Tank waste remediation system program plan

Energy Technology Data Exchange (ETDEWEB)

Powell, R.W.

1998-01-05

This program plan establishes the framework for conduct of the Tank Waste Remediation System (TWRS) Project. The plan focuses on the TWRS Retrieval and Disposal Mission and is specifically intended to support the DOE mid-1998 Readiness to Proceed with Privatized Waste Treatment evaluation for establishing firm contracts for waste immobilization.

Sampling and analysis plan for remediation of Operable Unit 100-IU-3 waste site 600-104

International Nuclear Information System (INIS)

1997-08-01

This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities to support remediation of 100-IU-3 Operable Unit waste site 600-104. The purpose of the proposed sampling and analysis activities is to demonstrate that time-critical remediation of the waste site for soil containing 2,4-Dichlorophonoxyacetic acid salts and esters (2,4-D) and dioxin/furan isomers at concentrations that exceed cleanup levels has been effective. This shall be accomplished by sampling various locations of the waste site before and after remediation, analyzing the samples, and comparing the results to action levels set by the Washington State Department of Ecology

Department of Energy Hazardous Waste Remedial Actions Program

International Nuclear Information System (INIS)

Franco, P.J.

1989-01-01

This paper discusses the hazardous waste remedial actions program (HAZWRAP) which manages approximately 200 hazardous waste projects. These projects include preliminary assessments, site inspections, and remedial investigation/feasibility studies. The author describes the procedures HAZWRAP follows to ensure quality. The discussion covers the quality assurance aspects of project management, project planning, site characterization, document control and technical teamwork

Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

Energy Technology Data Exchange (ETDEWEB)

Wilmarth, William R.; Lumetta, Gregg J.; Johnson, Michael E.; Poirier, Micheal R.; Thompson, Major C.; Suggs, Patricia C.; Machara, N.

2011-01-13

The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste that has been generated during the production of nuclear weapons in the United States. The vast bulk of this waste material is stored in underground tanks at the Savannah River Site in South Carolina and the Hanford Site in Washington State. The general strategy for treating the radioactive tank waste consists of first separating the waste into high-level and low-activity fractions. This initial partitioning of the waste is referred to as pretreatment. Following pretreatment, the high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for disposal at the respective site. This paper provides a review of recent developments in the application of pretreatment technologies to the processing of the Hanford and Savannah River radioactive tank wastes. Included in the review are discussions of 1) solid/liquid separations methods, 2) cesium separation technologies, and 3) other separations critical to the success of the DOE tank waste remediation effort. Also included is a brief discussion of the different requirements and circumstances at the two DOE sites that have in some cases led to different choices in pretreatment technologies.

Radioactive Tank Waste Remediation Focus Area. Technology summary

International Nuclear Information System (INIS)

1995-06-01

In February 1991, DOE's Office of Technology Development created the Underground Storage Tank Integrated Demonstration (UST-ID), to develop technologies for tank remediation. Tank remediation across the DOE Complex has been driven by Federal Facility Compliance Agreements with individual sites. In 1994, the DOE Office of Environmental Management created the High Level Waste Tank Remediation Focus Area (TFA; of which UST-ID is now a part) to better integrate and coordinate tank waste remediation technology development efforts. The mission of both organizations is the same: to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. The TFA has focused on four DOE locations: the Hanford Site in Richland, Washington, the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho, the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site (SRS) in Aiken, South Carolina

Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan

International Nuclear Information System (INIS)

G. L. Schwendiman

2006-01-01

This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition

Radioactive tank waste remediation focus area

International Nuclear Information System (INIS)

1996-08-01

EM's Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form

Radioactive tank waste remediation focus area

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

EM`s Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form.

Waste area Grouping 2 Phase I remedial investigation: Sediment and Cesium-137 transport modeling report

International Nuclear Information System (INIS)

Clapp, R.B.; Bao, Y.S.; Moore, T.D.; Brenkert, A.L.; Purucker, S.T.; Reece, D.K.; Burgoa, B.B.

1996-06-01

This report is one of five reports issued in 1996 that provide follow-up information to the Phase I Remedial Investigation (RI) Report for Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL). The five reports address areas of concern that may present immediate risk to public health at the Clinch River and ecological risk within WAG 2 at ORNL. A sixth report, on groundwater, in the series documenting WAG 2 RI Phase I results were part of project activities conducted in FY 1996. The five reports that complete activities conducted as part of Phase I of the Remedial Investigation (RI) for WAG 2 are as follows: (1) Waste Area Grouping 2, Phase I Task Data Report: Seep Data Assessment, (2) Waste Area Grouping 2, Phase I Task Data Report: Tributaries Data Assessment, (3) Waste Area Grouping 2, Phase I Task Data Report: Ecological Risk Assessment, (4) Waste Area Grouping 2, Phase I Task Data Report: Human Health Risk Assessment, (5) Waste Area Grouping 2, Phase I Task Data Report: Sediment and 137 Cs Transport Modeling In December 1990, the Remedial Investigation Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory was issued (ORNL 1990). The WAG 2 RI Plan was structured with a short-term component to be conducted while upgradient WAGs are investigated and remediated, and a long-term component that will complete the RI process for WAG 2 following remediation of upgradient WAGs. RI activities for the short-term component were initiated with the approval of the Environmental Protection Agency, Region IV (EPA), and the Tennessee Department of Environment and Conservation (TDEC). This report presents the results of an investigation of the risk associated with possible future releases of 137 Cs due to an extreme flood. The results are based on field measurements made during storms and computer model simulations

Communication activities during remediation project of Zavratec

International Nuclear Information System (INIS)

Kukovica, T.; Mele, I.

1996-01-01

The remediation project of temporary storage of radioactive waste near village Zavratec is under way. The Agency for Radwaste Management was assigned to perform this project by the Slovenian government. Radioactive waste was stored on site of Zavratec in 1961. That year an accident has occurred at Oncological institute in Ljubljana in which several rooms and some equipment have been contaminated by the content of radium applicator. Radioactive waste from decontamination was transported and stored in an old Italian military barrack near village Zavratec. The storage became known to public in eighties by the TV report. Since that time it is frequently the subject of public polemics and discussions. This year the first part of remediation project, i.e. the activity measurements and sorting of radioactive waste is taking place. It is planned to conclude the project next year. For successful realization of the project the PR activities, specially the communication with the local community, are of great importance. Special plan of these activities has been prepared by the Agency for Radwaste Management in early stage of the project. Initial activities have already been successfully realized. In this paper the communication plan is presented and most important elements of this plan are briefly described. (author)

Integrated approach to hazardous and radioactive waste remediation

International Nuclear Information System (INIS)

Hyde, R.A.; Reece, W.J.

1994-01-01

The US Department of Energy Office of Technology Development is supporting the demonstration, and evaluation of a suite of waste retrieval technologies. An integration of leading-edge technologies with commercially available baseline technologies will form a comprehensive system for effective and efficient remediation of buried waste throughout the complex of DOE nuclear facilities. This paper discusses the complexity of systems integration, addressing organizational and engineering aspects of integration as well as the impact of human operators, and the importance of using integrated systems in remediating buried hazardous and radioactive waste

Object reasoning for waste remediation

International Nuclear Information System (INIS)

Pennock, K.A.; Bohn, S.J.; Franklin, A.L.

1991-08-01

A large number of contaminated waste sites across the United States await size remediation efforts. These sites can be physically complex, composed of multiple, possibly interacting, contaminants distributed throughout one or more media. The Remedial Action Assessment System (RAAS) is being designed and developed to support decisions concerning the selection of remediation alternatives. The goal of this system is to broaden the consideration of remediation alternatives, while reducing the time and cost of making these considerations. The Remedial Action Assessment System is a hybrid system, designed and constructed using object-oriented, knowledge- based systems, and structured programming techniques. RAAS uses a combination of quantitative and qualitative reasoning to consider and suggest remediation alternatives. The reasoning process that drives this application is centered around an object-oriented organization of remediation technology information. This paper describes the information structure and organization used to support this reasoning process. In addition, the paper describes the level of detail of the technology related information used in RAAS, discusses required assumptions and procedural implications of these assumptions, and provides rationale for structuring RAAS in this manner. 3 refs., 3 figs

Tank waste remediation system retrieval and disposal mission waste feed delivery plan

International Nuclear Information System (INIS)

Potter, R.D.

1998-01-01

This document is a plan presenting the objectives, organization, and management and technical approaches for the Waste Feed Delivery (WFD) Program. This WFD Plan focuses on the Tank Waste Remediation System (TWRS) Project's Waste Retrieval and Disposal Mission

Sampling and analysis plan for remediation of Operable Unit 100-IU-3 waste site 600-104. Revision 1

International Nuclear Information System (INIS)

1997-08-01

This sampling and analysis plan presents the rationale and strategy for the sampling and analysis activities to support remediation of 100-IU-3 Operable Unit waste site 600-104. The purpose of the proposed sampling and analysis activities is to demonstrate that time-critical remediation of the waste site for soil containing 2,4-Dichlorophenoxyacetic acid salts and esters (2,4-D) and dioxin/furan isomers at concentrations that exceed cleanup levels has been effective. This shall be accomplished by sampling various locations of the waste site before and after remediation, analyzing the samples, and comparing the results to action levels set by the Washington State Department of Ecology

An overview of the hazardous waste remedial actions program: hazardous and mixed waste activities for the U.S. Departments of energy and defense

International Nuclear Information System (INIS)

Craig, Robert B.; Rothermich, Nancy E.

1991-01-01

In May 1987 all mixed waste generated at the U.S. Department of Energy (DOE) facilities became jointly regulated by the U.S. Environmental Protection Agency (EPA) and DOE. The Department of Defense (DOD) generates hazardous wastes and is also regulated by the EPA. To maintain or attain compliance, both DOE and DOD have initiated compliance activities on all hazardous and mixed waste streams. This compliance includes the development of innovative technologies and processes to avoid the generation of hazardous and mixed wastes, development of technologies to treat the process wastes that are unavoidably generated, development of technologies to restore the environment where wastes have been released to the environment, the cleanup of asbestos and the monitoring of radon in federal facilities, the completion of remedial investigation/feasibility studies, and development of the data systems that are necessary to compile this information. This paper will describe each of these activities as they relate to compliance with the Resource Conservation and Recovery Act and/or CERCLA and their implementing regulations

Department of Energy hazardous waste remedial actions program: Quality assurance program

International Nuclear Information System (INIS)

Horne, T.E.

1988-01-01

This paper describes the Quality Assurance Program developed for the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAP SCO). Key topics discussed include an overview of the HAZWRAP SCO mission and organization, the basic quality assurance program requirements and the requirements for the control of quality for the Department of Energy and Work for Others hazardous waste management programs, and the role of ensuring quality through the project team concept for the management of remedial response actions. The paper focuses on planning for quality assurance for this remedial waste management process from preliminary assessments of remedial sites to feasibility studies. Some observations concerning the control of quality during the implementation of remedial actions are presented. (2 refs.)

Remedial Action and Waste Disposal Project Manager's Implementing Instructions

International Nuclear Information System (INIS)

Dronen, V.R.

1998-01-01

These Project Manager's Implementing Instructions provide the performance standards required of all Environmental Restoration Contractor personnel in their work during operation and administration of the Remedial Action and Waste Disposal Project. The instructions emphasize technical competency, workplace discipline, and personal accountability to ensure a high level of safety and performance during operations activities

REAL TIME DATA FOR REMEDIATION ACTIVITIES (11505)

International Nuclear Information System (INIS)

Brock, C.T.

2011-01-01

Health physicists from the CH2M HILL Plateau Remediation Company collaborated with Berkeley Nucleonics Corporation to modify the SAM 940 isotope identifier instrument to be used for nuclear waste remediation. These modifications coupled with existing capabilities of the SAM 940 have proven to be invaluable during remediation activities, reducing disposal costs by allowing swift remediation of targeted areas that have been identified as having isotopes of concern (IOC), and eliminating multiple visits to sites by declaring an excavation site clear of IOCs before demobilizing from the site. These advantages are enabled by accumulating spectral data for specific isotopes that is nearly 100 percent free of false positives, which are filtered out in 'real time.'

Tank waste remediation system dangerous waste training plan

International Nuclear Information System (INIS)

POHTO, R.E.

1999-01-01

This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench

Methodology to remediate a mixed waste site

International Nuclear Information System (INIS)

Berry, J.B.

1994-08-01

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

Methodology to remediate a mixed waste site

Energy Technology Data Exchange (ETDEWEB)

Berry, J.B.

1994-08-01

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

Flammable gas deflagration consequence calculations for the tank waste remediation system basis for interim operation

Energy Technology Data Exchange (ETDEWEB)

Van Vleet, R.J., Westinghouse Hanford

1996-08-13

This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.The attached SD documents the originator`s analysis only. It shall not be used as the final or sole document for effecting changes to an authorization basis or safety basis for a facility or activity.

Environmental Impact and Remediation of Uranium Tailings and Waste Rock Dumps at Mailuu-Suu in Kyrgyzstan

International Nuclear Information System (INIS)

Kunze, C.; Walter, U.; Wagner, F.; Schmidt, P.; Barnekow, U.; Gruber, A.

2011-01-01

This paper describes the environmental situation in the former uranium mining and milling region of Mailuu-Suu (Kyrgyzstan), the approach to environmental remediation of the waste facilities (tailings ponds and waste dumps) and the results achieved so far. It starts with an outline of the history of the environmental remediation project which has received international attention and is seen as a pilot project for further remediation activities of former uranium mining and milling sites in the region. Apart from technical aspects, the paper draws conclusions with respect to the administrative environment, institutional capacity building and the local availability of resources needed to successfully implement a complex remediation project. (author)

Tank waste remediation system risk management plan

International Nuclear Information System (INIS)

Zimmerman, B.D.

1998-01-01

The purpose of the Tank Waste Remediation System (TWRS) Risk Management Plan is to describe a consistent approach to risk management such that TWRS Project risks are identified and managed to achieve TWRS Project success. The Risk Management Plan implements the requirements of the Tank Waste Remediation System Systems Engineering Management Plan in the area of risk management. Figure ES-1 shows the relationship of the TWRS Risk Management Plan to other major TWRS Project documents. As the figure indicates, the Risk Management Plan is a tool used to develop and control TWRS Project work. It provides guidance on how TWRS Project risks will be assessed, analyzed, and handled, and it specifies format and content for the risk management lists, which are a primary product of the risk management process. In many instances, the Risk Management Plan references the TWRS Risk Management Procedure, which provides more detailed discussion of many risk management activities. The TWRS Risk Management Plan describes an ongoing program within the TWRS Project. The Risk Management Plan also provides guidance in support of the TWRS Readiness To-Proceed (RTP) assessment package

Project Strategy For The Remediation And Disposition Of Legacy Transuranic Waste At The Savannah River Site, South Carolina, USA

International Nuclear Information System (INIS)

Rodriguez, M.

2010-01-01

This paper discusses the Savannah River Site Accelerated Transuranic (TRU) Waste Project that was initiated in April of 2009 to accelerate the disposition of remaining legacy transuranic waste at the site. An overview of the project execution strategy that was implemented is discussed along with the lessons learned, challenges and improvements to date associated with waste characterization, facility modifications, startup planning, and remediation activities. The legacy waste was generated from approximately 1970 through 1990 and originated both on site as well as at multiple US Department of Energy sites. Approximately two thirds of the waste was previously dispositioned from 2006 to 2008, with the remaining one third being the more hazardous waste due to its activity (curie content) and the plutonium isotope Pu-238 quantities in the waste. The project strategy is a phased approach beginning with the lower activity waste in existing facilities while upgrades are made to support remediation of the higher activity waste. Five waste remediation process lines will be used to support the full remediation efforts which involve receipt of the legacy waste container, removal of prohibited items, venting of containers, and resizing of contents to fit into current approved waste shipping containers. Modifications have been minimized to the extent possible to meet the accelerated goals and involve limited upgrades to address life safety requirements, radiological containment needs, and handling equipment for the larger waste containers. Upgrades are also in progress for implementation of the TRUPACT III for the shipment of Standard Large Boxes to the Waste Isolation Pilot Plant, the US TRU waste repository. The use of this larger shipping container is necessary for approximately 20% of the waste by volume due to limited size reduction capability. To date, approximately 25% of the waste has been dispositioned, and several improvements have been made to the overall processing

Tank Farm Contractor Waste Remediation System and Utilization Plan

International Nuclear Information System (INIS)

KIRKBRIDE, R.A.

1999-01-01

The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy

FY-95 technology catalog. Technology development for buried waste remediation

International Nuclear Information System (INIS)

1995-01-01

The US Department of Energy's (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described

FY-95 technology catalog. Technology development for buried waste remediation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

The US Department of Energy`s (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described.

Waste Management Plan for the Lower East Fork Poplar Creek Remedial Action Project Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

The Lower East Fork Poplar Creek (LEFPC) Remedial Action project will remove mercury-contaminated soils from the floodplain of LEFPC, dispose of these soils at the Y-12 Landfill V, and restore the affected floodplain upon completion of remediation activities. This effort will be conducted in accordance with the Record of Decision (ROD) for LEFPC as a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) action. The Waste Management Plan addresses management and disposition of all wastes generated during the remedial action for the LEFPC Project Most of the solid wastes will be considered to be sanitary or construction/demolition wastes and will be disposed of at existing Y-12 facilities for those types of waste. Some small amounts of hazardous waste are anticipated, and the possibility of low- level or mixed waste exists (greater than 35 pCi/g), although these are not expected. Liquid wastes will be generated which will be sanitary in nature and which will be capable of being disposed 0214 of at the Oak Ridge Sewage Treatment Plant.

Waste Management Plan for the Lower East Fork Poplar Creek Remedial Action Project Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-08-01

The Lower East Fork Poplar Creek (LEFPC) Remedial Action project will remove mercury-contaminated soils from the floodplain of LEFPC, dispose of these soils at the Y-12 Landfill V, and restore the affected floodplain upon completion of remediation activities. This effort will be conducted in accordance with the Record of Decision (ROD) for LEFPC as a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) action. The Waste Management Plan addresses management and disposition of all wastes generated during the remedial action for the LEFPC Project Most of the solid wastes will be considered to be sanitary or construction/demolition wastes and will be disposed of at existing Y-12 facilities for those types of waste. Some small amounts of hazardous waste are anticipated, and the possibility of low- level or mixed waste exists (greater than 35 pCi/g), although these are not expected. Liquid wastes will be generated which will be sanitary in nature and which will be capable of being disposed 0214 of at the Oak Ridge Sewage Treatment Plant

Fifth international conference on radioactive waste management and environmental remediation -- ICEM '95: Proceedings. Volume 2: Management of low-level waste and remediation of contaminated sites and facilities

International Nuclear Information System (INIS)

Slate, S.; Baker, R.; Benda, G.

1995-01-01

The objective of this conference is the broad international exchange of information on technologies, operations, management approaches, economics, and public policies in the critical areas of radioactive waste management and environmental remediation. The ICEM '95 technical program includes four parallel program tracks: Low/intermediate-level waste management; High-level waste, spent fuel, nuclear material management; Environmental remediation and facility D and D; and Major institutional issues in environmental management. Volume 2 contains approximately 200 papers divided into the following topical sections: Characterization of low and intermediate level waste; Treatment of low and intermediate level waste; LLW disposal and near-surface contaminant migration; Characterization and remediation of contaminated sites; and Decontamination and decommissioning technologies and experience. Papers have been processed separately for inclusion on the data base

Remedial action and waste disposal project: 100-B/C remedial action readiness evaluation plan

International Nuclear Information System (INIS)

April, J.G.; Bryant, D.L.; Cislo, G.B.

