gives broadly extended statutory authority to the Bureau of Land Management (BLM) to effect public land transactions. For the purposes of this study, the focus will be on an examination of the boundaries of BLM's powers to effect the exchange and sale of public lands. In the course of examining these powers, consideration will be given also to certain limitations inherent in the statutes which may delay implementation of BLM powers and the consequent effective transfer of public lands. The principal reason for possible delay is the FLPMA requirement for land use planning. Other delay sources could be the requirement for fair market value and the increased prospect of third party judicial challenge. Finally, some consideration will be given to alternative approaches such as the Federal Asset Management Program, the Recreation and Public Purposes Act and State selection of lands

The opportunities for woody biomass fuels in New Zealand produced in association with land disposal of effluent

International Nuclear Information System (INIS)

Sims, R.E.H.; Collins, C.

1993-01-01

An assessment of the future New Zealand biomass resource has shown exotic forest arisings could supply 970 GWh/year by the year 2002; wood processing residues 280 GWh/year; and fuelwood plantations 2,060 GWh/year with potential to rise to 10,000 GWh/year by 2012. Currently annual electricity demand is around 30,000 GWh 70% of which is generated by hydro power. A further 25% stems from natural gas, a resource with estimated reserves of only approximately 14 years. This paper describes how part replacement of gas by biomass could be a feasible proposition for the future. Life cycle cost analyses showed electricity could be generated from arisings for 4.8--6 c/kWh; from residues for 2.4--4.8 c/kWh; and from plantations for 4.8--7.2 c/kWh. For comparison the current retail electricity price is around 4--5.5 c/kWh and estimates for wind power generation range from 5--10 c/kWh. Future hydro-power schemes will generate power between 4--9 c/kWh depending on site suitability. The link between land disposal of effluent and short rotation coppice production can reduce the biomass costs. A meatworks processing 1.6 million sheep annually has planted 90 ha in trees for flood irrigation of effluent and biomass fuel production for use on site. Similar schemes linking sewage disposal with wood-fired power generation are under evaluation

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

International Nuclear Information System (INIS)

DeMonia, Brian; Dunning, Don; Hampshire John

2013-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Identification of sites for the low-level waste disposal development and demonstration program

International Nuclear Information System (INIS)

Ketelle, R.H.; Lee, D.W.

1988-04-01

This report presents the results of site selection studies for potential low-level radioactive waste disposal sites on the Oak Ridge Reservation (ORR). Summaries of the site selection procedures used and results of previous site selection studies on the ORR are included. This report includes recommendations of sites for demonstration of shallow land burial using engineered trench designs and demonstration of above-grade disposal using design concepts similar to those used in tumulus disposal. The site selection study, like its predecessor (ORNL/TM-9717, Use of DOE Site Selection Criteria for Screening Low-Level Waste Disposal Sites on the Oak Ridge Reservation), involved application of exclusionary site screening criteria to the region of interest to eliminate unacceptable areas from consideration. Also like the previous study, the region of interest for this study was limited to the Oak Ridge Department of Energy Reservation. Reconnaissance-level environmental data were used in the study, and field inspections of candidate sites were made to verify the available reconnaissance data. Five candidate sites, all underlain by Knox dolomite residuum and bedrock, were identified for possible development of shallow land burial facilities. Of the five candidate sites, the West Chestnut site was judged to be best suited for deployment of the shallow land burial technology. Three candidate sites, all underlain by the Conasauga Group in Bear Creek Valley, were identified for possible development of above-grade disposal technologies. Of the three sites identified, the Central Bear Creek Valley site lying between State Route 95 and Gum Hollow Road was ranked most favorable for deployment of the above-grade disposal technology

Data base for radioactive waste management: review of low-level radioactive waste disposal history

International Nuclear Information System (INIS)

Clancy, J.J.; Gray, D.F.; Oztunali, O.I.

1981-11-01

This document is prepared in three volumes and provides part of the technical support to the draft environmental impact statement (NUREG-0782) on a proposed regulation, 10CFR Part 61, setting forth licensing requirements for land disposal of low level radioactive waste. Volume 1 is a summary and analysis of the history of low level waste disposal at both commercial and government disposal facilities

Sewage sludge pretreatment and disposal. (Latest citations from the NTIS Bibliographic database). Published Search

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The bibliography contains citations concerning techniques and equipment used in the pretreatment processes and disposal of sewage sludges. Topics include resource and energy recovery operations, land disposal, composting, ocean disposal, and incineration. Digestion, dewatering, and disinfection are among the pretreatment processes discussed. Environmental aspects, including the effects on soils, plants, and animals, are also presented. (Contains 250 citations and includes a subject term index and title list.)

Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

International Nuclear Information System (INIS)

Moriyama, Yoshinori

1998-01-01

Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

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

International Nuclear Information System (INIS)

1994-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-04-01

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

Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste. Summary and main report

International Nuclear Information System (INIS)

1982-11-01

The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

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

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.

Long-term surveillance plan for the Lowman, Idaho, disposal site

International Nuclear Information System (INIS)

1993-09-01

The long-term surveillance plan (LTSP) for the Lowman, Idaho, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lowman disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This preliminary final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. The LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and describes, in detail, how the long-term care of the disposal site will be carried out through the UMTRA Project long-term surveillance program. The Lowman, Idaho, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program, (DOE, 1992)

Conceptual design report for Central Waste Disposal Facility

International Nuclear Information System (INIS)

1984-01-01

The permanent facilities are defined, and cost estimates are provided for the disposal of Low-Level Radioactive Wastes (LLW) at the Central Waste Disposal Facility (CWDF). The waste designated for the Central Waste Disposal Facility will be generated by the Y-12 Plant, the Oak Ridge Gaseous Diffusion Plant, and the Oak Ridge National Laboratory. The facility will be operated by ORNL for the Office of Defense Waste and By-Products Management of the Deparment of Energy. The CWDF will be located on the Department of Energy's Oak Ridge Reservation, west of Highway 95 and south of Bear Creek Road. The body of this Conceptual Design Report (CDR) describes the permanent facilities required for the operation of the CWDF. Initial facilities, trenches, and minimal operating equipment will be provided in earlier projects. The disposal of LLW will be by shallow land burial in engineered trenches. DOE Order 5820 was used as the performance standard for the proper disposal of radioactive waste. The permanent facilities are intended for beneficial occupancy during the first quarter of fiscal year 1989. 3 references, 9 figures, 7 tables