1996-06-01

The Readiness Evaluation Plan presents the methodology used to assess the readiness of the 100-B/C Remedial Action Project. The 100 Areas Remedial Action Project will remediate the 100 Areas liquid waste site identified in the Interim Action Record of Decision for the 100- BC-1, 100-DR-1, and 100-HR-1 Operable Units. These sites are located in the 100 Area of the Hanford Site in Richland, Washington

Tank Waste Remediation System Projects Document Control Plan

International Nuclear Information System (INIS)

Slater, G.D.; Halverson, T.G.

1994-01-01

The purpose of this Tank Waste Remediation System Projects Document Control Plan is to provide requirements and responsibilities for document control for the Hanford Waste Vitrification Plant (HWVP) Project and the Initial Pretreatment Module (IPM) Project

Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment plan

International Nuclear Information System (INIS)

April, J.G.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Plastino, J.C.; Roeck, F.V.; Tuttle, B.G.

1997-04-01

This Readiness Assessment Plan presents the methodology used to assess the readiness of the 300-FF-1 Remedial Action Project. Remediation involves the excavation, treatment if applicable, and final disposal of contaminated soil and debris associated with the waste sites in the 300-FF-1 Operable Unit. The scope of the 300-FF-1 remediation is to excavate, transport, and dispose of contaminated solid from sites identified in the 300-FF-1 Operable Unit

Surface water management at a mixed waste remediation site

International Nuclear Information System (INIS)

Schlotzhauer, D.S.; Warbritton, K.R.

1991-01-01

The Weldon Spring Remedial Action Project (WSSRAP) deals with chemical and radiological contaminants. MK-Ferguson Company is managing the project under contract with the US Department of Energy. Remedial activities include demolishing buildings, constructing material storage and staging areas, excavating and consolidating waste materials, and treating and disposing of the materials in a land disposal facility. Due to the excavation and construction required during remediation, a well-planned surface water management system is essential. Planning involves characterization of source areas and surface water transport mechanisms and identification of applicable regulations. System components include: erosion control sediment control, flow attenuation, and management of contaminated water. Combinations of these components may be utilized during actual construction and remediation to obtain optimum control. Monitoring is performed during implementation in order to assess the effectiveness of control measures. This management scheme provides for comprehensive management of surface water at this site by providing control and/or treatment to appropriate standards. Although some treatment methodologies for contaminated water are specific to site contaminants, this comprehensive program provides a management approach which is applicable to many remedial projects in order to minimize contaminant release and meet Clean Water Act requirements

Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

International Nuclear Information System (INIS)

Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W.

2013-01-01

A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

Energy Technology Data Exchange (ETDEWEB)

Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W. [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)

2013-07-01

A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

Activities in department of energy hazardous and mixed waste defense waste management

International Nuclear Information System (INIS)

Eyman, L.D.

1988-01-01

In January 1986, the U.S. Department of Energy (DOE) Office of Assistant Secretary for Defense Programs (DP) created the Hazardous Waste and Remedial Actions Division within the Office of Defense Waste and Transportation Management. The Oak Ridge Operations Office (ORO) was assigned the responsibility for supporting DOE Headquarters (HQ) in planning nationally integrated activities for Resource Conservation and Recovery Act/Comprehensive Environmental Response, Compensation, and Liability Act/Superfund Amendments and Reauthorization Act (RCRA/CERCLA/SARA) compliance. In turn, ORO created the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAPSCO) to assist with the expanded lead assignment. The HAZWRAPSCO activities are currently supported by three distinct DOE-HQ funding elements: the Environmental Restoration Program, the Hazardous Waste Compliance Technology Program, and the Hazardous Waste Research and Development R and D Program. The Environmental Restoration Program is discussed in the paper, entitled The DOE Defense Program for Environmental Restoration

Remedial action and waste disposal project: 100-DR-1 remedial action readiness evaluation plan

International Nuclear Information System (INIS)

April, J.G.; Bryant, D.L.; Calverley, C.

1996-08-01

This plan presents the method used to assess the readiness of the 100- DR-1 Remedial Action Project. Remediation of the 100-D sites (located on the Hanford Site) involves the excavation (treatment if applicable) and final disposal of contaminated soil and debris associated with the high-priority waste sites in the 100 Areas

Rail transportation of Fernald remediation waste

International Nuclear Information System (INIS)

Fellman, R.T.; Lojek, D.A.; Motl, G.P.; Weddendorf, W.K.

1995-01-01

Remediation of the Department of Energy (DOE) Fernald site located north of Cincinnati will generate large quantities of low-level radwaste. This volume includes approximately 1,050,000 tons of material to be removed from eight waste pits comprising Operable Unit 1 (OU-1). The remedial alternative selected includes waste material excavation, drying and transportation by rail to a burial site in the arid west for disposal. Rail transportation was selected not only because rail transportation is safer than truck transportation, but also because of the sheer magnitude of the project and the availability of bulk rail car unloading facilities at a representative disposal site. Based upon current waste quantity estimates as presented in the Feasibility Study for OUI, a fully-loaded 47-car unit train would depart the Fernald site weekly for five years. This paper illustrates the steps taken to obtain agency and public acceptance of the Record of Decision for the remedy which hinged on rail transportation. A preliminary, but detailed, rail transportation plan was prepared for the project to support a series of CERCLA public meetings conducted in late 1994. Some of the major issues addressed in the plan included the following: (1) Scope of project leading to selection of rail transportation; (2) Waste classification; (3) Rail Company overview; (4) Train configuration and rail car selection; (5) Routing; (6) Safety; (7) Prior Notification Requirements (8) Emergency Response. A series of three public meetings identified a number of issues of prime concern to Fernald stakeholders. Following resolution of these issues during the public comment period, a Record of Decision (ROD) approving implementation of the rail transportation strategy was approved pending incorporation of EPA and State of Ohio comments on December 22, 1994

Tank waste remediation system optimized processing strategy with an altered treatment scheme

International Nuclear Information System (INIS)

Slaathaug, E.J.

1996-03-01

This report provides an alternative strategy evolved from the current Hanford Site Tank Waste Remediation System (TWRS) programmatic baseline for accomplishing the treatment and disposal of the Hanford Site tank wastes. This optimized processing strategy with an altered treatment scheme performs the major elements of the TWRS Program, but modifies the deployment of selected treatment technologies to reduce the program cost. The present program for development of waste retrieval, pretreatment, and vitrification technologies continues, but the optimized processing strategy reuses a single facility to accomplish the separations/low-activity waste (LAW) vitrification and the high-level waste (HLW) vitrification processes sequentially, thereby eliminating the need for a separate HLW vitrification facility

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

Environmental remediation activities at WISMUT GmbH, Germany

International Nuclear Information System (INIS)

Saito, Hiroshi; Takahashi, Kuniaki; Miyasaka, Yasuhiko; Yamana, Hajimu

2007-01-01

The WISMUT GmbH has carried out environmental remediation activities since 1991 in former GDR (German Democratic Republic) to rehabilitate the environment and landscape which have been adversely affected by decades of unrestrained mining and processing of uranium ores. It is worthy of being mentioned especially that WISMUT GmbH's sites including waste rock dump, mill tailings pond, open pit mine and water treatment facilities with an area of 3,700ha have been rehabilitated practically and extensively, and these activities are planned to terminate in 2015 except for the water treatment. For safety assessment after remediation, the value of 1mSv/y (in excess of the background level) is applied to as an individual effective dose, from the recommendation of ICRP (International Commission on Radiological Protection). This report shows a summary of environmental remediation activities carried out by the WISMUT GmbH and related regulatory laws. (author)

Multivariate methods in nuclear waste remediation: Needs and applications

International Nuclear Information System (INIS)

Pulsipher, B.A.

1992-05-01

The United States Department of Energy (DOE) has developed a strategy for nuclear waste remediation and environmental restoration at several major sites across the country. Nuclear and hazardous wastes are found in underground storage tanks, containment drums, soils, and facilities. Due to the many possible contaminants and complexities of sampling and analysis, multivariate methods are directly applicable. However, effective application of multivariate methods will require greater ability to communicate methods and results to a non-statistician community. Moreover, more flexible multivariate methods may be required to accommodate inherent sampling and analysis limitations. This paper outlines multivariate applications in the context of select DOE environmental restoration activities and identifies several perceived needs

Tank waste remediation system: An update

International Nuclear Information System (INIS)

Alumkal, W.T.; Babad, H.; Dunford, G.L.; Honeyman, J.O.; Wodrich, D.D.

1995-02-01

The US Department of Energy's Hanford Site, located in southeastern Washington State, contains the largest amount and the most diverse collection of highly radioactive waste in the US. High-level radioactive waste has been stored at the Hanford Site in large, underground tanks since 1944. Approximately 217,000 M 3 (57 Mgal) of caustic liquids, slurries, saltcakes, and sludges have accumulated in 177 tanks. In addition, significant amounts of 90 Sr and 137 Cs were removed from the tank waste, converted to salts, doubly encapsulated in metal containers, and stored in water basins. The Tank Waste Remediation System Program was established by the US Department of Energy in 1991 to safely manage and immobilize these wastes in anticipation of permanent disposal of the high-level waste fraction in a geologic repository. Since 1991, significant progress has been made in resolving waste tank safety issues, upgrading Tank Farm facilities and operations, and developing a new strategy for retrieving, treating, and immobilizing the waste for disposal

Chemical Remediation of Nickel(II) Waste: A Laboratory Experiment for General Chemistry Students

Science.gov (United States)

Corcoran, K. Blake; Rood, Brian E.; Trogden, Bridget G.

2011-01-01

This project involved developing a method to remediate large quantities of aqueous waste from a general chemistry laboratory experiment. Aqueous Ni(II) waste from a general chemistry laboratory experiment was converted into solid nickel hydroxide hydrate with a substantial decrease in waste volume. The remediation method was developed for a…

Effectiveness of interim remedial actions at a radioactive waste facility

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

1989-01-01

Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

A systematic look at Tank Waste Remediation System privatization

International Nuclear Information System (INIS)

Holbrook, J.H.; Duffy, M.A.; Vieth, D.L.; Sohn, C.L.

1996-01-01

The mission of the Tank Waste Remediation System (TWRS) Program is to store, treat, immobilize, and dispose, or prepare for disposal, the Hanford radioactive tank waste in an environmentally sound, safe, and cost effective manner. Highly radioactive Hanford waste includes current and future tank waste plus the cesium and strontium capsules. In the TWRS program, as in other Department of Energy (DOE) clean-up activities, there is an increasing gap between the estimated funding required to enable DOE to meet all of its clean-up commitments and level of funding that is perceived to be available. Privatization is one contracting/management approach being explored by DOE as a means to achieve cost reductions and as a means to achieve a more outcome-oriented program. Privatization introduces the element of competition, a proven means of establishing true cost as well as achieving significant cost reduction

300-FF-1 remedial design report/remedial action work plan

Energy Technology Data Exchange (ETDEWEB)

Gustafson, F.W.

1997-02-01

The 300 Area has been divided into three operable units 300-FF-1, 300-FF-2, and 300-FF-5 all of which are in various stages of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) process. The 300-FF-1 Operable Unit, the subject of this report, includes liquid waste disposal sites, landfills, and a burial ground. This Remedial Design Report/Remedial Action Work Plan (RDR/RAWP) provides a summary description of each waste site included in the 300-FF-1 Operable Unit, the basis for remedial actions to be taken, and the remedial action approach and management process for implementing these actions. The remedial action approach and management sections provide a description of the remedial action process description, the project schedule, the project team, required planning documentation, the remedial action change process, the process for verifying attainment of the remedial action goals, and the required CERCLA and RCRA closeout documentation. Appendix A provides additional details on each waste site. In addition to remediation of the waste sites, waste generated during the remedial investigation/feasibility study portions of the project will also be disposed at the Environmental Restoration Disposal Facility (ERDF). Appendix B provides a summary of the modeling performed in the 300-FF-1 Phase 3 FS and a description of the modeling effort to be used to show attainment of the remedial action goals. Appendix C provides the sampling and analysis plan (SAP) for all sampling and field-screening activities performed during remediation and for verification of attainment with the remedial action goals. Appendix D provides the public involvement plan, prepared to ensure information is provided to the public during remedial design and remedial action processes.

300-FF-1 remedial design report/remedial action work plan

International Nuclear Information System (INIS)

Gustafson, F.W.

1997-02-01

The 300 Area has been divided into three operable units 300-FF-1, 300-FF-2, and 300-FF-5 all of which are in various stages of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) process. The 300-FF-1 Operable Unit, the subject of this report, includes liquid waste disposal sites, landfills, and a burial ground. This Remedial Design Report/Remedial Action Work Plan (RDR/RAWP) provides a summary description of each waste site included in the 300-FF-1 Operable Unit, the basis for remedial actions to be taken, and the remedial action approach and management process for implementing these actions. The remedial action approach and management sections provide a description of the remedial action process description, the project schedule, the project team, required planning documentation, the remedial action change process, the process for verifying attainment of the remedial action goals, and the required CERCLA and RCRA closeout documentation. Appendix A provides additional details on each waste site. In addition to remediation of the waste sites, waste generated during the remedial investigation/feasibility study portions of the project will also be disposed at the Environmental Restoration Disposal Facility (ERDF). Appendix B provides a summary of the modeling performed in the 300-FF-1 Phase 3 FS and a description of the modeling effort to be used to show attainment of the remedial action goals. Appendix C provides the sampling and analysis plan (SAP) for all sampling and field-screening activities performed during remediation and for verification of attainment with the remedial action goals. Appendix D provides the public involvement plan, prepared to ensure information is provided to the public during remedial design and remedial action processes

GIS-based tools to identify tradeoffs between waste management and remediation strategies from radiological dispersal device incidents

Energy Technology Data Exchange (ETDEWEB)

Lemieux, P.; Wood, J.; Snyder, E. [U.S. Environmental Protection Agency, Research Triangle Park, NC (United States); Boe, T. [Oak Ridge Inst. for Science and Education, Research Triangle Park, NC (United States); Schulthiesz, D.; Peake, T.; Ierardi, M. [U.S. Environmental Protection Agency, Washington, DC (United States); Hayes, C.; Rodgers, M. [Eastern Research Group, Inc., Morrisville, NC (United States)

2011-07-01

Management of waste and debris from the detonation of a Radiological Dispersal Device (RDD) will likely comprise a significant portion of the overall remediation effort and possibly contribute to a significant portion of the overall remediation costs. As part of the recent National Level Exercise, Liberty RadEx, that occurred in Philadelphia in April 2010, a methodology was developed by EPA to generate a first-order estimate of a waste inventory for the hypothetical RDD from the exercise scenario. Determination of waste characteristics and whether the generated waste is construction and demolition (C&D) debris, municipal solid waste (MSW), hazardous waste, mixed waste, or low level radioactive waste (LLRW), and characterization of the wastewater that is generated from the incident or subsequent cleanup activities will all influence the cleanup costs and timelines. Decontamination techniques, whether they involve chemical treatment, abrasive removal, or aqueous washing, will also influence the waste generated and associated cleanup costs and timelines. This paper describes the ongoing effort to develop a tool to support RDD planning and response activities by assessing waste quantities and characteristics as a function of potential mitigation strategies and targeted cleanup levels. (author)

GIS-based tools to identify tradeoffs between waste management and remediation strategies from radiological dispersal device incidents

International Nuclear Information System (INIS)

Lemieux, P.; Wood, J.; Snyder, E.; Boe, T.; Schulthiesz, D.; Peake, T.; Ierardi, M.; Hayes, C.; Rodgers, M.

2011-01-01

Management of waste and debris from the detonation of a Radiological Dispersal Device (RDD) will likely comprise a significant portion of the overall remediation effort and possibly contribute to a significant portion of the overall remediation costs. As part of the recent National Level Exercise, Liberty RadEx, that occurred in Philadelphia in April 2010, a methodology was developed by EPA to generate a first-order estimate of a waste inventory for the hypothetical RDD from the exercise scenario. Determination of waste characteristics and whether the generated waste is construction and demolition (C&D) debris, municipal solid waste (MSW), hazardous waste, mixed waste, or low level radioactive waste (LLRW), and characterization of the wastewater that is generated from the incident or subsequent cleanup activities will all influence the cleanup costs and timelines. Decontamination techniques, whether they involve chemical treatment, abrasive removal, or aqueous washing, will also influence the waste generated and associated cleanup costs and timelines. This paper describes the ongoing effort to develop a tool to support RDD planning and response activities by assessing waste quantities and characteristics as a function of potential mitigation strategies and targeted cleanup levels. (author)

Draft Environmental Impact Statement for the tank waste remediation system. Volume 1

International Nuclear Information System (INIS)

1996-04-01

This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, and Ex Situ/In Situ Combination. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. At this time, DOE and Ecology do not have a preferred alternative for the cesium and strontium capsules

Applicability of petroleum horizontal drilling technology to hazardous waste site characterization and remediation

International Nuclear Information System (INIS)

Goranson, C.

1992-09-01

Horizontal wells have the potential to become an important tool for use in characterization, remediation and monitoring operations at hazardous waste disposal, chemical manufacturing, refining and other sites where subsurface pollution may develop from operations or spills. Subsurface pollution of groundwater aquifers can occur at these sites by leakage of surface disposal ponds, surface storage tanks, underground storage tanks (UST), subsurface pipelines or leakage from surface operations. Characterization and remediation of aquifers at or near these sites requires drilling operations that are typically shallow, less than 500-feet in depth. Due to the shallow nature of polluted aquifers, waste site subsurface geologic formations frequently consist of unconsolidated materials. Fractured, jointed and/or layered high compressive strength formations or compacted caliche type formations can also be encountered. Some formations are unsaturated and have pore spaces that are only partially filled with water. Completely saturated underpressured aquifers may be encountered in areas where the static ground water levels are well below the ground surface. Each of these subsurface conditions can complicate the drilling and completion of wells needed for monitoring, characterization and remediation activities. This report describes some of the equipment that is available from petroleum drilling operations that has direct application to groundwater characterization and remediation activities. A brief discussion of petroleum directional and horizontal well drilling methodologies is given to allow the reader to gain an understanding of the equipment needed to drill and complete horizontal wells. Equipment used in river crossing drilling technology is also discussed. The final portion of this report is a description of the drilling equipment available and how it can be applied to groundwater characterization and remediation activities

Remediating the INEL's buried mixed waste tanks

International Nuclear Information System (INIS)

Kuhns, D.J.; Matthern, G.E.; Reese, C.L.

1996-01-01

The Idaho National Engineering Laboratory (INEL), formerly the National Reactor Testing Station (NRTS), encompasses 890 square miles and is located in southeast Idaho. In 1949, the United States Atomic Energy Commission, now the Department of Energy (DOE), established the NRTS as a site for the building and testing of nuclear facilities. Wastes generated during the building and testing of these nuclear facilities were disposed within the boundaries of the site. These mixed wastes, containing radionuclides and hazardous materials, were often stored in underground tanks for future disposal. The INEL has 11 buried mixed waste storage tanks regulated under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) ranging in size from 400 to 50,000 gallons. These tanks are constructed of either stainless or carbon steel and are located at 3 distinct geographic locations across the INEL. These tanks have been grouped based on their similarities in an effort to save money and decrease the time required to complete the necessary remediation. Environmental Restoration and Technology Development personnel are teaming in an effort to address the remediation problem systematically

Tank waste remediation system mission analysis report

International Nuclear Information System (INIS)

Acree, C.D.

1998-01-01

This document describes and analyzes the technical requirements that the Tank Waste Remediation System (TWRS) must satisfy for the mission. This document further defines the technical requirements that TWRS must satisfy to supply feed to the private contractors' facilities and to store or dispose the immobilized waste following processing in these facilities. This document uses a two phased approach to the analysis to reflect the two-phased nature of the mission

Remediating while preserving wetland habitat at an LLR waste site in Canada

International Nuclear Information System (INIS)

Kleb, H.R.; Zelmer, R.L.