De minimis concepts in radioactive waste disposal. Considerations in defining de minimis quantities of solid radioactive waste for uncontrolled disposal by incineration and landfill

International Nuclear Information System (INIS)

1983-02-01

This document deals with recommendations addressed to those national authorities wishing to dispose of low level radioactive waste into the terrestrial environment, on how de minimis levels or quantities can be derived. The only radioactive materials covered here are declared solid radioactive wastes of very low activity which are controlled up to the point where deliberate control is lost, or wastes below a level that requires regulatory control. As regards the disposal sites, these wastes are not intended to be disposed of in fully controlled disposal facilities, such as repositories located in shallow land, rock cavities, etc. On the other hand, it is considered that these materials should not be disposed of in any place, but should be handled like other municipal wastes. Among the different techniques available, only two are considered in this document, namely a sanitary landfill facility, and an urban incineration plant

Options for the disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Mitchell, N.T.; Laughton, A.S.; Webb, G.A.M.

1977-01-01

The management of radioactive waste within the fuel cycle, especially the high-level wastes from reprocessing of nuclear fuel, is currently a matter of particular concern. In the short term (meaning a timescale of tens of years) management by engineered storage is considered to provide a satisfactory solution. Beyond this, however, the two main alternative options which are considered in the paper are: (a) disposal by burial into geologic formations on land; and (b) disposal by emplacement into or onto the seabed. Status of our present knowledge on the land and seabed disposal options is reviewed together with an assessment of the extent to which their reliability and safety can be judged on presently available information. Further information is needed on the environmental behaviour of radioactivity in the form of solidified waste in both situations in order to provide a more complete, scientific assessment. Work done so far has clarified the areas where further research is most needed - for instance modelling of the environmental transfer processes associated with the seabed option. This is discussed together with an indication of the research programmes which are now being pursued

Problems in shallow land disposal of solid low-level radioactive waste in the united states

Science.gov (United States)

Stevens, P.R.; DeBuchananne, G.D.

1976-01-01

Disposal of solid low-level wastes containing radionuclides by burial in shallow trenches was initiated during World War II at several sites as a method of protecting personnel from radiation and isolating the radionuclides from the hydrosphere and biosphere. Today, there are 11 principal shallow-land burial sites in the United States that contain a total of more than 1.4 million cubic meters of solid wastes contaminated with a wide variety of radionuclides. Criteria for burial sites have been few and generalized and have contained only minimal hydrogeologic considerations. Waste-management practices have included the burial of small quantities of long-lived radionuclides with large volumes of wastes contaminated with shorter-lived nuclides at the same site, thereby requiring an assurance of extremely long-time containment for the entire disposal site. Studies at 4 of the 11 sites have documented the migration of radionuclides. Other sites are being studied for evidence of containment failure. Conditions at the 4 sites are summarized. In each documented instance of containment failure, ground water has probably been the medium of transport. Migrating radionuclides that have been identified include90Sr,137Cs,106Ru,239Pu,125Sb,60Co, and3H. Shallow land burial of solid wastes containing radionuclides can be a viable practice only if a specific site satisfies adequate hydrogeologic criteria. Suggested hydrogeologic criteria and the types of hydrogeologic data necessary for an adequate evaluation of proposed burial sites are given. It is mandatory that a concomitant inventory and classification be made of the longevity, and the physical and chemical form of the waste nuclides to be buried, in order that the anticipated waste types can be matched to the containment capability of the proposed sites. Ongoing field investigations at existing sites will provide data needed to improve containment at these sites and help develop hydrogeologic criteria for new sites. These

Russian low-level waste disposal program

Energy Technology Data Exchange (ETDEWEB)

Lehman, L. [L. Lehman and Associates, Inc., Burnsville, MN (United States)

1993-03-01

The strategy for disposal of low-level radioactive waste in Russia differs from that employed in the US. In Russia, there are separate authorities and facilities for wastes generated by nuclear power plants, defense wastes, and hospital/small generator/research wastes. The reactor wastes and the defense wastes are generally processed onsite and disposed of either onsite, or nearby. Treating these waste streams utilizes such volume reduction techniques as compaction and incineration. The Russians also employ methods such as bitumenization, cementation, and vitrification for waste treatment before burial. Shallow land trench burial is the most commonly used technique. Hospital and research waste is centrally regulated by the Moscow Council of Deputies. Plans are made in cooperation with the Ministry of Atomic Energy. Currently the former Soviet Union has a network of low-level disposal sites located near large cities. Fifteen disposal sites are located in the Federal Republic of Russia, six are in the Ukraine, and one is located in each of the remaining 13 republics. Like the US, each republic is in charge of management of the facilities within their borders. The sites are all similarly designed, being modeled after the RADON site near Moscow.

Greater-Than-Class C Low Level Radioactive Waste Characteristics and Disposal Aspects

International Nuclear Information System (INIS)

Arlt, Hans D.; Brimfield, Terrence; Grossman, Chris

2016-01-01

Conclusions • Due to the way LLRW is defined in the US, there is a category of LLRW (i.e., GTCC waste) that was categorized in the 1980’s and is similar to ILW and not generally acceptable for near-surface disposal. • Three decades later, it cannot be excluded that future NRC analyses may find some GTCC waste type suitable for near-surface disposal, and a proposed rule may be developed for licensing the disposal of such waste. • Current regulations only allow individual proposals for GTCC LLRW disposal to be evaluated on a case-by-case basis to determine the acceptability of land disposal other than in a geologic repository • Based on current regulations, the variability and diversity of FEPs associated with such safety cases is theoretically large: - The range of activity concentrations, half-lives, and volumes of GTCC waste types is large; - The range of physical forms is large: metal pieces to soils and sludges; - The range of potential disposal methods is large: trench, vault, landfill, shaft, borehole; - The range of potential disposal environments is large: arid vs. humid, unsaturated vs. saturated, sediment vs. rock, nearsurface to intermediate; - The stability and past natural history of a specific disposal site must also be adequately known. • Examples of potential site-specific cases designed to demonstrate the acceptability of GTCC LLRW land disposal other than deep geologic: - Proposals for disposal could entail concepts that have been relatively well assessed by NRC staff in the past; e.g., trench disposal of a moderate volume of GTCC Other Waste in an arid, unsaturated, near-surface environment; - Proposals for disposal could also entail concepts that have been less frequently assessed; e.g., borehole disposal of higher activity sealed sources in a humid, saturated, intermediate depth environment. • However, if one potential site and design was under consideration, the variability and diversity of FEPs associated with that site

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

International Nuclear Information System (INIS)

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

2001-01-01

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

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

Study of backfill material composition for shallow land radioactive wastes disposal

International Nuclear Information System (INIS)

Sukarman-Aminjoyo; Sukrosono; Supardi

1996-01-01

The composition of back fill material for shallow land radioactive wastes disposal has been investigated by using bentonite, magnetic and quartz sands. The aim of this research is to observe the kind of mineral suitable for back fill material. The research was done for each mineral material and for the mixture of those three minerals. Firstly 2 grams of bentonite. magnetite or quartz sand was put into a glass column of 1.2 cm in diameter. Then the Sr-90 liquid waste was flown through out the column. In this experiment the adsorption velocity, through velocity, adsorption capacity and decontamination factor were determined for the grain size of 10 up to 100 mesh. By the same method the experiment was done for the mix of those three minerals. The experiment result indicated that the grain size mineral influenced the parameter of adsorption velocity, through velocity, adsorption capacity and decontamination factor. The relatively good result was obtained for the grain size of 80 mesh. Among the three kinds of minerals, bentonite had the highest of adsorption capacity and decontamination factor, while its adsorption velocity and through velocity were the lowest. The mixture of that three minerals gave better result than that mixture of two mineral component. The usage of the mineral mixture with the grain size of 80 mesh and the weight ratio between that component of 1:1:1, resulted in the decontamination factor of 68.44, the adsorption capacity of 235 ml/g, the adsorption velocity of 31x10 -3 ml/sec. and the through velocity of 1.82x10 -3 ml/sec

Soil management planning for military installations: Strategy for identifying contaminated soils

International Nuclear Information System (INIS)

Makdisi, R.S.; Baskin, D.A.; Downey, D.; Taffinder, S.A.

1992-01-01

Numerous federal and state regulations mandate the proper handling and disposal and/or treatment of contaminated soils. The Land Disposal Ban and the increasing lack of new or proximal land disposal facilities, coupled with the increasing liability of off-site disposal, have created a need for altering the traditional methods of managing contaminated sods. To delineate soil management decisions, a Soil Management Plan (SMP) was developed which incorporates the substantive requirements of CERCLA/SARA and RCRA into the ongoing base activities (i.e., construction projects, utility repairs and maintenance) and other environmental projects (i.e., underground storage tank removals) that may involve contaminated soils. The decision-making process is developed to guide base personnel in recognizing contamination, following proper sampling and temporary storage procedures, preventing unnecessary human exposure and isolating soils for removal off-site or treatment on-site. The SMP also contains a comprehensive review of soil remediation technologies, such as biological treatment, soil vapor extraction, soil washing, biofiltering, thermal desorption, soil stabilization/solidification, chemical/physical treatment and incineration. Contaminant types expected at the federal military facility are cross-referenced to the appropriate remediation technologies to determine the specific base needs for a soil treatment unit. An example of a conceptual design for a hydrocarbon-contaminated soil treatment unit is presented for a base where underground fuel tanks are the principal source of soil contamination

Economic analysis of alternative LLW disposal methods

International Nuclear Information System (INIS)

Foutes, C.E.; Queenan, C.J. III

1987-01-01

The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were evaluated both in absolute terms and also relative to a base case (current practice). Incremental costs of the standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, defined as the incremental cost per avoided health effect, was calculated for each alternative standard. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis. 15 references, 7 figures, 3 tables

US/Japan workshop on global change land disposal of CO{sub 2}

Energy Technology Data Exchange (ETDEWEB)

Bailey, R.T. [Alberta Oil Sands Technology and Research Authority (Canada)

1993-12-31

The general responses proposed to reduce CO{sub 2} emissions to the atmosphere are conservation, improved efficiency and fuel substitution. These are valid options but other alternatives such as CO{sub 2} capture and disposal may be more attractive for specific areas. There are good reasons why the capture and disposal option fits the situation in Western Canada. The first and obvious reason is the importance of hydrocarbon energy to the regional economy. Here the economy is based on the production, utilization and sale of hydrocarbons such as coal, oil and natural gas and we intend to stay in business. Besides meeting the Canadian demand, natural gas from Alberta is used in the US as far away as Boston and Los Angeles. Canadian heavy crude oil serves much of the American Midwest and coal from the Canadian Rocky Mountains is exported to Japan. Although many may consider these hydrocarbon reserves and fossil fuel production as part of the greenhouse gas problem, they may offer part of the solution through the capture and disposal of CO{sub 2}.

Institutional considerations for near-surface land disposal

International Nuclear Information System (INIS)

Gustafson, P.F.

1989-01-01

This chapter discusses the federal and state responsibilities for low level radioactive waste and the laws and policies that have been enacted to define those responsibilities. Historical perspective is given on the intent by both Congress and the Atomic Energy Commission to keep all nuclear activity other than regulating and licensing in the private sector. The Low Level Waste Policy Act of 1980 and the 1985 Amendments are described along with the ramifications for states. Individual state approaches and regional compacts for LLW management are examined and the following general issues common to all endeavors are considered: Public involvement, Management plans, Economic viability, Site selection criteria, Site acceptance incentives, Disposal technology, Selection of site operator, and Site ownership. Finally, licensing and other regulatory responsibilities; site closure, long-term ownership, and fiscal responsibility; unresolved issues; and flaws in the present compact alignments are discussed

Design and operation of a low-level solid-waste disposal site at Los Alamos

International Nuclear Information System (INIS)

Balo, K.A.; Wilson, N.E.; Warren, J.L.