2007-01-01

The Low-Level Radioactive Waste Management Office was established in 1982 to carry out the federal government's responsibilities for low-level radioactive (LLR) waste management in Canada. The Office operates programs to characterize, delineate, decontaminate and consolidate historic LLR waste for interim and long-term storage. In this capacity, the Office is currently considering the remediation of 9,000 cubic metres of contaminated sediment in a coastal marsh in the context of a major remediation project involving multiple urban sites. The marsh is situated between the Lake Ontario shoreline and the urban fringe of the Town of Port Hope. The marsh is designated a Cattail Mineral Shallow Marsh under the Ecological Land Classification system for Southern Ontario and was recently named the A.K. Sculthorpe Marsh in memory of a local community member. The marsh remediation will therefore require trade off between the disruption of a sensitive wetland and the removal of contaminated sediment. This paper discusses the issues and trade-off relating to the waste characterization, environmental assessment and regulatory findings and thus the remediation objectives for the marsh. Considerations include the spatial distribution of contaminated sediment, the bioavailability of contaminants, the current condition of the wetland and the predicted effects of remediation. Also considered is the significance of the wetland from provincial and municipal regulatory perspectives and the resulting directives for marsh remediation. (authors)

Structural analysis of Hanford's single-shell 241-C-106 tank: A first step toward waste-tank remediation

International Nuclear Information System (INIS)

Harris, J.P.; Julyk, L.J.; Marlow, R.S.; Moore, C.J.; Day, J.P.; Dyrness, A.D.; Jagadish, P.; Shulman, J.S.

1993-10-01

The buried single-shell waste tank 241-C-106, located at the US Department of Energy's Hanford Site, has been a repository for various liquid radioactive waste materials since its construction in 1943. A first step toward waste tank remediation is demonstrating that remediation activities can be performed safely. Determination of the current structural capacity of this high-heat tank is an important element in this assessment. A structural finite-element model of tank 241-C-106 has been developed to assess the tank's structural integrity with respect to in situ conditions and additional remediation surface loads. To predict structural integrity realistically, the model appropriately addresses two complex issues: (1) surrounding soil-tank interaction associated with thermal expansion cycling and surcharge load distribution and (2) concrete-property degradation and creep resulting from exposure to high temperatures generated by the waste. This paper describes the development of the 241-C-106 structural model, analysis methodology, and tank-specific structural acceptance criteria

Tank waste remediation system baseline tank waste inventory estimates for fiscal year 1995

International Nuclear Information System (INIS)

Shelton, L.W.

1996-01-01

A set of tank-by-tank waste inventories is derived from historical waste models, flowsheet records, and analytical data to support the Tank Waste Remediation System flowsheet and retrieval sequence studies. Enabling assumptions and methodologies used to develop the inventories are discussed. These provisional inventories conform to previously established baseline inventories and are meant to serve as an interim basis until standardized inventory estimates are made available

Design requirements document for project W-520, immobilized low-activity waste disposal

International Nuclear Information System (INIS)

Ashworth, S.C.

1998-01-01

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity

Design requirements document for project W-520, immobilized low-activity waste disposal

Energy Technology Data Exchange (ETDEWEB)

Ashworth, S.C.

1998-08-06

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

Technology needs and trends for hazardous waste site remediation

International Nuclear Information System (INIS)

Kovalick, W.W. Jr.

1995-01-01

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

Hanford site tank waste remediation system programmatic environmental review report

International Nuclear Information System (INIS)

Haass, C.C.

1998-01-01

The US Department of Energy (DOE) committed in the Tank Waste Remediation System (TWRS) Environmental Impact Statement (EIS) Record of Decision (ROD) to perform future National Environmental Policy Act (NEPA) analysis at key points in the Program. Each review will address the potential impacts that new information may have on the environmental impacts presented in the TWRS EIS and support an assessment of whether DOE's plans for remediating the tank waste are still pursuing the appropriate plan for remediation or whether adjustments to the program are needed. In response to this commitment, DOE prepared a Supplement Analysis (SA) to support the first of these reevaluations. Subsequent to the completion of the SA, the Phase IB negotiations process with private contractors resulted in several changes to the planned approach. These changes along with other new information regarding the TWRS Program have potential implications for Phase 1 and Phase 2 of tank waste retrieval and waste storage and/or disposal that may influence the environmental impacts of the Phased Implementation alternative. This report focuses on identifying those potential environmental impacts that may require NEPA analysis prior to authorization to begin facility construction and operations

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

International Nuclear Information System (INIS)

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

1992-01-01

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

Technical baseline description of high-level waste and low-activity waste feed mobilization and delivery

International Nuclear Information System (INIS)

Papp, I.G.

1997-01-01

This document is a compilation of information related to the high-level waste (HLW) and low-activity waste (LAW) feed staging, mobilization, and transfer/delivery issues. Information relevant to current Tank Waste Remediation System (TWRS) inventories and activities designed to feed the Phase I Privatization effort at the Hanford Site is included. Discussions on the higher level Phase II activities are offered for a perspective on the interfaces

Department of Energy Hazardous Waste Remedial Actions Program: An overview

International Nuclear Information System (INIS)

Eyman, L.D.; Swiger, R.F.

1988-01-01

This paper describes the national Department of Energy (DOE) program for managing hazardous waste. An overview of the DOE Hazardous Waste Remedial Actions Program (HAZWRAP), including its mission, organizational structure, and major program elements, is given. The paper focuses on the contractor support role assigned to Martin Marietta Energy Systems, Inc., through the establishment of the HAZWRAP Support Contractor Office (SCO). The major SCO programs are described, and the organization for managing the programs is discussed. The HAZWRAP SCO approaches to waste management planning and to technology research, development, and demonstration are presented. The role of the SCO in the DOE Environmental Restoration Program and the development of the DOE Waste Information network are reviewed. Also discussed is the DOE Work for Others Program, where waste management decentralized support, via interagency agreements between DOE and the Department of Defense and DOE and the Environmental Protection Agency, is provided for those sponsors planning remedial response actions. 2 refs

The Use of Waste Materials in the Passive Remediation of Mine Water Polution

Science.gov (United States)

Batty, Lesley C.; Younger, Paul L.

2004-01-01

The contamination and resulting degradation of water courses by effluents from abandoned and active mines is a world-wide problem. Traditional methods of remediating the discharges from mines involve the addition of chemicals and the utilisation of artificial energy sources. Over the last 15-20 years passive treatment systems have been developed that harness natural chemical and biological processes to ameliorate the potentially toxic effects of such discharges. There are many different types of passive system, including compost wetlands, reducing and alkalinity producing systems (RAPS), permeable reactive barriers and inorganic media passive systems. Different waste materials can be utilised as reactive media within each of these systems, dependent upon the type of mine water and treatment technology. In many cases the reactivity of these recycled waste materials is key to the remedial performance of these systems. The materials used may be organic (e.g., composts) or inorganic (e.g., blast furnace slag) and where possible are sourced locally in order to minimise transport costs. The remediation of mine waters in itself can produce large quantities of waste products in the form of iron oxide sludge. Potential uses of this material in the production of pigments and in the treatment of phosphate contaminated waters is also currently under investigation. The exploitation of what are traditionally thought of as waste materials within treatment systems for polluted waters is an expanding technology which provides great scope for recycling.

Tank waste remediation system mission analysis report

International Nuclear Information System (INIS)

Acree, C.D.

1998-01-01

The Tank Waste Remediation System Mission Analysis Report identifies the initial states of the system and the desired final states of the system. The Mission Analysis Report identifies target measures of success appropriate to program-level accomplishments. It also identifies program-level requirements and major system boundaries and interfaces

Hazardous Waste Remedial Actions Program annual progress report, FY 1990

Energy Technology Data Exchange (ETDEWEB)

1990-12-01

The Hazardous Waste Remedial Actions Programs (HAZWRAP), a unit of Martin Marietta Energy Systems, Inc., supports the Department of Energy (DOE) Oak Ridge Operations Office in broadly environmental areas, especially those relating to waste management and environmental restoration. HAZWRAP comprises six program areas, which are supported by central administrative and technical organizations. Existing programs deal with airborne hazardous substances, pollution prevention, remedial actions planning, environmental restoration, technology development, and information and data systems. HAZWRAP's mission to develop, promote, and apply-cost-effective hazardous waste management and environmental technologies to help solve national problems and concerns. HAZWRAP seeks to serve as integrator for hazardous waste and materials management across the federal government. It applies the unique combination of research and development (R D) capabilities, technologies, management expertise, and facilities in the Energy Systems complex to address problems of national importance. 24 figs., 10 tabs.

The use of historical imagery in the remediation of an urban hazardous waste site

Science.gov (United States)

Slonecker, E.T.

2011-01-01

The information derived from the interpretation of historical aerial photographs is perhaps the most basic multitemporal application of remote-sensing data. Aerial photographs dating back to the early 20th century can be extremely valuable sources of historical landscape activity. In this application, imagery from 1918 to 1927 provided a wealth of information about chemical weapons testing, storage, handling, and disposal of these hazardous materials. When analyzed by a trained photo-analyst, the 1918 aerial photographs resulted in 42 features of potential interest. When compared with current remedial activities and known areas of contamination, 33 of 42 or 78.5% of the features were spatially correlated with areas of known contamination or other remedial hazardous waste cleanup activity.

High-level waste tank remediation technology integration summary. Revision 1

International Nuclear Information System (INIS)

DeLannoy, C.R.; Susiene, C.; Fowler, K.M.; Robson, W.M.; Cruse, J.M.

1994-07-01

The U.S. Department of Energy's Environmental Restoration and Waste Management and Technology Development Programs are engaged in a number of projects to develop, demonstrate, test, and evaluate new technologies to support the cleanup and site remediation of more than 300 underground storage tanks containing over 381,000 m 3 (100 million gal) of liquid radioactive mixed waste at the Hanford Reservation. Significant development is needed within primary functions and in determining an overall bounding strategy. This document is an update of continuing work to summarize the overall strategy and to provide data regarding technology development activities within the strategy. It is intended to serve as an information resource to support understanding, decision making, and integration of multiple program technology development activities. Recipients are encouraged to provide comments and input to the authors for incorporation in future revisions

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final environmental impact statement. Summary

International Nuclear Information System (INIS)

1996-08-01

This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

Waste management and environmental compliance aspects of a major remedial action program

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.

1991-01-01

The Formerly Utilized Sites Remedial Action Program (FUSRAP) is one of four major programs undertaken by the US Department of Energy (DOE) to remediate various sites where radiological contamination remained from programs conducted during the nation's early years of research and development in atomic energy. The remedial actions at the 33 sites that are currently in FUSRAP could generate an estimated total volume of about 1.6 million cubic meters of radioactive waste. Waste disposal is currently estimated to represent about one-third of the total estimated $2.1 billion cost for the entire program over its total duration. Waste management aspects within the program are diverse. The sites range in size from small areas used only for storage operations to large-scale decommissioned industrial facilities where uranium processing and other operations were carried out in the past. Currently, four sites are on the National Priorities List for remediation. Remedial actions at FUSRAP sites have to satisfy the requirements of both the National Environmental Policy Act and the Comprehensive Environmental Response, Compensation and Liability Act, as amended. In addition, a number of federal, state, and local laws as well as Executive Orders and DOE Orders may be applicable or relevant to each site. Several key issues currently face the program, including the mixed waste issue, both from the environmental compliance (with Resource Conservation and Recovery Act) and the disposal technology perspectives. 7 refs., 1 tab

Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition

International Nuclear Information System (INIS)

Leach, C.E.; Galbraith, J.D.; Grant, P.R.; Francuz, D.J.; Schroeder, P.J.

1995-11-01

This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs

Tank Waste Remediation System decisions and risk assessment

International Nuclear Information System (INIS)

Johnson, M.E.

1994-09-01

The Tank Waste Remediation System (TWRS) mission is to store, treat, and immobilize the highly radioactive Hanford Site tank wastes and encapsulated cesium and strontium materials in an environmentally sound, safe, and cost effective manner. Additionally, the TWRS conducts, as part of this mission, resolution of safety issues associated with the wastes within the 177 underground radioactive waste tanks. Systems engineering principles are being applied to determine the functions and establish requirements necessary for accomplishing the TWRS mission (DOE 1994 draft). This systematic evaluation of the TWRS program has identified key decisions that must be executed to establish mission scope, determine requirements, or select a technical solution for accomplishing identified functions and requirements. Key decisions identified through the systematic evaluation of the TWRS mission are presented in this document. Potential alternative solutions to each decision are discussed. After-discussion and evaluation of each decision with effected stakeholder groups, the US Department of Energy (DOE) will select a solution from the identified alternatives for implementation. In order to proceed with the development and execution of the tank waste remediation program, the DOE has adopted a planning basis for several of these decisions, until a formal basis is established. The planning bases adopted by the DOE is continuing to be discussed with stakeholder groups to establish consensus for proceeding with proposed actions. Technical and programmatic risks associated with the planning basis adopted by the DOE are discussed

Tank waste remediation system privatization infrastructure program requirements and document management process guide

International Nuclear Information System (INIS)

ROOT, R.W.

1999-01-01

This guide provides the Tank Waste Remediation System Privatization Infrastructure Program management with processes and requirements to appropriately control information and documents in accordance with the Tank Waste Remediation System Configuration Management Plan (Vann 1998b). This includes documents and information created by the program, as well as non-program generated materials submitted to the project. It provides appropriate approval/control, distribution and filing systems

200 Areas soil remediation strategy -- Environmental Restoration Program

International Nuclear Information System (INIS)

1996-09-01

The remediation and waste management activities in the 200 Areas of the Hanford Site (located in Richland, Washington) currently range from remediating groundwater, remediating source units (contaminated soils), decontaminating and decommissioning of buildings and structures, maintaining facilities, managing transuranic, low-level and mixed waste, and operating tank farms that store high-level waste. This strategy focuses on the assessment and remediation of soil that resulted from the discharge of liquids and solids from processing facilities to the ground (e.g., ponds, ditches, cribs, burial grounds) in the 200 Areas and addresses only those waste sites assigned to the Environmental Restoration Program

TECHNICAL GUIDANCE DOCUMENT: CONSTRUCTION QUALITY MANAGEMENT FOR REMEDIAL ACTION AND REMEDIAL DESIGN WASTE CONTAINMENT SYSTEMS

Science.gov (United States)

This Technical Guidance Document is intended to augment the numerous construction quality control and construction quality assurance (CQC and CQA) documents that are available far materials associated with waste containment systems developed for Superfund site remediation. In ge...

Tank Waste Remediation System Guide

International Nuclear Information System (INIS)

Robershotte, M.A.; Dirks, L.L.; Seaver, D.A.; Bothers, A.J.; Madden, M.S.

1995-06-01

The scope, number and complexity of Tank Waste Remediation System (TWRS) decisions require an integrated, consistent, and logical approach to decision making. TWRS has adopted a seven-step decision process applicable to all decisions. Not all decisions, however, require the same degree of rigor/detail. The decision impact will dictate the appropriate required detail. In the entire process, values, both from the public as well as from the decision makers, play a key role. This document concludes with a general discussion of the implementation process that includes the roles of concerned parties

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume I

International Nuclear Information System (INIS)

1996-08-01

This document, Volume 1 of the Final Environmental Impact Statement, analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

Evaluation of select trade-offs between ground-water remediation and waste minimization for petroleum refining industry

International Nuclear Information System (INIS)

Andrews, C.D.; McTernan, W.F.; Willett, K.K.

1996-01-01

An investigation comparing environmental remediation alternatives and attendant costs for a hypothetical refinery site located in the Arkansas River alluvium was completed. Transport from the land's surface to and through the ground water of three spill sizes was simulated, representing a base case and two possible levels of waste minimization. Remediation costs were calculated for five alternative remediation options, for three possible regulatory levels and alternative site locations, for four levels of technology improvement, and for eight different years. It is appropriate from environmental and economic perspectives to initiate significant efforts and expenditures that are necessary to minimize the amount and type of waste produced and disposed during refinery operations; or conversely, given expected improvements in technology, is it better to wait until remediation technologies improve, allowing greater environmental compliance at lower costs? The present work used deterministic models to track a light nonaqueous phase liquid (LNAPL) spill through the unsaturated zone to the top of the water table. Benzene leaching from LNAPL to the ground water was further routed through the alluvial aquifer. Contaminant plumes were simulated over 50 yr of transport and remediation costs assigned for each of the five treatment options for each of these years. The results of these efforts show that active remediation is most cost effective after a set point or geochemical quasi-equilibrium is reached, where long-term improvements in technology greatly tilt the recommended option toward remediation. Finally, the impacts associated with increasingly rigorous regulatory levels present potentially significant penalties for the remediation option, but their likelihood of occurrence is difficult to define

Reduction of radioactive waste from remediation of uranium-contaminated soil

Energy Technology Data Exchange (ETDEWEB)

Kim, Il Gook; Kim, Seung Soo; Kim, Gye Nam; Han, Gyu Seong; Choi, Jong Won [Decontamination and Decommissioning Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-06-15

Great amounts of solid radioactive waste (second waste) and waste solution are generated from the remediation of uranium-contaminated soil. To reduce these, we investigated washing with a less acidic solution and recycling the waste solution after removal of the dominant elements and uranium. Increasing the pH of the washing solution from 0.5 to 1.5 would be beneficial in terms of economics. A high content of calcium in the waste solution was precipitated by adding sulfuric acid. The second waste can be significantly reduced by using sorption and desorption techniques on ampholyte resin S-950 prior to the precipitation of uranium at pH 3.0.

Reduction of radioactive waste from remediation of uranium-contaminated soil

International Nuclear Information System (INIS)

Kim, Il Gook; Kim, Seung Soo; Kim, Gye Nam; Han, Gyu Seong; Choi, Jong Won

2016-01-01

Great amounts of solid radioactive waste (second waste) and waste solution are generated from the remediation of uranium-contaminated soil. To reduce these, we investigated washing with a less acidic solution and recycling the waste solution after removal of the dominant elements and uranium. Increasing the pH of the washing solution from 0.5 to 1.5 would be beneficial in terms of economics. A high content of calcium in the waste solution was precipitated by adding sulfuric acid. The second waste can be significantly reduced by using sorption and desorption techniques on ampholyte resin S-950 prior to the precipitation of uranium at pH 3.0

Glassy slags as novel waste forms for remediating mixed wastes with high metal contents

International Nuclear Information System (INIS)

Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.

1994-01-01

Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms

Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

International Nuclear Information System (INIS)

McLaughlin, T.J.

1998-01-01

This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

Tank waste remediation system characterization project quality policies. Revision 1

International Nuclear Information System (INIS)

Trimble, D.J.

1995-01-01

These Quality Policies (QPs) describe the Quality Management System of the Tank Waste Characterization Project (hereafter referred to as the Characterization Project), Tank Waste Remediation System (TWRS), Westinghouse Hanford Company (WHC). The Quality Policies and quality requirements described herein are binding on all Characterization Project organizations. To achieve quality, the Characterization Project management team shall implement this Characterization Project Quality Management System

Tank waste remediation system retrieval and disposal mission phase 1 financial analysis

International Nuclear Information System (INIS)

Wells, M.W.

1998-01-01

modeled using a Monte Carlo type simulation and are included in Section 4.0 Analysis. The modeling was focused on low-activity waste (LAW) and high-level waste (HLW) feed delivery, infrastructure, and immobilized waste storage and disposal, and compiled at the total Phase 1B Retrieval and Disposal program. An independent review appraisal of technical plans and processes was also conducted utilizing experienced senior personnel both active and retired from Fluor Daniel Hanford, Inc. (FDH), (LHMC), U.S. Department of Energy (DOE), and previous Hanford contractors. The results were merged with the output from other evaluations to form HNF-1945, Tank Waste Remediation System Retrieval and Disposal Mission Key Enabling Assumptions

Tank waste remediation system retrieval and disposal mission infrastructure plan

International Nuclear Information System (INIS)

Root, R.W.