1982-01-01

Since the mid-1940's, approximately 185000 m 3 of low-level and transuranic radioactive solid waste, generated in operations at the Los Alamos National Laboratory, have been disposed of by on-site shallow land burial. Procedures and facilities have been designed and evaluated in the areas of waste acceptance, treatment and storage, disposal, traffic control, and support systems. The methodologies assuring the proper management and disposal of radioactive solid waste are summarized

Low-Level Burial Grounds dangerous waste permit application: Request for exemption from lined trench requirements and from land disposal restrictions for residual liquid at 218-E-12B Burial Ground Trench 94

International Nuclear Information System (INIS)

1992-10-01

This document has been prepared and is being submitted to the respective agencies to satisfy three objectives of the US Department of Energy (DOE) Richland Field Office (DOE-RL) concerning Trench 94 of the 218-E-12B Burial Ground. The 218-E-12B Burial Ground is located in the 200 East Area of the Hanford Facility. Figure 1-1 shows the general location of the Hanford Site. The 218-E-12B Burial Ground is one of eight burial grounds included in the Low-Level Burial Grounds (LLBG), a treatment, storage and/or disposal (TSD) unit. Decommissioned, defueled naval submarine reactor compartments (SRCs) contain radioactivity caused by exposure of structural components to neutrons during normal operation of the submarines. After all the alternatives were evaluated in the US Department of the Navy 1984 environmental impact statement (EIS) (USN 1984), land burial of the SRCs was selected as the preferred disposal option. The SRCs currently are sent to Trench 94 of the 218-E-12B Burial Ground. In addition to radioactivity, the SRCs disposed in. The DOE-RL's three objectives in preparing and submitting this document are as follows. Request from Ecology an exemption from dangerous waste landfill liner and leachate collection and removal system (hereinafter referred to as liner/leachate system) requirements for Trench 94 of the 218-E-12B Burial Ground. Petition Ecology to exempt residual liquid in the SRCs from land disposal restrictions. Obtain EPA Region 10 review and comment on the request to Ecology for exemption from liner/leachate system requirements

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

International Nuclear Information System (INIS)

1993-01-01

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

Co-disposal of sewage sludge and solid wastes-it works

Energy Technology Data Exchange (ETDEWEB)

Sussman, D B

1977-10-01

The problem of sludge disposal is one of more sludge than ever before, few suitable land disposal or land application sites, the ocean dumping option being phased out, and energy cost so high or supplies so few as to make incineration a questionable endeavor. The energy required to run a wastewater treatment plant and the heat needed to incinerate the sludge may be available in the same community in the form of municipal solid waste. Municipal sludge has a heat value of about 10,000 Btu/lb of dry solids; it is autogenous at>30% solids. Codisposal techniques are discussed which use the energy produced by the combustion of solid waste to dewater the sludge to its autogenous point. One approach is to use sewage sludge incinerators, in many cases already installed at the wastewater treatment plant, and to use the organic portion of solid waste as a fuel to dry, burn, and reduce the volume of the sludge that must ultimately be disposed. A second approach would use a solid waste incinerator, solid waste-fired steam generator, or waterwall combustion unit to burn dewatered sludge. Both approaches are being demonstrated or used. Thermal sludge disposal at wastewater treatment plants normally is carried out in multiple-hearth or fluidized-bed incinerators. The experiences of such plants in the US and Europe are summarized.

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

Energy Technology Data Exchange (ETDEWEB)

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

International Nuclear Information System (INIS)

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-01

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility

Proceedings of the Department of Energy Defense Programs hazardous and mixed waste minimization workshop: Hazardous Waste Remedial Actions Program

International Nuclear Information System (INIS)

1988-09-01

The first workshop on hazardous and mixed waste minimization was held in Las Vegas, Nevada, on July 26--28, 1988. The objective of this workshop was to establish an interchange between DOE headquarters (DOE-HQ) DP, Operations Offices, and contractors of waste minimization strategies and successes. The first day of the workshop began with presentations stressing the importance of establishing a waste minimization program at each site as required by RCRA, the land ban restrictions, and the decrease in potential liabilities associated with waste disposal. Discussions were also centered on pending legislation which would create an Office of Waste Reduction in the Environmental Protection Agency (EPA). The Waste Minimization and Avoidance Study was initiated by DOE as an addition to the long-term productivity study to address the issues of evolving requirements facing RCRA waste management activities at the DP sites, to determine how major operations will be affected by these requirements, and to determine the available strategies and options for waste minimization and avoidance. Waste minimization was defined in this study as source reduction and recycling

Waste Isolation Pilot Plant land management plan

International Nuclear Information System (INIS)

1996-01-01

On October 30, 1992, the WIPP Land Withdrawal Act became law. This Act transferred the responsibility for the management of the WIPP Land Withdrawal Area (WILWA) from the Secretary of the Interior to the Secretary of Energy. In accordance with sections 3(a)(1) and (3) of the Act, these lands open-quotes hor-ellipsis are withdrawn from all forms of entry, appropriation, and disposal under the public land laws hor-ellipsis close quotesand are reserved for the use of the Secretary of Energy open-quotes hor-ellipsis for the construction, experimentation, operation, repair and maintenance, disposal, shutdown, monitoring, decommissioning, and other activities, associated with the purposes of WIPP as set forth in the Department of Energy National Security and Military Applications of Nuclear Energy Act of 1980 and this Act.close quotes. As a complement to this LMP, a MOU has been executed between the DOE and the BLM, as required by section 4(d) of the Act. The state of New Mexico was consulted in the development of the MOU and the associated Statement of Work (SOW)

Waste Isolation Pilot Plant land management plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

On October 30, 1992, the WIPP Land Withdrawal Act became law. This Act transferred the responsibility for the management of the WIPP Land Withdrawal Area (WILWA) from the Secretary of the Interior to the Secretary of Energy. In accordance with sections 3(a)(1) and (3) of the Act, these lands {open_quotes}{hor_ellipsis}are withdrawn from all forms of entry, appropriation, and disposal under the public land laws{hor_ellipsis}{close_quotes}and are reserved for the use of the Secretary of Energy {open_quotes}{hor_ellipsis}for the construction, experimentation, operation, repair and maintenance, disposal, shutdown, monitoring, decommissioning, and other activities, associated with the purposes of WIPP as set forth in the Department of Energy National Security and Military Applications of Nuclear Energy Act of 1980 and this Act.{close_quotes}. As a complement to this LMP, a MOU has been executed between the DOE and the BLM, as required by section 4(d) of the Act. The state of New Mexico was consulted in the development of the MOU and the associated Statement of Work (SOW).

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

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.

Characterization of organics in leachates from low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Francis, A.J.; Iden, C.R.; Nine, B.; Chang, C.

1979-01-01

Low-level radioactive wastes generated by the nuclear industry, universities, research institutions, and hospitals are disposed of in shallow-land trenches and pits. In 1962 the first commercial disposal site was opened in Beatty, Nevada. Since then, the industry has grown to include three private companies operating six disposal areas located in sparsely populated areas: at Maxey Flats (Morehead), Kentucky; Beatty, Nevada; Sheffield, Illinois; Barnwell, South Carolina; West Valley, New York; and Richland, Washington. Although the facilities are operated by private industry, they are located on public land and are subject to federal and state regulation. Although inventories of the radioactive materials buried in the disposal sites are available, no specific records are kept on the kinds and quantities of organic wastes buried. In general, the organic wastes consist of contaminated paper, packing materials, clothing, plastics, ion-exchange resins, scintillation vials, solvents, chemicals, decontamination fluids, carcasses of experimental animals, and solidification agents. Radionuclides such as 14 C, 3 H, 90 Sr, 134 137 Cs, 60 Co, 241 Am, and 238 239 240 Pu have been identified in leachate samples collected from several trenches at Maxey Flats and West Valley. The purpose of this report is to identify some of the organic compounds present in high concentrations in trench leachates at the disposal sites in order to begin to evaluate their effect on radionuclide mobilization and contamination of the environment

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.

Disposal options for polluted plants grown on heavy metal contaminated brownfield lands - A review.

Science.gov (United States)

Kovacs, Helga; Szemmelveisz, Katalin

2017-01-01

Reducing or preventing damage caused by environmental pollution is a significant goal nowadays. Phytoextraction, as remediation technique is widely used, but during the process, the heavy metal content of the biomass grown on these sites special treatment and disposal techniques are required, for example liquid extraction, direct disposal, composting, and combustion. These processes are discussed in this review in economical and environmental aspects. The following main properties are analyzed: form and harmful element content of remains, utilization of the main and byproducts, affect to the environment during the treatment and disposal. The thermal treatment (combustion, gasification) of contaminated biomass provides a promising alternative disposal option, because the energy production affects the rate of return, and the harmful elements are riched in a small amount of solid remains depending on the ash content of the plant (1-2%). The biomass combustion technology is a wildely used energy production process in residential and industrial scale, but the ordinary biomass firing systems are not suited to burn this type of fuel without environmental risk. Copyright © 2016 Elsevier Ltd. All rights reserved.

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

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)

75 FR 30392 - Approval of a Petition for Exemption from Hazardous Waste Disposal Injection Restrictions to...

Science.gov (United States)

2010-06-01

... petition for renewal of an existing exemption from the land disposal restrictions of hazardous waste on... Waste Disposal Injection Restrictions to Cabot Corporation Tuscola, Tuscola, IL AGENCY: Environmental... under the 1984 Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act...

Waste disposal in underground mines -- A technology partnership to protect the environment

International Nuclear Information System (INIS)

1995-01-01

Environmentally compatible disposal sites must be found despite all efforts to avoid and reduce the generation of dangerous waste. Deep geologic disposal provides the logical solution as ever more categories of waste are barred from long-term disposal in near-surface sites through regulation and litigation. Past mining in the US has left in its wake large volumes of suitable underground space. EPA studies and foreign practice have demonstrated deep geologic disposal in mines to be rational and viable. In the US, where much of the mined underground space is located on public lands, disposal in mines would also serve the goal of multiple use. It is only logical to return the residues of materials mined from the underground to their origin. Therefore, disposal of dangerous wastes in mined underground openings constitutes a perfect match between mining and the protection and enhancement of the environment

Long-term storage of radioactive solid waste within disposal facilities

International Nuclear Information System (INIS)

Wakerley, M.W.; Edmunds, J.

1986-05-01

A study of the feasibility and implications of operating potential disposal facilities for low and intermediate level solid radioactive waste in a retrievable storage mode for extended periods of up to 200 years has been carried out. The arisings of conditioned UK radioactive waste up to the year 2030 have been examined. Assignments of these wastes to different types of underground disposal facilities have been made on the basis of their present activity and that which they will have in 200 years time. Five illustrative disposal concepts proposed both in the UK and overseas have been examined with a view to their suitability for adaption for storage/disposal duty. Two concepts have been judged unsuitable because either the waste form or the repository structure were considered unlikely to last the storage phase. Three of the concepts would be feasible from a construction and operational viewpoint. This suggests that with appropriate allowance for geological aspects and good repository and waste form design that storage/disposal within the same facility is achievable. The overall cost of the storage/disposal concepts is in general less than that for separate surface storage followed by land disposal, but more than that for direct disposal. (author)

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

International Nuclear Information System (INIS)

2001-01-01

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

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)

Screening of alternative methods for the disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Macbeth, P.J.; Thamer, B.J.; Christensen, D.E.; Wehmann, G.