1998-01-01

This system plan presents the objectives, organization, and management and technical approaches for the Infrastructure Program. This Infrastructure Plan focuses on the Tank Waste Remediation System (TWRS) Project's Retrieval and Disposal Mission

Tank waste remediation system integrated technology plan. Revision 2

International Nuclear Information System (INIS)

Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P.

1995-01-01

The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m 3 (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program

Tank waste remediation system integrated technology plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

1995-02-28

The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

Draft Environmental Impact Statement for the tank waste remediation system. Volume 4

International Nuclear Information System (INIS)

1996-04-01

This appendix describes the current safety concerns associated with the tank waste and analyzes the potential accidents and associated potential health effects that could occur under the alternatives included in this Tank Waste Remediation System (TWRS) Environmental Impact Statement (EIS)

Tank waste remediation system configuration management implementation plan

International Nuclear Information System (INIS)

Vann, J.M.

1998-01-01

The Tank Waste Remediation System (TWRS) Configuration Management Implementation Plan describes the actions that will be taken by Project Hanford Management Contract Team to implement the TWRS Configuration Management program defined in HNF 1900, TWRS Configuration Management Plan. Over the next 25 years, the TWRS Project will transition from a safe storage mission to an aggressive retrieval, storage, and disposal mission in which substantial Engineering, Construction, and Operations activities must be performed. This mission, as defined, will require a consolidated configuration management approach to engineering, design, construction, as-building, and operating in accordance with the technical baselines that emerge from the life cycles. This Configuration Management Implementation Plan addresses the actions that will be taken to strengthen the TWRS Configuration Management program

The Hanford Site Tank Waste Remediation System: An update

International Nuclear Information System (INIS)

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

1994-01-01

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

FY 1995 remedial investigation work plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Watkins, D.R.; Herbes, S.E.

1994-09-01

Field activities to support the remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) include characterization of the nature and extent of contamination in WAG 2, specifically to support risk-based remediation decisions. WAG 2 is the major drainage system downgradient of other WAGs containing significant sources of contamination at ORNL. The RI of WAG 2 is developed in three phases: Phase 1, initial scoping characterization to determine the need for early action; Phase 2, interim activities during remediation of upgradient WAGs to evaluate potential changes in the contamination status of WAG 2 that would necessitate reevaluation of the need for early action; and Phase 3, completion of the RI process following remediation of upslope WAGs. Specifically, Phase 2 activities are required to track key areas to determine if changes have occurred in WAG 2 that would require (1) interim remedial action to protect human health and the environment or (2) changes in remedial action plans and schedules for WAG2 because of changing contaminant release patterns in upslope WAGs or because of the effects of interim remedial or removal actions in other WAGs. This report defines activities to be conducted in FY 1995 for completion of the Phase 1 RI and initiation of limited Phase 2 field work

Electrodialytic remediation of CCA treated waste wood in pilot scale

DEFF Research Database (Denmark)

Pedersen, Anne Juul; Christensen, Iben Vernegren; Ottosen, Lisbeth M.

2005-01-01

study the utility of the method Electrodialytic Remediation was demonstrated for handling of CCA treated waste wood in pilot scale. The electrodialytic remediation method, which uses a low level DC current as the cleaning agent, combines elektrokinetic movement of ions in the wood matrix with the princi......-ples of electrodialysis. It has previously been shown that it is possible to remove Cu, Cr and As from CCA treated wood using electrodialytic remediation in laboratory scale (Ribeiro et al., 2000; Kristensen et al., 2003), but until now, the method had not been studied in larger scale. The pilot scale plant used...... in this study was designed to contain up to 2 m3 wood chips. Six remediation experiments were carried out. In these experiments, the process was up-scaled stepwise by increasing the distance between the electrodes from initially 60 cm to fi-nally 150 cm. The remediation time was varied between 11 and 21 days...

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

Present status of the Zavratec remediation project

International Nuclear Information System (INIS)

Zeleznik, N.; Stepisnik, M.; Mele, I.

1997-01-01

In 1992 the responsibility for the remediation of the temporary storage of radioactive waste near Zavratec was assigned to the Agency for Radwaste Management. The project was divided into two phases. First, in a study, different options for remediation were considered. In the second phase, performed in 1996, the measurements, inventorying and repacking of radioactive waste were carried out. Simultaneously with these activities a programme for covering public relations was prepared. One of the results of the public relation campaign is also a 15-minute video film, which was prepared from documentary material recorded during remedial activities, and will be presented here. (author)

Final remediation of the provisional storage near Zavratec. Separation of waste, decontamination and radiological measurements

International Nuclear Information System (INIS)

Stepisnik, M.; Zeleznik, N.; Mele, I.

2000-01-01

This paper presents remedial activities in Zavratec during winter 1999 - 2000. The difficult and slow process of separation radioactive from non-radioactive waste is explained, and the measuring techniques and equipment for separation are presented. The measurements of storage contamination and its decontamination, involving different practical problems, are described in detail. As a result, the initial volume of the waste was reduced to 50%, in spite of the extended decontamination works. The waste has been relocated to the Brinje storage facility. Measurements inside and outside the Zavratec facility after decontamination showed that no radioactivity higher than the natural background was present. The facility was released for unrestricted use. (author)

Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

International Nuclear Information System (INIS)

Bitz, D.A.; Berry, D.L.; Jardine, L.J.

1994-03-01

Hanford's underground tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this report

The Sonophysics and Sonochemistry of Liquid Waste Quantification and Remediation

Energy Technology Data Exchange (ETDEWEB)

Matula, Thomas J.

1998-06-01

This research is being conducted to (a) perform an in-depth and comprehensive study of the fundamentals of acoustic cavitation and nonlinear bubble dynamics, (b) elucidate the fundamental physics of sonochemical reactions, (c) examine the potential of sonoluminescence to quantify and monitor the presence of alkali metals and other elements in waste liquids, (d) design and evaluate more effective sonochemical reactors for waste remediation, and (e) determine the optimal acoustical parameters in the use of sonochemistry for liquid-waste-contaminant remediation. So far cells have been designed for multibubble sonoluminescence (MBSL) and single-bubble sonoluminescence (SBSL) spectroscopy experiments. Positive results have been obtained in both systems using a Raman system which covers the wavelength range from 790 to 1,070 nm. Further progress from year-1 involved the use of the newly discovered technique of changing the pressure head above the cavitation field to increase the light emission from MBSL. A second method for changing the pressure head involves pressure-jumping, whereby the pressure in the head space above the solution is quickly increased to a new steady value.

Testing and development strategy for the tank waste remediation system

International Nuclear Information System (INIS)

Reddick, G.W.

1994-12-01

This document provides a strategy for performing radioactive (hot) and nonradioactive testing to support processing tank waste. It evaluates the need for hot pilot plant(s) to support pretreatment and other processing functions and presents a strategy for performing hot test work. A strategy also is provided for nonradioactive process and equipment testing. The testing strategy supports design, construction, startup, and operation of Tank Waste Remediation System (TWRS) facilities

Testing and development strategy for the tank waste remediation system

International Nuclear Information System (INIS)

Reddick, G.W.

1995-01-01

This document provides a strategy for performing radioactive (hot) and nonradioactive testing to support processing tank waste. It evaluates the need for hot pilot plant(s) to support pretreatment and other processing functions and presents a strategy for performing hot test work. A strategy also is provided for nonradioactive process and equipment testing. The testing strategy supports design, construction, startup, and operation of Tank Waste Remediation System (TWRS) facilities

Evaluation of technical, economic and financial feasibility for recycling and reprocessing of radioactive waste from a remediation work of low and medium activity for the extraction of heavy minerals - 59231

International Nuclear Information System (INIS)

Raposo de Almeida, Rodrigo; Mortagua, Valter J.G.

2012-01-01

Document available in abstract form only. Full text of publication follows: This paper aims to present the methodology and criteria used for the destination, discard and reuse of waste from the remediation activities of soil contaminated by radioactive waste of low activity in the USIN Plant. The site is located in Sao Paulo city, the city with the largest population of Brazil, with approximately 11 million inhabitants. As the environmental agency in Sao Paulo state, in this neighborhood there are several cases of severe contamination of soil and groundwater. The situation of contamination is so severe that it is forbidden the use of groundwater in the region for an indefinite period. Site of the plant running in a monazite processing plant for extraction of rare earths, have been filed across the land several fractions of soil containing monazite sand. In order to guide the remediation of the area for unrestricted use, was a plan for remediation of radioactive waste characterization based on geological, hydrogeological and environmental extensive in the area. From the calculation of the dose was established that the fractions of soil with concentrations of 226 Ra and 228 Ra below 0.5 Bq/g result in additional effective dose less than 1.0 mSv/yr and therefore can be kept on the ground

Inorganic ion exchangers for nuclear waste remediation

Energy Technology Data Exchange (ETDEWEB)

Clearfield, A.; Bortun, A.; Bortun, L.; Behrens, E. [Texas A& M Univ., College Station, TX (United States)

1997-10-01

The objective of this work is to provide a broad spectrum of inorganic ion exchangers that can be used for a range of applications and separations involving remediation of groundwater and tank wastes. The authors intend to scale-up the most promising exchangers, through partnership with AlliedSignal Inc., to provide samples for testing at various DOE sites. While much of the focus is on exchangers for removal of Cs{sup +} and Sr{sup 2+} from highly alkaline tank wastes, especially at Hanford, the authors have also synthesized exchangers for acid wastes, alkaline wastes, groundwater, and mercury, cobalt, and chromium removal. These exchangers are now available for use at DOE sites. Many of the ion exchangers described here are new, and others are improved versions of previously known exchangers. They are generally one of three types: (1) layered compounds, (2) framework or tunnel compounds, and (3) amorphous exchangers in which a gel exchanger is used to bind a fine powder into a bead for column use. Most of these exchangers can be regenerated and used again.

Tank waste remediation system programmatic risk management plan

International Nuclear Information System (INIS)

Seaver, D.A.

1995-01-01

This risk management plan defines the approach to be taken to managing risks in the Tank Waste Remediation System (TWRS) program. It defines the actions to be taken at the overall program level, and the risk management requirements for lower-level projects and other activities. The primary focus of this plan is on ''programmatic'' risks, i.e., risks with respect to the cost, schedule, and technical performance of the program. The plan defines an approach providing managers with the flexibility to manage risks according to their specific needs, yet creates. The consistency needed for effectiveness across the program. The basic risk management approach uses a risk management list for the program, each project, and additional lower-level activities. The risk management list will be regularly reviewed and updated by appropriate level of management. Each list defines key risks, their likelihood and consequences, risk management actions to be taken, responsible individuals, and other management information

Strategy paper. Remedial design/remedial action 100 Area. Revision 2

International Nuclear Information System (INIS)

Donahoe, R.L.

1995-10-01

This strategy paper identifies and defines the approach for remedial design and remedial action (RD/RA) for source waste sites in the 100 Area of the Hanford Site, located in southeastern Washington State. This paper provides the basis for the US Department of Energy (DOE) to assess and approve the Environmental Restoration Contractor's (ERC) approach to RD/RA. Additionally, DOE is requesting review/agreement from the US Environmental Protection Agency (EPA) and Washington State Department of Ecology (Ecology) on the strategy presented in this document in order to expedite remedial activities

Gas cylinder disposal pit remediation waste minimization and management

International Nuclear Information System (INIS)

Alas, C.A.; Solow, A.; Criswell, C.W.; Spengler, D.; Brannon, R.; Schwender, J.M.; Eckman, C.K.; Rusthoven, T.

1995-01-01

A remediation of a gas cylinder disposal pit at Sandia National Laboratories, New Mexico has recently been completed. The cleanup prevented possible spontaneous releases of hazardous gases from corroded cylinders that may have affected nearby active test areas at Sandia's Technical Area III. Special waste management, safety, and quality plans were developed and strictly implemented for this project. The project was conceived from a waste management perspective, and waste minimization and management were built into the planning and implementation phases. The site layout was planned to accommodate light and heavy equipment, storage of large quantities of suspect soil, and special areas to stage and treat gases and reactive chemicals removed from the pit, as well as radiation protection areas. Excavation was a tightly controlled activity using experienced gas cylinder and reactive chemical specialists. Hazardous operations were conducted at night under lights, to allow nearby daytime operations to function unhindered. The quality assurance plan provided specific control of, and documentation for, critical decisions, as well as the record of daily operations. Both hand and heavy equipment excavation techniques were utilized. Hand excavation techniques were utilized. Hand excavation techniques allows sealed glass containers to be exhumed unharmed. In the end, several dozen thermal batteries; 5 pounds (2.3 kg) of lithium metal; 6.6 pounds (3.0 kg) of rubidium metal; several kilograms of unknown chemicals; 140 cubic yards (107 cubic meters) of thorium-contaminated soil; 270 cubic yards (205 cubic meters) of chromium-contaminated soil; and 450 gas cylinders, including 97 intact cylinders containing inert, flammable, toxic, corrosive, or oxidizing gases were removed and effectively managed to minimize waste

Electrokinetic remediation of plutonium-contaminated nuclear site wastes: Results from a pilot-scale on-site trial

International Nuclear Information System (INIS)

Agnew, Kieran; Cundy, Andrew B.; Hopkinson, Laurence; Croudace, Ian W.; Warwick, Phillip E.; Purdie, Philip

2011-01-01

This paper examines the field-scale application of a novel low-energy electrokinetic technique for the remediation of plutonium-contaminated nuclear site soils, using soil wastes from the Atomic Weapons Establishment (AWE) Aldermaston site, Berkshire, UK as a test medium. Soils and sediments with varying composition, contaminated with Pu through historical site operations, were electrokinetically treated at laboratory-scale with and without various soil pre-conditioning agents. Results from these bench-scale trials were used to inform a larger on-site remediation trial, using an adapted containment pack with battery power supply. 2.4 m 3 (ca. 4 tonnes) of Pu-contaminated soil was treated for 60 days at a power consumption of 33 kW h/m 3 , and then destructively sampled. Radiochemical data indicate mobilisation of Pu in the treated soil, and migration (probably as a negatively charged Pu-citrate complex) towards the anodic compartment of the treatment cell. Soil in the cathodic zone of the treatment unit was remediated to a level below free-release disposal thresholds (1.7 Bq/g, or <0.4 Bq/g above background activities). The data show the potential of this method as a low-cost, on-site tool for remediation of radioactively contaminated soils and wastes which can be operated remotely on working sites, with minimal disruption to site infrastructure or operations.

Mitigation action plan for 300-FF-1 remedial action

International Nuclear Information System (INIS)

Weiss, S.G.

1996-10-01

A record of decision was issued (dated July 1996), for remediation of waste sites in the 300-FF-1 Operable Unit in the 300 Area of the Hanford Site. The selected remedies for the 300-FF-1 and 300-FF-5 waste sites include selective excavation and disposal of contaminated soil and debris from the process waste units, excavation and removal of the 618-4 Burial Ground, and institutional controls for groundwater. This mitigation action plan explains how cultural resources will be managed and how revegetation for these remedial activities will be planned

Experimental logistics plan in support of Extensive Separations for Hanford tank waste remediation systems

International Nuclear Information System (INIS)

Enderlin, W.I.; Swanson, J.L.; Carlson, C.D.; Hirschi, E.J.

1993-12-01

All proposed methods for remediating the radioactive and chemical waste stored in single- and double-shell tanks (SSTs and DSTs) at the Hanford Site require the separation of the waste mixtures in the tank into high-level and low-level fractions, the safe transport of this separated waste to appropriate immobilization facilities, and the long-term disposal of the immobilized waste forms. Extensive experimentation, especially in waste separations, will be required to develop the technologies and to produce the data that support the most effective and safe cleanup processes. As part of this effort, Pacific Northwest Laboratory (PNL) is developing this detailed experimental logistics plan to determine the logistical/resource requirements, and ultimately the critical paths, necessary to effectively and safely conduct the multitude of experiments within the Extensive Separations Development Program, which addresses the experimental needs of a concept that provides a high degree of separation for the high-level and low-level waste fractions. The logistics issues developed for this program are expected to be similar to those for other programs aimed at remediating and disposing of the wastes

Tailings From Mining Activities, Impact on Groundwater, and Remediation

Directory of Open Access Journals (Sweden)

Khalid Al-Rawahy

2001-12-01

Full Text Available Effluent wastes from mining operations and beneficiation processes are comprized mostly of the following pollutants: total suspended solids (TTS, alkalinity or acidity (pH, settleable solids, iron in ferrous mining, and dissolved metals in nonferrous mining. Suspended solids consist of small particles of solid pollutants that resist separation by conventional means. A number of dissolved metals are considered toxic pollutants. The major metal pollutants present in ore mining and beneficiation waste waters include arsenic, cadmium, copper, lead, mercury, nickel, and zinc. Tailings ponds are used for both the disposal of solid waste and the treatment of waste-water streams. The supernatant decanted from these ponds contains suspended solids and, at times, process reagents introduced to the water during ore beneficiation. Leakage of material from tailings pond into groundwater is one possible source of water pollution in the mining industry. Percolation of waste-water from impoundment may occur if tailings ponds are not properly designed. This paper addresses potential groundwater pollution due to effluent from mining activities, and the possible remediation options.

Design requirements document for Project W-465, immobilized low-activity waste interim storage

International Nuclear Information System (INIS)

Burbank, D.A.

1998-01-01

The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

Waste Management Plan for the Oak Ridge National Remedial Investigation/Feasibility Study

International Nuclear Information System (INIS)

1988-04-01

In accordance with the requirements of the Remedial Investigation/Feasibility Study (RI/FS) Project Quality Assurance Plan, this Waste Management Plan establishes clear lines of responsibility and authority, documentation requirements, and operational guidance for the collection, identification, segregation, classification, packaging, certification, and storage/disposal of wastes. These subjects are discussed in the subsequent sections of this document

Waste Management Plan for the Oak Ridge National Remedial Investigation/Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

1988-04-01

In accordance with the requirements of the Remedial Investigation/Feasibility Study (RI/FS) Project Quality Assurance Plan, this Waste Management Plan establishes clear lines of responsibility and authority, documentation requirements, and operational guidance for the collection, identification, segregation, classification, packaging, certification, and storage/disposal of wastes. These subjects are discussed in the subsequent sections of this document.

Remediation of hazardous waste sites by heap leaching

International Nuclear Information System (INIS)

Samani, Z.; Hanson, A.; Dwyer, B.

1994-01-01

Efforts are being made to devise technologies and treatment systems to remediate contaminated soil-on site without generating significant wastes for off-site disposal. Heap leaching, a technique used extensively in the mining industry, has been investigated as a method for remediation of hazardous chemical contamination of the vadose zone. In the mining industry, metal-bearing ore is excavated and mounded on a pad. The metals are removed by passing a special leaching solution through the ore. In this study, the removal of chromium(VI) from the New Mexico soils (sand, sandy loam, and clay) using heap leaching was evaluated at a column scale. The heap leaching study demonstrated greater than 99% removal of Cr(VI) from all three soils using tap water as the leaching agent. (author) 13 figs., 5 tabs., 21 refs

DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary

International Nuclear Information System (INIS)

DeMuth, S.F.

1996-10-01

This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2

Energy Technology Data Exchange (ETDEWEB)

Lewis, BE

2003-10-07

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List

Methodology for generating waste volume estimates

International Nuclear Information System (INIS)

Miller, J.Q.; Hale, T.; Miller, D.

1991-09-01

This document describes the methodology that will be used to calculate waste volume estimates for site characterization and remedial design/remedial action activities at each of the DOE Field Office, Oak Ridge (DOE-OR) facilities. This standardized methodology is designed to ensure consistency in waste estimating across the various sites and organizations that are involved in environmental restoration activities. The criteria and assumptions that are provided for generating these waste estimates will be implemented across all DOE-OR facilities and are subject to change based on comments received and actual waste volumes measured during future sampling and remediation activities. 7 figs., 8 tabs

Remediation of phosphorus from electric furnace waste streams

International Nuclear Information System (INIS)

Hanna, J.; Jung, J.O.

1992-01-01

Electrothermal production of elemental phosphorus (P4) generates substantial amounts of highly toxic phossy water sludge, slag and other gaseous wastes. Because of their high phosphorus content the sludges pose potential fire hazards. In the absence of a reliable processing technology, large amounts of these hazardous wastes are accumulated at an annual rate of 1.5-2.5 million tons from current and past operations. The accumulated sludges are stored in ponds or in special containment vessels in 30 locations in 18 states including Alabama, California, Tennessee, Idaho and Montana. Serious water pollution problems will result unless these wastes are given extensive treatment to remove the elemental phosphorus. Federal regulations prohibit permanent storage of flammable wastes. This paper reports that recently, researchers at the University of Alabama have developed a two-step method for the treatment of phosphorus sludge that includes bulk removal of phosphorus by physical separation techniques followed by remediation of the residual P4 in the sludge using a novel wet air oxidation technique known as HSAD

Minutes from Department of Energy/Hazardous Waste Remedial Actions Program research and development technology needs assessment review meeting

International Nuclear Information System (INIS)

1989-01-01

On November 1--2, 1988, representatives of the Department of Energy (DOE) Headquarters, DOE Operations Offices, DOE contractors, and the Hazardous Waste Remedial Actions Program met in Salt Lake City, Utah, to select and prioritize candidate waste problems in need of research and development. The information gained will be used in planning for future research and development tasks and in restructuring current research activities to address the priority needs. All Operations Offices were represented by DOE staff and by contractor delegates from the area. This document summarizes the results of the meeting and lists the priority waste problems established

Waste site characterization and remediation: Problems in developing countries

Energy Technology Data Exchange (ETDEWEB)

Kalavapudi, M. [ENVIROSYS, Gaithersburg, MD (United States); Iyengar, V. [Biomineral Sciences International Inc., Bethesda, MD (United States)

1996-12-31

Increased industrial activities in developing countries have degraded the environment, and the impact on the environment is further magnified because of an ever-increasing population, the prime receptors. Independent of the geographical location, it is possible to adopt effective strategies to solve environmental problems. In the United States, waste characterization and remediation practices are commonly used for quantifying toxic contaminants in air, water, and soil. Previously, such procedures were extraneous, ineffective, and cost-intensive. Reconciliation between the government and stakeholders, reinforced by valid data analysis and environmental exposure assessments, has allowed the {open_quotes}Brownfields{close_quotes} to be a successful approach. Certified reference materials and standard reference materials from the National Institute of Standards (NIST) are indispensable tools for solving environmental problems and help to validate data quality and the demands of legal metrology. Certified reference materials are commonly available, essential tools for developing good quality secondary and in-house reference materials that also enhance analytical quality. This paper cites examples of environmental conditions in developing countries, i.e., industrial pollution problems in India, polluted beaches in Brazil, and deteriorating air quality in countries, such as Korea, China, and Japan. The paper also highlights practical and effective approaches for remediating these problems. 23 refs., 7 figs., 1 tab.

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume II

International Nuclear Information System (INIS)

1996-08-01

This document, Volume 2, provides the inventory of waste addressed in this Final Environmental Impact Statement (EIS) for the Tank Waste Remediation System, Hanford Site, Richland, Washington. The inventories consist of waste from the following four groups: (1) Tank waste; (2) Cesium (Cs) and Strontium (Sr) capsules; (3) Inactive miscellaneous underground storage tanks (MUSTs); and (4) Anticipated future tank waste additions. The major component by volume of the overall waste is the tank waste inventory (including future tank waste additions). This component accounts for more than 99 percent of the total waste volume and approximately 70 percent of the radiological activity of the four waste groups identified previously. Tank waste data are available on a tank-by-tank basis, but the accuracy of these data is suspect because they primarily are based on historical records of transfers between tanks rather than statistically based sampling and analyses programs. However, while the inventory of any specific tank may be suspect, the overall inventory for all of the tanks combined is considered more accurate. The tank waste inventory data are provided as the estimated overall chemical masses and radioactivity levels for the single-shell tanks (SSTs) and double-shell tanks (DSTs). The tank waste inventory data are broken down into tank groupings or source areas that were developed for analyzing groundwater impacts

Tank waste remediation system nuclear criticality safety inspection and assessment plan

International Nuclear Information System (INIS)

VAIL, T.S.

1999-01-01

This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506

International Nuclear Information System (INIS)

Beres, Christopher M.; Fort, E. Joseph; Boyle, James D.

2013-01-01

The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506

Energy Technology Data Exchange (ETDEWEB)

Beres, Christopher M.; Fort, E. Joseph [Cabrera Services, Inc., 473 Silver Lane, East Hartford, CT 06118 (United States); Boyle, James D. [United States Army Corps of Engineers - Buffalo, 1776 Niagara Street, Buffalo, NY 14207 (United States)

2013-07-01

The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 2: Final report

International Nuclear Information System (INIS)

Peters, B.B.; Cameron, R.J.; McCormack, W.D.

1994-08-01

The objective of DOE's Radioactive Waste Tank Remediation Technology Focus Area is to identify and develop new technologies that will reduce the risk and/or cost of remediating DOE underground waste storage tanks and tank contents. There are, however, many more technology investment opportunities than the current budget can support. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program. The report identifies the project objectives and provides a description of the model. Development of the first ''demonstration'' version of this model and a trial application have been completed and the results are presented. This model will continue to evolve as it undergoes additional user review and testing

Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 2: Final report

Energy Technology Data Exchange (ETDEWEB)

Peters, B.B.; Cameron, R.J.; McCormack, W.D. [Enserch Environmental Corp., Richland, WA (United States)

1994-08-01

The objective of DOE`s Radioactive Waste Tank Remediation Technology Focus Area is to identify and develop new technologies that will reduce the risk and/or cost of remediating DOE underground waste storage tanks and tank contents. There are, however, many more technology investment opportunities than the current budget can support. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program. The report identifies the project objectives and provides a description of the model. Development of the first ``demonstration`` version of this model and a trial application have been completed and the results are presented. This model will continue to evolve as it undergoes additional user review and testing.

Environmental health: an analysis of available and proposed remedies for victims of toxic waste contamination

International Nuclear Information System (INIS)

Hurwitz, W.J.

1981-01-01

Past and present residents of the Love Canal area near Niagara Falls, New York, fear that they and their homes have been contaminated by toxic wastes seeping out from nearby chemical disposal sites. Hundreds of landfills nationwide are as potentially dangerous as Love Canal. In the absence of a statutory remedy, victims of contamination must rely upon common law theories of lability in order to recover damages for injuries suffered as a result of toxic waste contamination. This Note examines the merits and deficiencies of four common law theories: negligence, strict liability, nuisance and trespass. The Note concludes that none of these remedies is adequate to assure recovery to a person injured by toxic waste disposal, and recommends that legislation be adopted to ensure that victims of toxic waste contamination can be compensated for their injuries

FY 1995 Remedial Investigation Work Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Watkins, D.R.; Herbes, S.E.

1994-12-01

The purpose of this project is to provide key information needed by decision makers to expedite the process of environmental restoration and to provide the data base required by the Remedial Investigation/Feasibility Study (RI/FS) for Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL). WAG 2 is the major drainage system downgradient of other WAGs that contain significant sources of contamination at ORNL. Field activities to support the remedial investigation for the RI portion include characterization of the nature and extent of contamination in WAG 2 [consisting of White Oak Creek (WOC) and associated tributaries and floodplain, White Oak Lake (WOL), and White Oak Creek Embayment (WOCE)], specifically to support risk-based remediation decisions. The project consists of three phases: Phase 1, initial scoping characterization to determine the need for early action; Phase 2, interim activities during remediation of upslope WAGs to evaluate potential changes in the contamination status of WAG 2 that would necessitate revaluation of the need for early action; and Phase 3, completion of the RI process following remediation of upslope WAGs. Overall RI objectives, consistent with ORNL Environmental Restoration (ER) Program strategic objectives to reduce risks and comply with environmental regulations, are discussed in the WAG 2 Remedial Investigation Plan

Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume IV

International Nuclear Information System (INIS)

1996-08-01

This document, Volume 4, describes the current safety concerns associated with the tank waste and analyzes the potential accidents and associated potential health effects that could occur under the alternatives included in this Tank Waste Remediation System (TWRS) Final Environmental Impact Statement (EIS) for the Hanford Site, Richland, Washington

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

REMEDIAL ACTION, TREATMENT AND DISPOSAL OF HAZARDOUS WASTE: PROCEEDINGS OF THE SIXTEENTH ANNUAL HAZARDOUS WASTE RESEARCH SYMPOSIUM

Science.gov (United States)

The Sixteenth Annual Research Symposium on Remedial Action, Treatment and Disposal of Hazardous Waste was held in Cincinnati, Ohio, April 3-5, 1990. he purpose of this Symposium was to present the latest significant research findings from ongoing and recently completed projects f...

Environmental Restoration Remedial Actions Program Field Office Work Plan

International Nuclear Information System (INIS)

1989-02-01

The Environmental Restoration Remedial Actions (ERRA) Program was established by DP to comply with regulations for characterization and cleanup of inactive waste sites. The program specifically includes inactive site identification and characterization, technology development and demonstration, remedial design and cleanup action, and postclosure activities of inactive radioactive, chemically hazardous, and mixed waste sites. It does not include facility decontamination and decommissioning activities; these are included in a parallel program, Environmental Restoration Decontamination and Decommissioning (ERD and D), also managed by DP. The ERRA program was formally established in fiscal year (FY) 1988 at the Hanford Site to characterize and remediate inactive waste sites at Hanford. The objectives, planned implementation activities, and management planning for the ERRA Program are contained in several planning documents. These documents include planning for the national program and for the Hanford Program. This summary describes the major documents and the role and purpose of this Field Office Work Plan (FOWP) within the overall hierarchy of planning documents. 4 refs., 7 figs., 8 tabs

Environmental remediation and waste management information systems

Energy Technology Data Exchange (ETDEWEB)

Harrington, M.W.; Harlan, C.P.

1993-12-31

The purpose of this paper is to document a few of the many environmental information systems that currently exist worldwide. The paper is not meant to be a comprehensive list; merely a discussion of a few of the more technical environmental database systems that are available. Regulatory databases such as US Environmental Protection Agency`s (EPA`s) RODS (Records of Decision System) database [EPA, 1993] and cost databases such as EPA`s CORA (Cost of Remedial Action) database [EPA, 1993] are not included in this paper. Section 2 describes several US Department of Energy (DOE) Environmental Restoration and Waste Management (EM) information systems and databases. Section 3 discusses several US EPA information systems on waste sites and technologies. Section 4 summarizes a few of the European Community environmental information systems, networks, and clearinghouses. And finally, Section 5 provides a brief overview of Geographical Information Systems. Section 6 contains the references, and the Appendices contain supporting information.

Environmental remediation and waste management information systems

International Nuclear Information System (INIS)

Harrington, M.W.; Harlan, C.P.

1993-01-01

The purpose of this paper is to document a few of the many environmental information systems that currently exist worldwide. The paper is not meant to be a comprehensive list; merely a discussion of a few of the more technical environmental database systems that are available. Regulatory databases such as US Environmental Protection Agency's (EPA's) RODS (Records of Decision System) database [EPA, 1993] and cost databases such as EPA's CORA (Cost of Remedial Action) database [EPA, 1993] are not included in this paper. Section 2 describes several US Department of Energy (DOE) Environmental Restoration and Waste Management (EM) information systems and databases. Section 3 discusses several US EPA information systems on waste sites and technologies. Section 4 summarizes a few of the European Community environmental information systems, networks, and clearinghouses. And finally, Section 5 provides a brief overview of Geographical Information Systems. Section 6 contains the references, and the Appendices contain supporting information

Waste management plan for the remedial investigation/feasibility study of Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1992-12-01

This plan defines the criteria and methods to be used for managing waste generated during activities associated with Waste Area Grouping (WAG) 5 at Oak Ridge National Laboratory (ORNL). WAG 5 is located in Melton Valley, south of the main ORNL plant area. It contains 17 solid waste management units (SWMUs) to be evaluated during the remedial investigation. The SWMUs include three burial areas, two hydrofracture facilities, two settling ponds, eight tanks, and two low-level liquid waste leak sites. These locations are all considered to be within the WAG 5 area of contamination (AOC). The plan contains provisions for safely and effectively managing soils, rock cuttings, development and sampling water, decontamination fluids, and disposable personal protective equipment (PPE) consistent with the Environmental Protection Agency (EPA) guidance of May 1991 (EPA 1991). Consistent with EPA guidance, this plan is designed to protect the environment and the health and safety of workers and the public

Research in Support of Remediation Activities at the Savannah River Site

International Nuclear Information System (INIS)

Seaman, J.C.; B.B. Looney and M.K. Harris

2007-01-01

The USDOE Savannah River Site (SRS), an 803-km 2 (310-mile 2 ) facility located south of Aiken, SC on the upper Atlantic Coastal Plain and bounded to the west by the Savannah River, was established in the 1950s for the production and refinement of nuclear materials. To fulfill this mission during the past 50 years SRS has operated five nuclear reactors, two large chemical separation areas, waste disposal facilities (landfills, waste ponds, waste tanks, and waste stabilization), and a large number of research and logistics support facilities. Contaminants of concern (COC) resulting from site operations include chlorinated solvents, radionuclides, metals, and metalloids, often found as complex mixtures that greatly complicate remediation efforts when compared with civilian industries. The objective of this article is to provide a description of the lithology and hydrostratigraphy of the SRS, as well as a brief history of site operations and research activities as a preface to the current special section of Vadose Zone Journal (VZJ) dedicated to SRS, focusing mainly on issues that are unique to the USDOE complex. Contributions to the special section reflect a diverse range of topics, from hydrologic tracer experiments conducted both within the vadose and saturated zones to studies specifically aimed at identifying geochemical processes controlling the migration and partitioning of specific contaminants (e.g., TCE, 137 Cs, U, and Pu) in SRS subsurface environments. Addressing the diverse environmental challenges of the SRS provides a unique opportunity to conduct both fundamental and applied research across a range of experimental scales. Hence, the SRS has been a pioneering force in several areas of environmental research and remediation, often through active interdisciplinary collaboration with researchers from other USDOE facilities, academic and federal institutions, and commercial entities

Targeted Health Assessment for Wastes Contained at the Niagara Falls Storage Site to Guide Planning for Remedial Action Alternatives - 13428

Energy Technology Data Exchange (ETDEWEB)

Busse, John; Keil, Karen; Staten, Jane; Miller, Neil; Barker, Michelle [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States); MacDonell, Margaret; Peterson, John; Chang, Young-Soo; Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01

The U.S. Army Corps of Engineers (USACE) is evaluating potential remedial alternatives at the 191-acre Niagara Falls Storage Site (NFSS) in Lewiston, New York, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Manhattan Engineer District (MED) and Atomic Energy Commission (AEC) brought radioactive wastes to the site during the 1940's and 1950's, and the U.S. Department of Energy (US DOE) consolidated these wastes into a 10-acre interim waste containment structure (IWCS) in the southwest portion of the site during the 1980's. The USACE is evaluating remedial alternatives for radioactive waste contained within the IWCS at the NFSS under the Feasibility Study phase of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process. A preliminary evaluation of the IWCS has been conducted to assess potential airborne releases associated with uncovered wastes, particularly during waste excavation, as well as direct exposures to uncovered wastes. Key technical issues for this assessment include: (1) limitations in waste characterization data; (2) representative receptors and exposure routes; (3) estimates of contaminant emissions at an early stage of the evaluation process; (4) consideration of candidate meteorological data and air dispersion modeling approaches; and (5) estimates of health effects from potential exposures to both radionuclides and chemicals that account for recent updates of exposure and toxicity factors. Results of this preliminary health risk assessment indicate if the wastes were uncovered and someone stayed at the IWCS for a number of days to weeks, substantial doses and serious health effects could be incurred. Current controls prevent such exposures, and the controls that would be applied to protect onsite workers during remedial action at the IWCS would also effectively protect the public nearby. This evaluation provides framing context for the upcoming development and detailed

Buried waste remediation: A new application for in situ vitrification

International Nuclear Information System (INIS)

Kindle, C.H.; Thompson, L.E.

1991-04-01

Buried wastes represent a significant environmental concern and a major financial and technological challenge facing many private firms, local and state governments, and federal agencies. Numerous radioactive and hazardous mixed buried waste sites managed by the US Department of Energy (DOE) require timely clean up to comply with state or federal environmental regulations. Hazardous wastes, biomedical wastes, and common household wastes disposed at many municipal landfills represent a significant environmental health concern. New programs and regulations that result in a greater reduction of waste via recycling and stricter controls regarding generation and disposal of many wastes will help to stem the environmental consequences of wastes currently being generated. Groundwater contamination, methane generation, and potential exposures to biohazards and chemically hazardous materials from inadvertent intrusion will continue to be potential environmental health consequences until effective and permanent closure is achieved. In situ vitrification (ISV) is being considered by the DOE as a permanent closure option for radioactive buried waste sites. The results of several ISV tests on simulated and actual buried wastes conducted during 1990 are presented here. The test results illustrate the feasibility of the ISV process for permanent remediation and closure of buried waste sites in commercial landfills. The tests were successful in immobilizing or destroying hazardous and radioactive contaminants while providing up to 75 vol % waste reduction. 6 refs., 7 figs., 5 tabs

The Rush to Remediate: Long Term Performance Favors Passive Systems at SRS

International Nuclear Information System (INIS)

Hoffman, D.; Cauthen, K.; Beul, R. R.

2003-01-01

The purpose of this paper is to describe the long-term performance of groundwater remediation systems at SRS and compare active versus passive systems. The presentation will focus on the limited effectiveness of active pump and treat systems and share the experience with more passive and natural systems such as soil vapor extraction, barometric pumping, bioremediation, and phytoremediation. Three remediation projects are presented. In each case the waste source is capped with clay or synthetic barriers; however, extensive groundwater contamination remains. The first project features the cleanup of the largest plume in the United States. The second project entails solvent and vinyl chloride remediation of groundwater beneath a hazardous waste landfill. The third project discusses tritium containment from a 160-acre radioactive waste disposal area. Special emphasis is placed on performance data from alternate technology cleanup. The goals are to share remediation data, successes and lessons learned, while making a case for passive systems use in groundwater remediation

Measurement systems in the area of land remediation and soil segregation activities

International Nuclear Information System (INIS)

Simon, Gerold G.; Sokcic-Kostic, Marina; Auler, Ingolf; Eickelpasch, Ludger; Betts, Jonathan

2007-01-01

Available in abstract form only. Full text of publication follows: The remediation of radioactively contaminated land is a small but growing sector in the area of decommissioning of nuclear facilities. This also includes the material from buildings after demolition. Contamination comprises in general alpha and beta activities and emission of alpha, beta and gamma radiation. The measurement is in practice restricted to the measurement of gamma emission, because of the high penetration of material by gamma rays. All isotopes, which do not emit gammas are estimated on the basis of given relation between alpha and beta emitters without gamma radiation and emitters with gamma radiation. This method is called 'key nuclide method'. Whilst many studies have been completed, others still continue in the processing of large volumes of concrete, steel and soil. An important conclusion from these and similar research programs is that a significant proportion of the waste contains only low concentrations of radioactive nuclides. Therefore, much of the material from the remediation can be considered for 'free release'. It was often not possible to attain adequate specific information on these materials, so a measurement system is needed for their classification and characterization. NUKEM Technologies has practical experience in characterising and remediating of nuclear sites. Recently, it has pioneered the use of innovative in-situ and ex-situ characterisation and waste segregation technologies, which enhance the efficiency of remedial actions and provide assurance to customers, regulators and the public that all significant contamination has been removed and sites can be used for new purposes. (authors)

UNITED STATES AND GERMAN BILATERAL AGREEMENT ON REMEDIATION OF HAZARDOUS WASTE SITES

Science.gov (United States)

The U.S. Environmental Protection Agency (EPA) and Germany's Bundesministerium fur Forschung und Technologie (BMFT) are involved in a collaborative effort called the U.S. and German Bilateral Agreement on Remediation of Hazardous Waste Sites. he purpose of this interim status rep...