1978-10-01

A systematic method for categorizing these disposal alternatives which provides assurance that no viable alternatives are overlooked is reported. Alternatives are categorized by (1) the general media in which disposal occurs, (2) by whether the disposal method can be considered as dispersal, containment or elimination of the wastes, and (3) by the applicability of the disposal method to the possible physical waste forms. A literature survey was performed and pertinent references listed for the various alternatives discussed. A bibliography is given which provides coverage of published information on low-level radioactive waste management options. The extensive list of disposal alternatives identified was screened and the most viable choices were selected for further evaluation. A Technical Advisory Panel met and reviewed the results. Suggestions from that meeting and other comments are discussed. The most viable options selected for further evaluation are: (1) improving present shallow land burial practices; (2) deeper depth burial; (3) disposal in cavities; (4) disposal in exposed or buried structures; and (5) ocean disposal. 42 references

Geology of high-level nuclear waste disposal

International Nuclear Information System (INIS)

Roxburgh, I.S.

1988-01-01

The concept of geological disposal is set out by describing the major rock types in terms of their ability to isolate high-level nuclear waste. The advantages and problems posed by particular rock formations are explored and the design and construction of geological repositories is considered, along with the methods used to estimate their safety. It gives special consideration to the use of sea-covered rock and sediment as well as the on-land situation. Throughout the book the various principles and problems inherent in geological disposal are explained and illustrated by reference to a multitude of European and North American case studies, backed up by a large number of tables, figures and an extensive bibliography

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

International Nuclear Information System (INIS)

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

1999-01-01

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

Geoenvironmental considerations for assessments of the potential of solid waste disposal in rural Lebanon, Metn-Kesserwan

International Nuclear Information System (INIS)

Nasser, Rima Souheil

1994-02-01

This investigation deals with the problem capitalizing on a mountainous area in Lebanon, and allocating potential sanitary landfill sites for solid waste disposal. The current solid waste management scheme is studied through questionnaires distributed to the community, and field investigations on the operation and effects of the final dump sites. The assessment of the potential for solid waste disposal is approached through evaluating the general suitability of that area for sanitary land filling. This is done by studying various socio-economic and technical parameters on both existing dump sites and others that are here proposed. The environmental impacts of existing dump sites are also described; a modified drastic scheme is used to assess potential ground water pollution in these sites. All of the sites ranked high with respect to their potential pollution of ground water. This is mainly due to their being located directly over highly fractured and karstified limestones. Four areas that proved favourable, in suitability analysis, for solid waste disposal are further subjected to geotechnical investigations to arrive at their capability for sanitary land filling. These include permeability, texture, particle density, Atterberg limits, organic content, clay content and type. As a result of capability analysis, the four sites are ranked from most to least capable for sanitary land filling, according to a quantified weighted rating scale. Sanitary land filling is thus proposed. Solid waste disposal, however, must be followed through an integrated management approach which includes, in addition to land filling, composting, incineration and recycling in a comprehensive waste management scheme. These alternatives are discussed in view of their advantages and disadvantages

Performance assessment strategy for low-level waste disposal sites

International Nuclear Information System (INIS)

Starmer, R.J.; Deering, L.G.; Weber, M.F.

1988-01-01

This paper describes US Nuclear Regulatory Commission (NRC) staff views on predicting the performance of low-level radioactive waste disposal facilities. Under the Atomic Energy Act, as amended, and the Low Level Radioactive Waste Policy Act, as amended, the NRC and Agreement States license land disposal of low-level radioactive waste (LLW) using the requirements in 10 CFR Part 61 or comparable state requirements. The purpose of this paper is to briefly describe regulatory requirements for performance assessment in low-level waste licensing, a strategy for performance assessments to support license applications, and NRC staff licensing evaluation of performance assessments. NRC's current activities in developing a performance assessment methodology will provide an overall systems modeling approach for assessing the performance of LLW disposal facilities. NRC staff will use the methodology to evaluate performance assessments conducted by applicants for LLW disposal facilities. The methodology will be made available to states and other interested parties

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

International Nuclear Information System (INIS)

Tasaka, Hiroshi; Kiyose, Ryohei

1980-01-01

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

Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

International Nuclear Information System (INIS)

Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

1997-01-01

Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

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

International Nuclear Information System (INIS)

1997-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

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

Long-term surveillance plan for the Shiprock disposal site, Shiprock, New Mexico

International Nuclear Information System (INIS)

1993-12-01

The long-term surveillance plan (LTSP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Shiprock disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. This Shiprock, New Mexico, LTSP documents whether the land and interests are owned by the US or an Indian tribe and describes in detail the long-term care program through the UMTRA Project Office

Long-term surveillance plan for the Shiprock Disposal site, Shiprock, New Mexico

International Nuclear Information System (INIS)

1994-09-01

The long-term surveillance plan (LTSP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Shiprock disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents the land ownership interests and details how the long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)

Radioactive waste disposal: an international law perspective

International Nuclear Information System (INIS)

Barrie, G.N.

1989-01-01

The question of radioactive waste disposal is the most intractable technical and political problem facing nuclear industry. Environmentalists world-wide demand a nuclear waste policy that must be ecologically acceptable internationally. Radioactive wastes and oil pollution were the first two types of marine pollution to receive international attention and various marine pollution controls were established. Ocean disposal was co-ordinated by the Nuclear Energy Agency and the Organization of Economic Co-operation and Development in 1967. The first treaty was the 1958 Convention on the High Seas (High Seas Convention). In response to its call for national co-operation the International Atomic Energy Agency (IAEA) established its Brynielson panel. The IAEA first issued guidelines on sea dumping in 1961. The London Dumping Convention, written in 1972, is the only global agreement concerned solely with the disposal of wastes in the marine environment by dumping. None of the global agreements make specific reference to sea-bed disposal of high-level radioactive wastes. Negotiations began at the Third UN Conference on the Law of the Sea (UNCLOS III) for the codification of a comprehensive treaty concerned with the protection, conservation, sustainable use and development of the marine environment. Burial in deep geological formations is a method of HLW disposal which decreases the chances of accidental intrusion by mankind and has little likelihood of malicious intrusion. National waste management programmes of different countries differ but there is agreement on the acceptable technical solutions to issues of waste management. The final disposition of HLW - storage or disposal - has not been decisively determined, but there is growing consensus that geological land-based disposal is the most viable alternative. Expanded international technical co-operation could well reduce the time needed to develop effective waste disposal mechanisms

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

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

International Nuclear Information System (INIS)

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

1988-01-01

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

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

International Nuclear Information System (INIS)

Di Sanza, E.F.; Carilli, J.T.