Integration of Environmental Restoration and Waste Management Activities for a More Cost-Effective Tank Remediation Program Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Brill, A.; Clark, R.; Stewart, R.

1998-01-01

This paper presents plans and strategies for remediation of the liquid low-level radioactive waste (LLLW) tanks that have been removed from service (also known as inactive tanks) at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. Much of the LLLW system at ORNL was installed more than 50 years ago. The overall objective of the Inactive Tank Program is to remediate all LLLW tanks that have been removed from service to the extent practicable in accordance with the regulatory requirements

Buried Waste Integrated Demonstration

International Nuclear Information System (INIS)

1994-03-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that offer promising solutions to the problems associated with the remediation of buried waste. BWID addresses the difficult remediation problems associated with DOE complex-wide buried waste, particularly transuranic (TRU) contaminated buried waste. BWID has implemented a systems approach to the development and demonstration of technologies that will characterize, retrieve, treat, and dispose of DOE buried wastes. This approach encompasses the entire remediation process from characterization to post-monitoring. The development and demonstration of the technology is predicated on how a technology fits into the total remediation process. To address all of these technological issues, BWID has enlisted scientific expertise of individuals and groups from within the DOE Complex, as well as experts from universities and private industry. The BWID mission is to support development and demonstration of a suite of technologies that, when integrated with commercially-available technologies, forms a comprehensive, remediation system for the effective and efficient remediation of buried waste throughout the DOE Complex. BWID will evaluate and validate demonstrated technologies and transfer this information and equipment to private industry to support the Office of Environmental Restoration (ER), Office of Waste Management (WM), and Office of Facility Transition (FT) remediation planning and implementation activities

Oxalic acid as an assisting agent for the electrodialytic remediation of chromated copper arsenate treated timber waste

DEFF Research Database (Denmark)

Ribeiro, Alexandra B.; Mateus, Eduardo P.; Ottosen, Lisbeth M.

1999-01-01

The electrodialytic process is proposed as a technique for the remediation of chromated copper arsenate treated timber waste, using oxalic acid as assisting agent. The method prowed succesfull 93% Cu, 95% Cr and 99% As was removed from the timber.......The electrodialytic process is proposed as a technique for the remediation of chromated copper arsenate treated timber waste, using oxalic acid as assisting agent. The method prowed succesfull 93% Cu, 95% Cr and 99% As was removed from the timber....

Status of international environmental remediation activities: A report from the Prague conference

International Nuclear Information System (INIS)

Slate, S.C.; Thornhill, C.K.; Allen, R.E.

1993-10-01

The Prague Conference on nuclear waste management and environmental remediation provided extensive interchange of ideas and insight into new technologies and management approaches throughout the world. A variety of environmental remediation technologies have potential application to Department of Energy facilities; others illustrate pitfalls to be avoided. This paper presents the highlights from the first environmental remediation (ER) technical program in the American Society of Mechanical Engineers' series of international nuclear waste management conferences. This program covers ER technologies, decontamination and decommissioning (D ampersand D) technologies and experience, ER site characterization and modeling, management of and results from actual clean up actions, and data on several major international environmental problems. Focusing on direct benefits to the Department of Energy's (DOE) ER Program, this paper summarizes pertinent technical information, identifies useful technical papers, lists key technical contacts, and identifies specific actions to obtain additional information. US attendance at meetings like this is normally quite limited compared to attendance at North American meetings. The purpose of this paper then is to increase general awareness of this meeting in US technical circles and to broadly disseminate key information to US ER programs and contractors. To do this, the paper is organized to present background information on the conference itself, document the beneficial technical information, and outline ongoing information exchange activities

SAFETY ANALYSIS APPROACH TO TANK 241-SY-101 REMEDIATION ACTIVITIES

International Nuclear Information System (INIS)

RYAN, G.W.

2000-01-01

An Unreviewed Safety Question was declared related to the unexplained waste surface level growth in high-level radioactive waste storage Tank 241-SY-101 at the Hanford Site in Richland, Washington. Because the waste surface level in Tank 241-SY-101 was growing in a manner inconsistent with previous behavior, the following issues of concern were recognized: (1) The continually rising surface level had the potential to reach physical encumbrances or limits within the tank (e.g., instrumentation, cameras, established Authorization Basis limits, and the double containment boundary) and the potential to significantly change the consequences of previously analyzed accidents (e.g., flammable gas deflagrations). (2) The presence of new hazards because of significant quantities of flammable gas retained in the crust (e.g., crust collapse gas-release events). (3) The potential to inhibit information gathering related to the existing hazards in the tank (e.g., unable to determine surface level to assess the potential for large gas releases). In response to this situation, a Contractor Project Team, which included Department of Energy representation, was formed to constructively address the issue. The team was responsible for developing and evaluating remediation options and executing the chosen option for remediating the surface level rise issue for Tank 241-SY-101. From an Authorization Basis perspective, the following important aspects will be discussed in this paper: (1) The integrated nature of the Project Team. The team consisted of all the organizations necessary to ensure that the time available to remediate Tank 241-SY-101 was effectively used. Most notable is the connectivity of the Nuclear Safety and Licensing organization with the Engineering, Design, and Operations organizations. (2) The ability of the safety analysis support to adjust to and address evolving Project Team goals and dynamic tank conditions. (3) Due to the urgency to mitigate this developing issue

Tank waste remediation system nuclear criticality safety program management review

International Nuclear Information System (INIS)

BRADY RAAP, M.C.

1999-01-01

This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico

International Nuclear Information System (INIS)

DOTSON, PATRICK WELLS; GALLOWAY, ROBERT B.; JOHNSON JR, CARL EDWARD

1999-01-01

This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where

Maxey Flats low-level waste disposal site closure activities

International Nuclear Information System (INIS)

Haight, C.P.; Mills, D.; Razor, J.E.

1987-01-01

The Maxey Flats Radioactive Waste Disposal Facility in Fleming County, Kentucky is in the process of being closed. The facility opened for commercial business in the spring of 1963 and received approximately 4.75 million cubic feet of radioactive waste by the time it was closed in December of 1977. During fourteen years of operation approximately 2.5 million curies of by-product material, 240,000 kilograms of source material, and 430 kilograms of special nuclear material were disposed. The Commonwealth purchased the lease hold estate and rights in May 1978 from the operating company. This action was taken to stabilize the facility and prepare it for closure consisting of passive care and monitoring. To prepare the site for closure, a number of remedial activities had to be performed. The remediation activities implemented have included erosion control, surface drainage modifications, installation of a temporary plastic surface cover, leachate removal, analysis, treatment and evaporation, US DOE funded evaporator concentrates solidification project and their on-site disposal in an improved disposal trench with enhanced cover for use in a humid environment situated in a fractured geology, performance evaluation of a grout injection demonstration, USGS subsurface geologic investigation, development of conceptual closure designs, and finally being added to the US EPA National Priority List for remediation and closure under Superfund. 13 references, 3 figures

Environmental remediation activities at the Ningyo-toge Uranium Mine, Japan

International Nuclear Information System (INIS)

Saito, Hiroshi; Taki, Tomohiro

2011-01-01

Ningyo-toge Uranium Mine is subject to the environmental remediation. The main purposes are to take measures to ensure the radiation protection from the exposure pathways to humans in future, and to prevent the occurrence of mining pollution. The Mill Tailings Pond in the Ningyo-toge Uranium Mine has deposited mining waste and impounded water as a buffer reservoir before it is transferred to the Water Treatment Facility. It is located at the upstream of the water-source river, and therefore, for the environmental remediation, the highest priority has been put to it among many facilities in the Mine. So far, basic concept has been examined and planning has been carried out for the remediation. Also, a great number of data has been acquired, and using the data, some remediation activities have already begun, including designing for the upstream part of the Mill Tailings Pond. According to the current plan, the Mill Tailings Pond will be covered by capping following dewatering and compressing of mill tailings. The capping is composed of 'radon barrier' for lowering radon-gas dissipation and dose rate, and its protection layer. Natural materials are planned to be used for the capping to alleviate the future maintenance. After capping, data will be accumulated to verify the effectiveness of the capping, and if proved effective, it will be utilized for the capping of the downstream part. (author)

Treatment Study Plan for Nitrate Salt Waste Remediation Revision 1.0

Energy Technology Data Exchange (ETDEWEB)

Juarez, Catherine L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Vigil-Holterman, Luciana R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Felicia Danielle [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-07

The two stabilization treatment methods that are to be examined for their effectiveness in the treatment of both the unremediated and remediated nitrate salt wastes include (1) the addition of zeolite and (2) cementation. Zeolite addition is proposed based on the results of several studies and analyses that specifically examined the effectiveness of this process for deactivating nitrate salts. Cementation is also being assessed because of its prevalence as an immobilization method used for similar wastes at numerous facilities around the DOE complex, including at Los Alamos. The results of this Treatment Study Plan will be used to provide the basis for a Resource Conservation and Recovery Act (RCRA) permit modification request of the LANL Hazardous Waste Facility Permit for approval by the New Mexico Environment Department-Hazardous Waste Bureau (NMED-HWB) of the proposed treatment process and the associated facilities.

Wastes from former mining and milling activities in Tajikistan

International Nuclear Information System (INIS)

Mirsaidov, U.M.

2012-01-01

This article is devoted to wastes from former mining and milling activities in Tajikistan. Currently, the serious radiological and ecological problems in Tajikistan are uranium mining and milling activities consequences overcoming which intensively developed during the soviet period. After the collapse of USSR, the uranic ores extraction in Tajikistan stopped due to deposit's output completion on the territory of the republic. Remediation of mining and milling activities' sites became the most urgent once all mines were closed.

Determining the number of samples required for decisions concerning remedial actions at hazardous waste sites

International Nuclear Information System (INIS)

Skiles, J.L.; Redfearn, A.; White, R.K.

1991-01-01

An important consideration for every risk analyst is how many field samples should be taken so that scientifically defensible decisions concerning the need for remediation of a hazardous waste site can be made. Since any plausible remedial action alternative must, at a minimum, satisfy the condition of protectiveness of human and environmental health, we propose a risk-based approach for determining the number of samples to take during remedial investigations rather than using more traditional approaches such as considering background levels of contamination or federal or state cleanup standards

Tank waste remediation system engineering plan

International Nuclear Information System (INIS)

Rifaey, S.H.

1998-01-01

This Engineering Plan describes the engineering process and controls that will be in place to support the Technical Baseline definition and manage its evolution and implementation to the field operations. This plan provides the vision for the engineering required to support the retrieval and disposal mission through Phase 1 and 2, which includes integrated data management of the Technical Baseline. Further, this plan describes the approach for moving from the ''as is'' condition of engineering practice, systems, and facilities to the desired ''to be'' configuration. To make this transition, Tank Waste Remediation System (TWRS) Engineering will become a center of excellence for TWRS which,will perform engineering in the most effective manner to meet the mission. TWRS engineering will process deviations from sitewide systems if necessary to meet the mission most effectively

Temporary septic holding tank at the 100-D remedial action support facility -- Engineering report. Revision 2

International Nuclear Information System (INIS)

Kelty, G.G.

1996-10-01

The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for the national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemical constituents. Investigation and remediation of the wastes sites is governed by the Tri-Party Agreement. This agreement grouped the waste sites into 78 operable units, each of which was to be investigated and remediated separately. Once actual remediation activities begin at the waste sites, a central support facility will be required at each of the reactor areas (100-B/C, 100-D, and 100-H). These facilities will provide office and work space for the supervisors, engineers, and technicians engaged in the field work. The central facilities will be temporary, modular buildings sized to accommodate the anticipated staff, which in turn is determined by the scope of the planned remediation activities. The paper describes the project location, geology and flooding potential, design criteria, operation, and maintenance

Protecting Lake Ontario - Treating Wastewater from the Remediated Low-Level Radioactive Waste Management Facility - 13227

International Nuclear Information System (INIS)

Freihammer, Till; Chaput, Barb; Vandergaast, Gary; Arey, Jimi

2013-01-01

The Port Granby Project is part of the larger Port Hope Area Initiative, a community-based program for the development and implementation of a safe, local, long-term management solution for historic low level radioactive waste (LLRW) and marginally contaminated soils (MCS). The Port Granby Project involves the relocation and remediation of up to 0.45 million cubic metres of such waste from the current Port Granby Waste Management Facility located in the Municipality of Clarington, Ontario, adjacent to the shoreline of Lake Ontario. The waste material will be transferred to a new suitably engineered Long-Term Waste Management Facility (LTWMF) to be located inland approximately 700 m from the existing site. The development of the LTWMF will include construction and commissioning of a new Wastewater Treatment Plant (WWTP) designed to treat wastewater consisting of contaminated surface run off and leachate generated during the site remediation process at the Port Granby Waste Management Facility as well as long-term leachate generated at the new LTWMF. Numerous factors will influence the variable wastewater flow rates and influent loads to the new WWTP during remediation. The treatment processes will be comprised of equalization to minimize impacts from hydraulic peaks, fine screening, membrane bioreactor technology, and reverse osmosis. The residuals treatment will comprise of lime precipitation, thickening, dewatering, evaporation and drying. The distribution of the concentration of uranium and radium - 226 over the various process streams in the WWTP was estimated. This information was used to assess potential worker exposure to radioactivity in the various process areas. A mass balance approach was used to assess the distribution of uranium and radium - 226, by applying individual contaminant removal rates for each process element of the WTP, based on pilot scale results and experience-based assumptions. The mass balance calculations were repeated for various flow

Protecting Lake Ontario - Treating Wastewater from the Remediated Low-Level Radioactive Waste Management Facility - 13227

Energy Technology Data Exchange (ETDEWEB)

Freihammer, Till; Chaput, Barb [AECOM, 99 Commerce Drive, Winnipeg, Manitoba, R3P 0Y7 (Canada); Vandergaast, Gary [Atomic Energy of Canada Limited, Port Hope, Ontario (Canada); Arey, Jimi [Public Works and Government Services Canada, Ontario (Canada)

2013-07-01

The Port Granby Project is part of the larger Port Hope Area Initiative, a community-based program for the development and implementation of a safe, local, long-term management solution for historic low level radioactive waste (LLRW) and marginally contaminated soils (MCS). The Port Granby Project involves the relocation and remediation of up to 0.45 million cubic metres of such waste from the current Port Granby Waste Management Facility located in the Municipality of Clarington, Ontario, adjacent to the shoreline of Lake Ontario. The waste material will be transferred to a new suitably engineered Long-Term Waste Management Facility (LTWMF) to be located inland approximately 700 m from the existing site. The development of the LTWMF will include construction and commissioning of a new Wastewater Treatment Plant (WWTP) designed to treat wastewater consisting of contaminated surface run off and leachate generated during the site remediation process at the Port Granby Waste Management Facility as well as long-term leachate generated at the new LTWMF. Numerous factors will influence the variable wastewater flow rates and influent loads to the new WWTP during remediation. The treatment processes will be comprised of equalization to minimize impacts from hydraulic peaks, fine screening, membrane bioreactor technology, and reverse osmosis. The residuals treatment will comprise of lime precipitation, thickening, dewatering, evaporation and drying. The distribution of the concentration of uranium and radium - 226 over the various process streams in the WWTP was estimated. This information was used to assess potential worker exposure to radioactivity in the various process areas. A mass balance approach was used to assess the distribution of uranium and radium - 226, by applying individual contaminant removal rates for each process element of the WTP, based on pilot scale results and experience-based assumptions. The mass balance calculations were repeated for various flow

Long-reach manipulation for waste storage tank remediation

International Nuclear Information System (INIS)

Jansen, J.F.; Burks, B.L.; Babcock, S.M.; Kress, R.L.; Hamel, W.R.

1991-01-01

Remediation of large underground storage tanks containing hazardous waste provides an application for state-of-the-art technology in flexible link manipulator design and control and a need for additional research and development. Application requirements are described, and preliminary analyses associated with this problem are summarized. Inherent physical limitations of flexible manipulators are discussed. Potential kinematic configurations, drive-train elements, and control issues for both free-space motion and damping of forced vibration are addressed. Also included are future directions for research and development in mechanical components and control strategies. 21 refs., 4 figs., 4 tabs

Integrating radiation protection criteria for radioactive waste management into remediation procedures in existing exposure situations after a nuclear accident.

Science.gov (United States)

Sugiyama, Daisuke; Kimura, Hideo; Tachikawa, Hirokazu; Iimoto, Takeshi; Kawata, Yosuke; Ogino, Haruyuki; Okoshi, Minoru

2018-03-01

Experience after the accident at the Fukushima Daiichi nuclear power station has shown that there is a need to establish radiation protection criteria for radioactive waste management consistent with the criteria adopted for the remediation of existing exposure situations. A stepwise approach to setting such criteria is proposed. Initially, a reference level for the annual effective dose from waste management activities in the range 1-10 mSv should be set, with the reference level being less than the reference level for the ambient dose. Subsequently, the reference level for the annual effective dose from waste management activities should be reduced in one or more steps to achieve a final target value of 1 mSv. The dose criteria at each stage should be determined with relevant stakeholder involvement. Illustrative case studies show how this stepwise approach might be applied in practice.

Uranium Mill Tailings remedial action project waste minimization and pollution prevention awareness program plan

International Nuclear Information System (INIS)

1994-07-01

The purpose of this plan is to establish a waste minimization and pollution prevention awareness (WM/PPA) program for the U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The program satisfies DOE requirements mandated by DOE Order 5400.1. This plan establishes planning objectives and strategies for conserving resources and reducing the quantity and toxicity of wastes and other environmental releases

Light Duty Utility Arm System applications for tank waste remediation

International Nuclear Information System (INIS)

Carteret, B.A.

1994-10-01

The Light Duty Utility Arm (LDUA) System is being developed by the US Department of Energy's (DOE's) Office of Technology Development (OTD, EM-50) to obtain information about the conditions and contents of the DOE's underground storage tanks. Many of these tanks are deteriorating and contain hazardous, radioactive waste generated over the past 50 years as a result of defense materials production at a member of DOE sites. Stabilization and remediation of these waste tanks is a high priority for the DOE's environmental restoration program. The LDUA System will provide the capability to obtain vital data needed to develop safe and cost-effective tank remediation plans, to respond to ongoing questions about tank integrity and leakage, and to quickly investigate tank events that raise safety concerns. In-tank demonstrations of the LDUA System are planned for three DOE sites in 1996 and 1997: Hanford, Idaho National Engineering Laboratory (INEL), and Oak Ridge National Laboratory (ORNL). This paper provides a general description of the system design and discusses a number of planned applications of this technology to support the DOE's environmental restoration program, as well as potential applications in other areas. Supporting papers by other authors provide additional in-depth technical information on specific areas of the system design

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

International Nuclear Information System (INIS)

Pickett, W.W.

1997-01-01

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

Energy Technology Data Exchange (ETDEWEB)

Pickett, W.W.

1997-12-30

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

Remedial investigation report on Waste Area Group 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Technical summary

International Nuclear Information System (INIS)

1995-03-01

A remedial investigation (RI) was performed to support environmental restoration activities for Waste Area Grouping (WAG) 5 at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The WAG 5 RI made use of the observational approach, which concentrates on collecting only information needed to assess site risks and support future cleanup work. This information was interpreted and is presented using the framework of the site conceptual model, which relates contaminant sources and release mechanisms to migration pathways and exposure points that are keyed to current and future environmental risks for both human and ecological receptors. The site conceptual model forms the basis of the WAG 5 remedial action strategy and remedial action objectives. The RI provided the data necessary to verify this model and allows recommendations to be made to accomplish those objectives

Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Technical summary

International Nuclear Information System (INIS)

1995-09-01

A remedial investigation (RI) was performed to support environmental restoration activities for Waste Area Grouping (WAG) 5 at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The WAG 5 RI made use of the observational approach, which concentrates on collecting only information needed to assess site risks and support future cleanup work. This information was interpreted and is presented using the framework of the site conceptual model, which relates contaminant sources and release mechanisms to migration pathways and exposure points that are keyed to current and future environmental risks for both human and ecological receptors. The site conceptual model forms the basis of the WAG 5 remedial action strategy and remedial action objectives. The RI provided the data necessary to verify this model and allows recommendations to be made to accomplish those objectives.

Remediation of the low-level radioactive waste tailing pond at Kowary, Poland

International Nuclear Information System (INIS)

Goerner, R.; Hartsch, J.; Koszela, J.; Krzyskow, A.; Machniewicz, B.; Sennewald, R.; Sowa, J.

2002-03-01

The last remaining uranium mining tailing pond in Poland, situated at Kowary, was the subject of the Kowary Tailing Pond Remediation Programme financed by Polish public bodies (70%) and by the European Commission (30%) within the framework of its programme of co-operation on radioactive waste issues with candidate countries. The EC-part of the project comprised investigations of the site, project management duties and large-scale civil works following the initial remediation planning performed by the Wroclaw University of Technology (WUT) in 1998-2000. The EC-part was contracted to G.E.O.S. Freiberg Ingenieurgesellschaft mbH following an Open Call for Tender launched by the European Commission in 1999. The following general tasks were performed in close co-operation with WUT, with the construction works subcontracted to local companies, as proposed in the Terms of Reference (TOR) of the EC-part: review of General Remediation Plan (GRP), technical design of the pond cover, construction work: internal drainage system, pond cover and site reclamation. From the information in the TOR, the following aims of remediation were defined: minimise the detrimental impact of the tailing pond on the environment, provide long-term stability of the slopes surrounding the pond, ensure the remediated site is in harmony with the surrounding natural scenery. Based on the experience gathered in similar projects, which had been running under PHARE-MCE or which belonged to the WISMUT-remediation programme in Germany, cost efficient remediation solutions were designed in close co-operation with all involved parties. They were delineated in the detailed planning documents approved in the overall remediation programme managed by WUT. The planned remediation works were prepared and performed successfully according to Polish law and in agreement with the competent local authorities. The aims of remediation were met. However, some additional tasks have been recommended in zones adjacent to the

Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

Energy Technology Data Exchange (ETDEWEB)

Esch, R.A.

1997-04-14

This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

Oak Ridge National Laboratory remedial investigation/feasibility study

International Nuclear Information System (INIS)

Glenn, R.D.; Hoffman, J.M.; Hyde, L.D.

1988-01-01

The Oak Ridge National Laboratory (ORNL) Remedial Investigation/ Feasibility Study (RI/FS) began in June 1987 to evaluate 13 contaminated waste area groupings (WAGs) to determine the feasibility and benefits of potential remedial action. The RI/FS and any future remedial action at ORNL will be of national significance and will likely lead to developments that will become models for environmental investigations and cleanups. Bechtel National, Inc. and a team of subcontractors will be working with Martin Marietta Energy systems to conduct intensive field investigations to obtain data required to evaluate the WAGs. The RI/F project continued in FY 1988 with project planning and preparation for field activities. Remedial Investigation (RI) Plans were prepared for 10 of the 13 WAGs. These plans were developed with sufficient information to ensure compliance with regulatory requirements, with intensive attention given to environmental, safety, and health protection; waste management; data management; and quality assurance. This paper reports on the progress made during FY 1988 and discusses activities planned for FY 1989

Permitting plan for the immobilized low-activity waste project

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of the Immobilized Low-Activity Waste (ILAW) produced during Phase 1 of the Hanford Site privatization effort. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage and disposal of Tank Waste Remediation Systems (TWRS) immobilized low-activity tank waste (ILAW) and (2) interim storage of TWRS immobilized HLW (IHLW) and other canistered high-level waste forms. Low-activity waste (LAW), low-level waste (LLW), and high-level waste (HLW) are defined by the TWRS, Hanford Site, Richland, Washington, Final Environmental Impact Statement (EIS) DOE/EIS-0189, August 1996 (TWRS, Final EIS). By definition, HLW requires permanent isolation in a deep geologic repository. Also by definition, LAW is ''the waste that remains after separating from high-level waste as much of the radioactivity as is practicable that when solidified may be disposed of as LLW in a near-surface facility according to the NRC regulations.'' It is planned to store/dispose of (ILAW) inside four empty vaults of the five that were originally constructed for the Group Program. Additional disposal facilities will be constructed to accommodate immobilized LLW packages produced after the Grout Vaults are filled. The specifications for performance of the low-activity vitrified waste form have been established with strong consideration of risk to the public. The specifications for glass waste form performance are being closely coordinated with analysis of risk. RL has pursued discussions with the NRC for a determination of the classification of the Hanford Site's low-activity tank waste fraction. There is no known RL action to change law with respect to onsite disposal of waste

Tank waste treatment science

International Nuclear Information System (INIS)

LaFemina, J.P.; Blanchard, D.L.; Bunker, B.C.; Colton, N.G.; Felmy, A.R.; Franz, J.A.; Liu, J.; Virden, J.W.

1994-01-01

Remediation efforts at the U.S. Department of Energy's Hanford Site require that many technical and scientific principles be combined for effectively managing and disposing the variety of wastes currently stored in underground tanks. Based on these principles, pretreatment technologies are being studied and developed to separate waste components and enable the most suitable treatment methods to be selected for final disposal of these wastes. The Tank Waste Treatment Science Task at Pacific Northwest Laboratory is addressing pretreatment technology development by investigating several aspects related to understanding and processing the tank contents. The experimental work includes evaluating the chemical and physical properties of the alkaline wastes, modeling sludge dissolution, and evaluating and designing ion exchange materials. This paper gives some examples of results of this work and shows how these results fit into the overall Hanford waste remediation activities. This work is part of series of projects being conducted for the Tank Waste Remediation System

Oak Ridge National Laboratory Old Hydrofracture Facility Waste Remediation Using the Borehole-Miner Extendible-Nozzle Sluicer

Energy Technology Data Exchange (ETDEWEB)

Bamberger, J.A.; Boris, G.F.

1999-10-07

A borehole-miner extendible-nozzle sluicing system was designed, constructed, and deployed at Oak Ridge National Laboratory to remediate five horizontal underground storage tanks containing sludge and supernate at the ORNL Old Hydrofracture Facility site. The tanks were remediated in fiscal year 1998 to remove {approx}98% of the waste, {approx}3% greater than the target removal of >95% of the waste. The tanks contained up to 18 in. of sludge covered by supernate. The 42,000 gal of low level liquid waste were estimated to contain 30,000 Ci, with 97% of this total located in the sludge. The retrieval was successful. At the completion of the remediation, the State of Tennessee Department of Environment and Conservation agreed that the tanks were cleaned to the maximum extent practicable using pumping technology. This deployment was the first radioactive demonstration of the borehole-miner extendible-nozzle water-jetting system. The extendible nozzle is based on existing bore hole-miner technology used to fracture and dislodge ore deposits in mines. Typically borehole-miner technology includes both dislodging and retrieval capabilities. Both dislodging, using the extendible-nozzle water-jetting system, and retrieval, using a jet pump located at the base of the mast, are deployed as an integrated system through one borehole or riser. Note that the extendible-nozzle system for Oak Ridge remediation only incorporated the dislodging capability; the retrieval pump was deployed through a separate riser. The borehole-miner development and deployment is part of the Retrieval Process Development and Enhancements project under the direction of the US Department of Energy's EM-50 Tanks Focus Area. This development and deployment was conducted as a partnership between RPD and E and the Oak Ridge National Laboratory's US DOE EM040 Old Hydrofracture Facility remediation project team.

Oak Ridge National Laboratory Old Hydrofracture Facility Waste Remediation Using the Borehole-Miner Extendible-Nozzle Sluicer

International Nuclear Information System (INIS)

Boris, G.F.; Bamberger, J.A.

1999-01-01

A borehole-miner extendible-nozzle sluicing system was designed, constructed, and deployed at Oak Ridge National Laboratory to remediate five horizontal underground storage tanks containing sludge and supernate at the ORNL Old Hydrofracture Facility site. The tanks were remediated in fiscal year 1998 to remove approximately98% of the waste, approximately3% greater than the target removal of >95% of the waste. The tanks contained up to 18 in. of sludge covered by supernate. The 42,000 gal of low level liquid waste were estimated to contain 30,000 Ci, with 97% of this total located in the sludge. The retrieval was successful. At the completion of the remediation, the State of Tennessee Department of Environment and Conservation agreed that the tanks were cleaned to the maximum extent practicable using pumping technology. This deployment was the first radioactive demonstration of the borehole-miner extendible-nozzle water-jetting system. The extendible nozzle is based on existing borehole-miner technology used to fracture and dislodge ore deposits in mines. Typically borehole-miner technology includes both dislodging and retrieval capabilities. Both dislodging, using the extendible-nozzle water-jetting system, and retrieval, using a jet pump located at the base of the mast, are deployed as an integrated system through one borehole or riser. Note that the extendible-nozzle system for Oak Ridge remediation only incorporated the dislodging capability; the retrieval pump was deployed through a separate riser. The borehole-miner development and deployment is part of the Retrieval Process Development and Enhancements project under the direction of the US Department of Energy's EM-50 Tanks Focus Area. This development and deployment was conducted as a partnership between RPD and E and the Oak Ridge National Laboratory's US DOE EM040 Old Hydrofracture Facility remediation project team

2016 Los Alamos National Laboratory Hazardous Waste Minimization Report

Energy Technology Data Exchange (ETDEWEB)

Salzman, Sonja L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); English, Charles Joe [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-12-02

Waste minimization and pollution prevention are goals within the operating procedures of Los Alamos National Security, LLC (LANS). The US Department of Energy (DOE), inclusive of the National Nuclear Security Administration (NNSA) and the Office of Environmental Management, and LANS are required to submit an annual hazardous waste minimization report to the New Mexico Environment Department (NMED) in accordance with the Los Alamos National Laboratory (LANL or the Laboratory) Hazardous Waste Facility Permit. The report was prepared pursuant to the requirements of Section 2.9 of the LANL Hazardous Waste Facility Permit. This report describes the hazardous waste minimization program, which is a component of the overall Pollution Prevention (P2) Program, administered by the Environmental Stewardship Group (EPC-ES). This report also supports the waste minimization and P2 goals of the Associate Directorate of Environmental Management (ADEM) organizations that are responsible for implementing remediation activities and describes its programs to incorporate waste reduction practices into remediation activities and procedures. This report includes data for all waste shipped offsite from LANL during fiscal year (FY) 2016 (October 1, 2015 – September 30, 2016). LANS was active during FY2016 in waste minimization and P2 efforts. Multiple projects were funded that specifically related to reduction of hazardous waste. In FY2016, there was no hazardous, mixed-transuranic (MTRU), or mixed low-level (MLLW) remediation waste shipped offsite from the Laboratory. More non-remediation hazardous waste and MLLW was shipped offsite from the Laboratory in FY2016 compared to FY2015. Non-remediation MTRU waste was not shipped offsite during FY2016. These accomplishments and analysis of the waste streams are discussed in much more detail within this report.

Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Appendix A

International Nuclear Information System (INIS)

1995-09-01

This document is a compilation of data relating to the Tank Waste Remediation System Multi-Year Program. Topics discussed include: management systems; waste volume, transfer and evaporation management; transition of 200 East and West areas; ferricyanide, volatile organic vapor, and flammable gas management; waste characterization; retrieval from SSTs and DSTs; heat management; interim storage; low-level and high-level radioactive waste management; and tank farm closure

Developing a disposal and remediation plan

International Nuclear Information System (INIS)

Messier, T.S.

1999-01-01

The environmental release of wastes generated by the upstream oil and gas industry in Alberta can result in polluted soil and groundwater at several facilities across the province. Responsibility for decommissioning upstream oil and gas facilities falls under the jurisdiction of the Alberta Energy and Utilities Board (EUB) and Alberta Environmental Protection (AEP). This paper outlines a protocol that can serve as a framework for the development of a plan to dispose of oilfield waste and to remediate related contaminated soils. The components involved in developing a disposal and remediation plan for oilfield wastes are: (1) identifying the potential source of pollution and oilfield waste generation, (2) characterizing oilfield wastes, (3) determining the nature and extent of soil and groundwater pollution, (4) preparing a remedial action plan, (5) assessing the viability of various remediation options, and (6) preparing health and safety plan. 12 refs., 2 tabs., 2 figs

Interim remedial action work plan for the cesium plots at Waste Area Grouping 13 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-07-01

This remedial action work plan (RAWP) is issued under the Federal Facility Agreement to provide a basic approach for implementing the interim remedial action (IRA) described in Interim Record of Decision for the Oak Ridge National Laboratory Waste Area Grouping 13 Cesium Plots, Oak Ridge, Tennessee. This RAWP summarizes the interim record of decision (IROD) requirements and establishes the strategy for the implementation of the field activities. As documented in the IROD document, the primary goal of this action is to reduce the risk to human health and the environment resulting from current elevated levels of gamma radiation on the site and at areas accessible to the public adjacent to the site. The major steps of this IRA are to: Excavate cesium-contaminated soil; place the excavated soils in containers and transport to Waste Area Grouping (WAG) 6; and backfill excavated plots with clean fill materials. The actual remedial action will be performed by Department of Energy prime contractor, MK-Ferguson of Oak Ridge Company. Remediation of the cesium plots will require approximately 60 days to complete. During this time, all activities will be performed according to this RAWP and the applicable specifications, plans, and procedures referred to in this document. The IRA on WAG 13 will prevent a known source of cesium-contaminated soil from producing elevated levels of gamma radiation in areas accessible to the public, eliminate sources of contamination to the environment, and reduce the risks associated with surveillance and maintenance of the WAG 13 site

Low-Activity Waste Feed Data Quality Objectives

Energy Technology Data Exchange (ETDEWEB)

MJ Truex; KD Wiemers

1998-12-11

This document describes characterization requirements for the Tank Waste Remediation System (TWRS) Waste Disposal Program's privatization efforts in support of low-activity waste (LAW) treatment and immobilization, This revised Data Quality Objective (DQO) replaces earlier documents (PNNL 1997; DOE-W 1998zq Wiemers 1996). Revision O of this DQO was completed to meet Tri-Party Agreement (TPA) target milestone M-60-14-TO1. Revision 1 updates the data requirements based on the contract issued `August 1998 (DOE-RL 1998b). In addition, sections of Revision O pertaining to "environmental planning" were not acceptable to the Washington State Department of Ecology (Ecology) and have been removed. Regulatory compliance for TWRS Privatization is being addressed in a separate DQO (Wiemers et al. 1998). The Project Hanford Management Contract (PHMC) Contractors and the private contractor may elect to complete issue-specific DQOS to accommodate their individual work scope.

REMEDIATION TECHNOLOGY EVALUATION AT THE GILT EDGE MINE, SOUTH DAKOTA

Science.gov (United States)

This document reports the findings of the Mine Waste Technology Program's Activity III, Project 29,The Remediation Technology Evaluation Project at the Gilt Edge Mine, S.D. This project consisted of evaluating three emerging acidic waste rock stabilization technologies and compar...

The buried waste integrated demonstration

International Nuclear Information System (INIS)

Kostelnik, K.M.

1991-01-01

There are numerous locations throughout the Department of Energy (DOE) Complex where wastes have been buried in the ground or stored for future disposal. Much of this buried waste is contaminated with hazardous and radioactive materials. An extensive research program has been initiated at the Idaho National Engineering Laboratory (INEL) to develop and demonstrate advanced remediation techniques for DOE Complex buried waste. The purpose of the Buried Waste Integrated Demonstration (BWID), is to develop a scientifically sound and deployable remediation system consisting of advanced technologies which address the buried waste characteristics of the DOE Complex. This comprehensive remediation system win include technologies for the entire remediation cycle (cradle-to-grave). Technologies developed and demonstrated within the BWID will be transferred to the DOE Complex sites with buried waste, to private industry, and to universities. Multidirectional technology transfer is encouraged by the BWID. Identification and evaluation of plausible technological solutions are an ongoing activity of the BWID. A number of technologies are currently under development throughout the DOE Complex, private industry, and universities. Technology integration mechanisms have been established by BWID to facilitate collaborative research and demonstration of applicable remedial technologies for buried waste. Successful completion of the BWID will result in the development of a proven and deployable system at the INEL and other DOE Complex buried waste sites, thereby supporting the DOE Complex's environmental restoration objectives

Safety analysis and hazard classification for the 100-B/C Site Remediation Project, Phase 1. Revision 1

International Nuclear Information System (INIS)

Adam, W.J.; Lehrschall, R.R.; Oestreich, D.K.

1996-07-01

The purpose of this report is to document the preliminary hazard classification (PHC) for the initial group of sites to be remediated by the 100-B/C Site Remediation Project. The project is targeted at excavation of contaminated solid from seven waste sites, and the transportation and disposal of these wastes at the Environmental Restoration Disposal Facility. The PHC for these remediation activities is rated as radiological

An innovative in-situ mixing technology and its applications in the waste remediation industry

International Nuclear Information System (INIS)

Toor, I.A.; Lanter, R.

1994-01-01

An innovative in-situ remediation technology has been developed for solidification and stabilization of hazardous wastes. The system incorporates a specially designed rotary mixing head attached to the boom of a long-reach backhoe or other dirt-moving equipment. A variety of mixing-head configurations are available to treat various types of wastes, ranging from oil sludge to very dry contaminated soils containing significant amounts of large aggregates and gravel. The system has been successfully applied in the field to remediate hazardous petroleum sludge, mine tailings, and steel mill process sediments containing heavy metals (e.g., chromium, arsenic, cadmium, and lead). A very elaborate quality assurance/quality control program was implemented to ensure minimum variation in additive concentration and thorough mixing. The mixing effectiveness and reagent injection capabilities of this unit have resulted in the in-situ treatment of listed hazardous wastes to below delisting thresholds at depths in excess of 15 ft. Applications of this unit are currently being reviewed for incorporating and mixing nutrients in a bioremediation process. The new technology provides a very economical means for treatment, with excellent product quality

Development of inorganic ion exchangers for nuclear waste remediation. 1997 annual progress report

International Nuclear Information System (INIS)

Clearfield, A.; Collins, J.L.; Egan, B.Z.