2006-01-01

Waste Acceptance Criteria. The disposal operations previously mentioned take place at the NTS in two disposal facilities. The isolation protection and overall performance of the two LLW disposal facilities at the NTS transcend those of any federal radioactive waste disposal site in the United States. The first of the two disposal sites is the Area 5 Radioactive Waste Management Site (RWMS) which is situated on alluvial fan deposits in the Frenchman Flat basin, approximately 770 feet (235 meters) above the water table. The Area 5 RWMS utilizes a combination of engineered shallow land disposal cells and deep augured shafts for the disposal of a variety of waste streams. Fifteen miles (24 kilometers) north of the Area 5 RWMS is the Area 3 RWMS located approximately 1,600 feet (488 meters) above the water table in Yucca Flat. Disposal activities at the Area 3 RWMS center around the placement of bulk LLW in subsidence craters formed from underground testing of nuclear weapons. Native alluvium soil is used to cover waste placed in the disposal cells at both facilities. In addition, information on the technical attributes, facility performance, updates on waste disposal volumes and capabilities, and current and future disposal site requirements will also be described. (authors)

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

International Nuclear Information System (INIS)

1997-05-01

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

Long-term surveillance plan for the Green River, Utah disposal site. Revision 2

International Nuclear Information System (INIS)

1998-07-01

The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out

Licensing of alternative methods of disposal of low-level radioactive waste: Branch technical position, Low-Level Waste Licensing Branch

International Nuclear Information System (INIS)

Higginbotham, L.B.; Dragonette, K.S.; Pittiglio, C.L. Jr.

1986-12-01

This branch technical position statement identifies and describes specific methods of disposal currently being considered as alternatives to shallow land burial, provides general guidance on these methods of disposal, and recommends procedures that will improve and simplify the licensing process. The statement provides answers to certain questions that have arisen regarding the applicability of 10 CFR 61 to near-surface disposal of waste, using methods that incorporate engineered barriers or structures, and other alternatives to conventional shallow land burial disposal practices. This position also identifies a recently published NRC contractor report that addresses the applicability of 10 CFR 61 to a range of generic disposal concepts and which provides technical guidance that the staff intends to use for these concepts. This position statement combined with the above-mentioned NRC contractor report fulfills the requirements of Section 8(a) of Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985

Subseabed Disposal Program Plan. Volume I. Overview

International Nuclear Information System (INIS)

1981-07-01

The primary objective of the Subseabed Disposal Program (SDP) is to assess the scientific, environmental, and engineering feasibility of disposing of processed and packaged high-level nuclear waste in geologic formations beneath the world's oceans. High-level waste (HLW) is considered the most difficult of radioactive wastes to dispose of in oceanic geologic formations because of its heat and radiation output. From a scientific standpoint, the understanding developed for the disposal of such HLW can be used for other nuclear wastes (e.g., transuranic - TRU - or low-level) and materials from decommissioned facilities, since any set of barriers competent to contain the heat and radiation outputs of high-level waste will also contain such outputs from low-level waste. If subseabed disposal is found to be feasible for HLW, then other factors such as cost will become more important in considering subseabed emplacement for other nuclear wastes. A secondary objective of the SDP is to develop and maintain a capability to assess and cooperate with the seabed nuclear waste disposal programs of other nations. There are, of course, a number of nations with nuclear programs, and not all of these nations have convenient access to land-based repositories for nuclear waste. Many are attempting to develop legislative and scientific programs that will avoid potential hazards to man, threats to other ocean uses, and marine pollution, and they work together to such purpose in meetings of the international NEA/Seabed Working Group. The US SDP, as the first and most highly developed R and D program in the area, strongly influences the development of subseabed-disposal-related policy in such nations

Sewage sludge pretreatment and disposal. (Latest citations from the NTIS bibliographic database). Published Search

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The bibliography contains citations concerning techniques and equipment used in the pretreatment and disposal of sewage sludges. Citations discuss sludge digestion, dewatering, disinfection, stabilization, chlorination, and desulfurization. Topics include pretreatment programs, land disposal, incineration, and waste utilization. Environmental monitoring and protection, federal regulations, and legal aspects are examined. (Contains 50-250 citations and includes a subject term index and title list.)

Ground-water quality beneath solid-waste disposal sites at anchorage, Alaska

Science.gov (United States)

Zenone, Chester; Donaldson, D.E.; Grunwaldt, J.J.

1975-01-01

Studies at three solid-waste disposal sites in the Anchorage area suggest that differences in local geohydrologic conditions influence ground-water quality. A leachate was detected in ground water within and beneath two sites where the water table is very near land surface and refuse is deposited either at or below the water table in some parts of the filled areas. No leachate was detected in ground water beneath a third site where waste disposal is well above the local water table.

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

Design, placement, and sampling of groundwater monitoring wells for the management of hazardous waste disposal facilities

International Nuclear Information System (INIS)

Tsai, S.Y.

1988-01-01

Groundwater monitoring is an important technical requirement in managing hazardous waste disposal facilities. The purpose of monitoring is to assess whether and how a disposal facility is affecting the underlying groundwater system. This paper focuses on the regulatory and technical aspects of the design, placement, and sampling of groundwater monitoring wells for hazardous waste disposal facilities. Such facilities include surface impoundments, landfills, waste piles, and land treatment facilities. 8 refs., 4 figs

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

Technical and socio-political issues in radioactive waste disposal 1986. Vol. 2

International Nuclear Information System (INIS)

Parker, F.L.; Kasperson, R.E.; Andersson, T.L.; Parker, S.A.