1997-01-01

'In this research program, Oak Ridge National Laboratory (ORNL) is collaborating with Texas A and M University in the development of highly selective inorganic ion exchangers for the removal of cesium and strontium from nuclear tank-waste and from groundwater. Inorganic ion exchangers are developed and characterized at Texas A and M University; ORNL is involved in preparing the powders in engineered forms and testing the performance of the sorbents in actual nuclear waste solutions. The Texas A and M studies are divided into two main categories: (1) exchangers for tank wastes and (2) exchangers for groundwater remediation. These are subdivided into exchangers for use in acid and alkaline solutions for tank wastes and those that can be recycled for use in groundwater remediation. The exchangers will also be considered for in situ immobilization of radionuclides. The approach will involve a combination of exchanger synthesis, structural characterization, and ion exchange behavior. ORNL has developed a technique for preparing inorganic ion exchangers in the form of spherules by a gel-sphere internal gelation process. This technology, which was developed and used for making nuclear fuels, has the potential of greatly enhancing the usability of many other special inorganic materials because of the improved flow dynamics of the spherules. Also, pure inorganic spherules can be made without the use of binders. ORNL also has access to actual nuclear waste in the form of waste tank supernatant solutions for testing the capabilities of the sorbents for removing the cesium and strontium radionuclides from actual waste solutions. The ORNL collaboration will involve the preparation of the powdered ion exchangers, developed and synthesized at Texas A and M, in the form of spherules, and evaluating the performance of the exchangers in real nuclear waste solutions. Selected sorbents will be provided by Texas A and M for potential incorporation into microspheres, and the performance

Remediation and upgrading of old, inadequate waste management facilities. Integrated waste management system for rare earth and rare metal industry at Sillamaee, Estonia, former uranium facility

International Nuclear Information System (INIS)

Kaasik, Tonis; Siinmaa, Anti

2001-01-01

Full text: The Sillamaee Metallurgical Plant was built in 1946-1948 at Sillamaee, in North-East Estonia, ca 190 km from Tallinn. Target product was uranium, mostly in form of yellow cake (U 3 O 8 ) for Soviet nuclear program. Uranium ore processing continued from 1948 to 1977, totally 4,013,000 tons of uranium ore were processed at Sillamaee plant. In early 1970s the plant introduced a new production line - rare earth elements. Rare earths were until 1991 produced from loparite (later from semi-processed loparite) - rare earths, niobium, tantalum and NORM-containing ore for Kola peninsula, Russia; later. All wastes were, as typical to hydrometallurgical processing all over the world, discharged to a large, 40 ha liquid waste depository - tailings pond, what in Sillamaee case was designed to discharge all liquid constituents slowly to the Baltic Sea. All uranium related activities were stopped in 1990, when only rare earth and rare metal production lines remained operational. The plant was 100 % privatized in 1997 and is today operated by Silmet Ltd., processing annually up to 8 000 tons of rare earth and 2000 tons of niobium and tantalum ores. Like all industries, inherited from Soviet times, Silmet plant is today facing a serious challenge to upgrading technologies towards waste minimizations process efficiency. The historical tailings pond, containing ca 1800 tons of natural uranium and ca 800 tons of thorium, was found geotechnically unstable and leaking to the Baltic Sea, in mid 90s. Being a problem of common Baltic concern, an international remediation project was initiated by Estonian Government and plant operator in 1998. In cooperation with Estonian, Finnish, Swedish, Danish and Norwegian Governments and with assistance by the European Union, the tailings pond will be environmentally remediated - dams stabilized and surface covered, by end of 2006. Close-down and environmental remediation of the tailings pond provides plant an ultimate challenge of

In Situ Remediation Integrated Program: Technology summary

International Nuclear Information System (INIS)

1994-02-01

The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed

In Situ Remediation Integrated Program: Technology summary

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed.

Phase I remedial investigation report of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Miller, D.E.

1995-07-01

This report presents the activities and findings of the first phase of a three-phase remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, and updates the scope and strategy for WAG-2-related efforts. WAG 2 contains White Oak Creek (WOC) and its tributaries downstream of the ORNL main plant area, White Oak Lake, White Oak Creek Embayment on the Clinch River, and the associated floodplain and subsurface environment. Water, sediment, soil, and biota in WAG 2 are contaminated and continue to receive contaminants from upgradient WAGs. This report includes field activities completed through October 1992. The remediation of WAG 2 is scheduled to follow the cessation of contaminant input from hydrologically upgradient WAGs. While upgradient areas are being remediated, the strategy for WAG 2 is to conduct a long-term monitoring and investigation program that takes full advantage of WAG 2's role as an integrator of contaminant fluxes from other ORNL WAGs and focuses on four key goals: (1) Implement, in concert with other programs, long-term, multimedia environmental monitoring and tracking of contaminants leaving other WAGs, entering WAG 2, and being transported off-site. (2) Provide a conceptual framework to integrate and develop information at the watershed-level for pathways and processes that are key to contaminant movement, and so support remedial efforts at ORNL. (3) Provide periodic updates of estimates of potential risk (both human health and ecological) associated with contaminants accumulating in and moving through WAG 2 to off-site areas. (4) Support the ORNL Environmental Restoration Program efforts to prioritize, remediate, and verify remedial effectiveness for contaminated sites at ORNL, through long-term monitoring and continually updated risk assessments

Remediation of uranium mill tailings wastes in Australia: a critical review

International Nuclear Information System (INIS)

Mudd, G.M.

2000-01-01

Australia has been an active participant in the global uranium mining industry since its inception in the 1940s. By the late 1950s five major mining and milling projects were operating, several small mines supplied custom ores. All of these projects were closed by the early 1960s, except for Rum Jungle which continued under government subsidy. Most sites have had lasting Environmental impacts. The advances in nuclear power in the 1960s saw increasing demand for uranium and Australia again explored with remarkable success in the Northern Territory, South Australia and Western Australia. After several government inquiries in the 1970s, Ranger, Nabarlek and Olympic Dam were operating by the mid 1980s. The principal risks from uranium mill tailings wastes arise from their radioactive nature and often their chemical toxicities. A critical review of the rehabilitation of abandoned uranium mines and mill tailings as a comparison for current projects is presented. It is concluded that the management of uranium mill tailings wastes is a complex task, requiring a sound multi-disciplinary approach. The problems include groundwater contamination, erosion, radon emanation and gamma radiation. evidence to data from the remediation of old and modern sites does not demonstrate effective long-term closure and safety

Remediation of the low-level radioactive waste tailing pond in Kowary

International Nuclear Information System (INIS)

Waclawek, Z.

1999-01-01

The town of Kowary was the centre of uranium mining activities in Poland. The headquarters of the uranium mining company ZPR-1 (Zaklady Przemyslowe R-1) were located there, as it was the only uranium processing plant in Poland. Mining in Uranium in Poland ceased in 1963, but processing of low-grade dumps was continued in Kowary until 1972. As a result of these processing activities, a significant volume of wastes was produced and the tailings pond in Kowary was constructed to accommodate these wastes. The tailings pond covers an area of 1,3 ha. It is a hydrotechnical construction closed on three sides by a dam, which has been modified a number of times over the years. It is now 300 m long (the sum of the three sides)m with a maximum height of 12 m, and is at the limits of the geotechnical stability. As a result of the uranium processing activities, the tailings pond was filled with about 2,5 x 10 5 t of disposed fine-grained gneisses and schists containing about 4,5 t of uranium and about 440 GBq of radium (from processing of uranium ores). A prompt remedial action in this case is particularly necessary because the tailings pond is located in a steep mountainous valley where the local climate involves rapid summer rains with heavy erosion. The nearest buildings in the town of Kowary are located literally at the foot of the 12 m high dam and private gardens extend onto the dam slope. The urgency has recently been demonstrated during the flood of summer 1997 when the base of the dam eroded. In the early seventies, Wroclaw University of Technology (WUT) received, by a governmental decision, ownership of both the area and the facilities of the former uranium mining company ZPR-1. Subsequently, the company Hydromet, Ltd., owned by WUT, has continued to use the existing chemical plant for the various experimental processes of rare (radioactive) metals, chemical production and galvanic processes. As a result, 30 t of mixed heavy metals and 300 t of the remnants from the

Field Sampling and Analysis Plan for the Remedial Investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1992-10-01

This report provides responses to US Environmental Protection Agency Region IV EPA-M and Tennessee Department of Environment and Conservation Oversite Division (TDEC-O) comments on report ORNL/ER-58, Field Sampling and Analysis Plan for the Remedial Investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Waste Area Grouping (WAG) 2 consists of the White Oak Creek (WOC) drainage system downgradient of the major ORNL WAGs in the WOC watershed. A strategy for the remedial investigation (RI) of WAG2 was developed in report ES/ER-14 ampersand Dl, Remedial Investigation Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This strategy takes full advantage of WAG2's role as an integrator of contaminant releases from the ORNL WAGs in the WOC watershed, and takes full advantage of WAG2's role as a conduit for contaminants from the ORNL site to the Clinch River. The strategy calls for a multimedia environmental monitoring and characterization program to be conducted in WAG2 while upgradient contaminant sources are being remediated. This monitoring and characterization program will (1) identify and quantify contaminant fluxes, (2) identify pathways of greatest concern for human health and environmental risk, (3) improve conceptual models of contaminant movement, (4) support the evaluation of remedial alternatives, (5) support efforts to prioritize sites for remediation, (6) document the reduction in contaminant fluxes following remediation, and (7) support the eventual remediation of WAG2. Following this strategy, WAG2 has been termed an ''integrator WAG,'' and efforts in WAG2 over the short term are directed toward supporting efforts to remediate the contaminant ''source WAGS'' at ORNL

The Remediation of Hanford's Last Low-Level Waste Burial Grounds in the 300 Area: 618-7 and 618-1

International Nuclear Information System (INIS)

Haass, M.J.

2009-01-01

Under the U.S. Department of Energy's (DOE) River Corridor Closure Project, Washington Closure Hanford (WCH) has completed remediation of more than seven low-level waste (LLW) burial grounds in the 300 Area of the Hanford Site. The records of decision for the burial grounds required excavation, characterization, and transport of contaminated material to a Resource Conservation and Recovery Act of 1976-compliant hazardous waste landfill. This paper discusses the challenges and lessons learned from remediating the last two major burial grounds in the 300 Area: 618-7 and 618-1. The 618-7 Burial Ground was in operation from 1960 through 1973, during which it received waste from the production of Zircaloy (zirconium alloy) jacketed metallic uranium fuel rods and thoria targets for the production of uranium-233. Its major remediation challenges included the recovery, characterization, and disposal of 550 drums and disposal of two compressed gas cylinders that were suspected to contain highly toxic chemicals. Approximately 100 of the drums contained Zircaloy metal turnings that could be pyrophoric under certain conditions. Remediation activities were completed in December 2008. The 618-1 Burial Ground was in operation from 1945 (i.e., the beginning of Hanford operations) through 1951. It received waste from 300 Area laboratories that conducted experimental work associated with World War II and Cold War era processes for fuel fabrication and the production of plutonium. Some of the wastes were associated with highly radioactive irradiated material. Remediation of this burial ground is still in progress and is expected to be completed by June 2009. Information presented in this paper will be an aid to those involved in the planning, design, and remediation of burial grounds located on the DOE complex. (authors) Remediation of the 618-7 Burial Ground was completed in December 2008; the 618-1 Burial Ground is proceeding without incident and is expected to be completed in June

Alternatives for management of wastes generated by the formerly utilized sites remedial action program and supplement

International Nuclear Information System (INIS)

Gilbert, T.L.; Peterson, J.M.; Vocke, R.W.; Alexander, J.K.

1983-03-01

Alternatives for disposal or stabilization of the wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP) are identified and compared, with emphasis on the long-term aspects. These wastes consist of soil material and rubble containing trace amounts of radionuclides. A detailed pathway analysis for the dose to the maximally exposed individual is carried out using an adaptation of the natural analogue method. Comparisons of the different alternatives, based on the results of the pathway analysis and qualitative cost considerations, indicate that, if the hazard is such that the wastes must be removed and disposed of rather than stabilized in place, disposal by immediate dispersal is preferable to containment, and containment followed by slow planned dispersal is preferable to containment without dispersal. The Supplement presents refinements of work that was reported at the 1982 International Decommissioning Symposium. The new material consists of revisions of the estimates of the predicted potential dose to the maximally exposed individual and a more detailed comparative assessment of the radiological impacts of alternatives for management of wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP)

Fluidized bed steam reformed mineral waste form performance testing to support Hanford Supplemental Low Activity Waste Immobilization Technology Selection

Energy Technology Data Exchange (ETDEWEB)

Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pierce, E. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Burket, P. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, C. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Daniel, W. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fox, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Herman, C. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Miller, D. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Missimer, D. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Williams, M. F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Brown, C. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, N. P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neeway, J. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Valenta, M. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gill, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Swanberg, D. J. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Robbins, R. A. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Thompson, L. E. [Washington River Protection Solutions (WRPS), Richland, WA (United States)

2015-10-01

This report describes the benchscale testing with simulant and radioactive Hanford Tank Blends, mineral product characterization and testing, and monolith testing and characterization. These projects were funded by DOE EM-31 Technology Development & Deployment (TDD) Program Technical Task Plan WP-5.2.1-2010-001 and are entitled “Fluidized Bed Steam Reformer Low-Level Waste Form Qualification”, Inter-Entity Work Order (IEWO) M0SRV00054 with Washington River Protection Solutions (WRPS) entitled “Fluidized Bed Steam Reforming Treatability Studies Using Savannah River Site (SRS) Low Activity Waste and Hanford Low Activity Waste Tank Samples”, and IEWO M0SRV00080, “Fluidized Bed Steam Reforming Waste Form Qualification Testing Using SRS Low Activity Waste and Hanford Low Activity Waste Tank Samples”. This was a multi-organizational program that included Savannah River National Laboratory (SRNL), THOR® Treatment Technologies (TTT), Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), Office of River Protection (ORP), and Washington River Protection Solutions (WRPS). The SRNL testing of the non-radioactive pilot-scale Fluidized Bed Steam Reformer (FBSR) products made by TTT, subsequent SRNL monolith formulation and testing and studies of these products, and SRNL Waste Treatment Plant Secondary Waste (WTP-SW) radioactive campaign were funded by DOE Advanced Remediation Technologies (ART) Phase 2 Project in connection with a Work-For-Others (WFO) between SRNL and TTT.

Remediation and production of low-sludge high-level waste glasses

International Nuclear Information System (INIS)

Ramsey, W.G.; Brown, K.G.; Beam, D.C.

1994-01-01

High-level radioactive sludge will constitute 24-28 oxide weight percent of the high-level waste glass produced at the Savannah River Site. A recent melter campaign using non-radioactive, simulated feed was performed with a sludge content considerably lower than 24 percent. The resulting glass was processed and shown to have acceptable durability. However, the durability was lower than predicted by the durability algorithm. Additional melter runs were performed to demonstrate that low sludge feed could be remediated by simply adding sludge oxides. The Product Composition Control System, a computer code developed to predict the proper feed composition for production of high-level waste glass, was utilized to determine the necessary chemical additions. The methodology used to calculate the needed feed additives, the effects of sludge oxides on glass production, and the resulting glass durability are discussed

Comparative life-cycle cost analysis for low-level mixed waste remediation alternatives

International Nuclear Information System (INIS)

Jackson, J.A.; White, T.P.; Kloeber, J.M.; Toland, R.J.; Cain, J.P.; Buitrago, D.Y.

1995-03-01

The purpose of this study is two-fold: (1) to develop a generic, life-cycle cost model for evaluating low-level, mixed waste remediation alternatives, and (2) to apply the model specifically, to estimate remediation costs for a site similar to the Fernald Environmental Management Project near Cincinnati, OH. Life-cycle costs for vitrification, cementation, and dry removal process technologies are estimated. Since vitrification is in a conceptual phase, computer simulation is used to help characterize the support infrastructure of a large scale vitrification plant. Cost estimating relationships obtained from the simulation data, previous cost estimates, available process data, engineering judgment, and expert opinion all provide input to an Excel based spreadsheet for generating cash flow streams. Crystal Ball, an Excel add-on, was used for discounting cash flows for net present value analysis. The resulting LCC data was then analyzed using multi-attribute decision analysis techniques with cost and remediation time as criteria. The analytical framework presented allows alternatives to be evaluated in the context of budgetary, social, and political considerations. In general, the longer the remediation takes, the lower the net present value of the process. This is true because of the time value of money and large percentage of the costs attributed to storage or disposal

Radiological criteria for the remediation of sites for spent fuel and radioactive waste storage in the Russian Northwest.

Science.gov (United States)

Shandala, N K; Sneve, M K; Titov, A V; Smith, G M; Novikova, N Ya; Romanov, V V; Seregin, V A

2008-12-01

In the 1960s, two technical bases of the Northern Fleet were created in Northwest Russia, at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel, and are now designated sites of temporary storage (STSs). An analysis of the radiation situation at these sites demonstrates that substantial long-term remediation work will be required after the removal of the waste and spent nuclear fuel. Regulatory guidance is under development to support this work. Having in mind modern approaches to guaranteeing radiation safety, the primary regulatory focus is on a justification of dose constraints for determining acceptable residual contamination which might lead to exposure to workers and the public. For these sites, four principal options for remediation have been considered-renovation, conversion, conservation and liquidation. This paper describes a system of recommended dose constraints and derived control levels formulated for each option. The unconditional guarantee of long-term radioecological protection provides the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimisation principle. The developed criteria relate to the condition of the facilities and the STS areas after the termination of remediation activities. The proposed criteria for renovation, conversion, conservation and liquidation are entirely within the dose limits adopted in Russia for the management of man-made radiation sources, and are consistent with ICRP recommendations and national practice in other countries. The proposed criteria for STS remediation and new industrial (non-radiation-hazardous) facilities and buildings on

Review of selected 100-N waste sites related to N-Springs remediation projects

International Nuclear Information System (INIS)

DeFord, D.H.; Carpenter, R.W.

1996-01-01

This document has been prepared in support of the environmental restoration program at the US Department of Energy's Hanford Site near Richland, Washington, by the Bechtel Hanford, Inc. Facility and Waste Site Research Office. It provides historical information that documents and characterizes selected waste sites that are related to the N-Springs remediation projects. The N-Springs are a series of small, inconspicuous groundwater seepage springs located along the Columbia River shoreline near the 100-N Reactor. The spring site is hydrologically down-gradient from several 100-N Area liquid waste sites that are believed to have been the source(s) of the effluents being discharged by the springs. This report documents and characterizes these waste sites, including the 116-N-1 Crib and Trench, 116-N-3 Crib and Trench, unplanned releases, septic tariks, and a backwash pond

Remediation of Soil at Nuclear Sites

International Nuclear Information System (INIS)

Holmes, R.; Boardman, C.; Robbins, R; Fox, Robert Vincent; Mincher, Bruce Jay

2000-01-01

As the major nuclear waste and decontamination and decommissioning projects progress, one of the remaining problems that faces the nuclear industry is that of site remediation. The range of contamination levels and contaminants is wide and varied and there is likely to be a significant volume of soil contaminated with transuranics and hazardous organic materials that could qualify as mixed TRU waste. There are many technologies that offer the potential for remediating this waste but few that tackle all or most of the contaminants and even fewer that have been deployed with confidence. This paper outlines the progress made in proving the ability of Supercritical Fluid Extraction as a method of remediating soil, classified as mixed (TRU) transuranic waste

Safety Assessment Approach for Decision Making Related to Remedial Measures and Radioactive Waste Management

International Nuclear Information System (INIS)

Rybalka, Nataliia; Kondratyev, Sergiy; Alekseeva, Zoya

2016-01-01

Conclusions: At each particular case of “legacy” radioactive waste management facilities the optimized remedial measures should be justified taken into account: • results of facility investigations; • site status and characteristics; • safety assessment; • economical reasons; • societal factors; • timeframes; • available technologies and techniques

Responsiveness summary for the remedial investigation/feasibility study for management of the bulk wastes at the Weldon Spring quarry, Weldon Spring, Missouri

International Nuclear Information System (INIS)

Peterson, J.M.; MacDonell, M.M.

1990-08-01

The US Department of Energy (DOE) is responsible for conducting remedial actions at