1987-11-01

Subseabed disposal of high level radioactive waste and spent fuel, in contrast to land based mined geologic repositories, has not yet been judged by any nation or international bodies to be technologically acceptable, but it is presently considered to be the only available alternative to land based geologic disposal. The work under the scientific program for subseabed disposal the most truly international of all the radioactive waste program, was proceeding along a well defined route to proof or rejection of concept. This date will certainly be delayed because of the withdrawal of the USA from the program. The work under the aegis of the NEA will result in a report in 1987 that will be a status report. To date no scientific information has emerged that would negate the advantages of the subseabed disposal method. Validation of some of the models has not been completed. The option, if possible, would be very attractive for many reasons including no easy direct exposure to man, no contamination of potential drinking water supplies, no near neighbors, an international solution rather than a parochial solution, and location in a formation with highly desirable attributes (stability, exchange capacity, etc.) that may not be available in every nation with a nuclear energy program. Even if the scientific feasibility were proven, then there still remain enormous institutional obstacles to be overcome including the determined opposition of many countries on ecological and philosophical grounds, the existence of international treaties that appear to prohibit such disposal and the fact that it is not the first choice for disposal of spent nuclear fuel or high level radioactive waste. (orig./HP)

Coordination of groundwater activities in the 100 N Area

International Nuclear Information System (INIS)

Hartman, M.J.

1995-09-01

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

Long-term surveillance plan for the Green River, Utah, disposal site

International Nuclear Information System (INIS)

1997-06-01

The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out. The Green River, Utah, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)

Long-term surveillance plan for the Collins Ranch Disposal Site, Lakeview, Oregon

International Nuclear Information System (INIS)

1993-12-01

This long-term surveillance plan (LTSP) for the Lakeview, Oregon, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lakeview (Collins Ranch) disposal cell, which will be referred to as the Collins Ranch disposal cell throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and details how the long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)

Ocean disposal option for bulk wastes containing naturally occurring radionuclides: an assessment case history

International Nuclear Information System (INIS)

Stull, E.A.; Merry-Libby, P.

1985-01-01

There are 180,000 m 3 of slightly contaminated radioactive wastes (36 pCi/g radium-226) currently stored at the US Department of Energy's Niagara Falls Storage Site (NFSS), near Lewiston, New York. These wastes resulted from the cleanup of soils that were contaminated above the guidelines for unrestricted use of property. An alternative to long-term management of these wastes on land is dispersal in the ocean. A scenario for ocean disposal is presented for excavation, transport, and emplacement of these wastes in an ocean disposal site. The potential fate of the wastes and impacts on the ocean environment are analyzed, and uncertainties in the development of two worst-case scenarios for dispersion and pathway analyses are discussed. Based on analysis of a worst-case pathway back to man, the incremental dose from ingesting fish containing naturally occurring radionuclides from ocean disposal of the NFSS wastes is insignificant. Ocean disposal of this type of waste appears to be a technically promising alternative to the long-term maintenance costs and eventual loss of containment associated with management in a near-surface land burial facility

Long-term surveillance plan for the Mexican Hat disposal site, Mexican Hat, Utah

International Nuclear Information System (INIS)

1996-01-01

This plan describes the long-term surveillance activities for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Mexican Hat, Utah. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This long-term surveillance plan (LTSP) was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive material (RRM). This LTSPC documents the land ownership interests and details how the long-term care of the disposal site will be accomplished

Long-term surveillance plan for the Collins Ranch disposal site, Lakeview, Oregon

International Nuclear Information System (INIS)

1994-08-01

This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Collins Ranch disposal site, Lakeview, Oregon, describes the surveillance activities for the disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)

Geodiametris: an integrated geoinformatic approach for monitoring land pollution from the disposal of olive oil mill wastes

Science.gov (United States)

Alexakis, Dimitrios D.; Sarris, Apostolos; Papadopoulos, Nikos; Soupios, Pantelis; Doula, Maria; Cavvadias, Victor

2014-08-01

The olive-oil industry is one of the most important sectors of agricultural production in Greece, which is the third in olive-oil production country worldwide. Olive oil mill wastes (OOMW) constitute a major factor in pollution in olivegrowing regions and an important problem to be solved for the agricultural industry. The olive-oil mill wastes are normally deposited at tanks, or directly in the soil or even on adjacent torrents, rivers and lakes posing a high risk to the environmental pollution and the community health. GEODIAMETRIS project aspires to develop integrated geoinformatic methodologies for performing monitoring of land pollution from the disposal of OOMW in the island of Crete -Greece. These methodologies integrate GPS surveys, satellite remote sensing and risk assessment analysis in GIS environment, application of in situ and laboratory geophysical methodologies as well as soil and water physicochemical analysis. Concerning project's preliminary results, all the operating OOMW areas located in Crete have been already registered through extensive GPS field campaigns. Their spatial and attribute information has been stored in an integrated GIS database and an overall OOMW spectral signature database has been constructed through the analysis of multi-temporal Landsat-8 OLI satellite images. In addition, a specific OOMW area located in Alikianos village (Chania-Crete) has been selected as one of the main case study areas. Various geophysical methodologies, such as Electrical Resistivity Tomography, Induced Polarization, multifrequency electromagnetic, Self Potential measurements and Ground Penetrating Radar have been already implemented. Soil as well as liquid samples have been collected for performing physico-chemical analysis. The preliminary results have already contributed to the gradual development of an integrated environmental monitoring tool for studying and understanding environmental degradation from the disposal of OOMW.

From disposal at sea to distribution of oil-based cuttings

International Nuclear Information System (INIS)

Boehm, J.T.C.; Laan, L.V.D.

1994-01-01

The environmental impact of cutting discharges has led to a significant change in the way oilbased mud has been used at the Dutch Continental Shelf (DCS). The industry has converted from direct disposal of oilbased cuttings to a zero oil disposal at sea by transfer of cuttings to land. Moreover, distillation of cuttings has resulted in a closed-loop application of the base oil. This method has been developed as a standard operation even before the zero oil disposal limit became effective in 1993. Although the well costs have increased with 2.5% as a result of the new requirement, the extra costs amount to only a small fraction of the extra well costs if only waterbased mud would be allowed. Both industry and environment benefit and it has resulted in an increased use of oilbased mud since 1991 at the DCS. Further scope for reduction of environmental impact related to waste disposal is limited. The remaining concerns are related to the prevention of oil spills

A data base for low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Daum, M.L.; Moskowitz, P.D.

1989-07-01

A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs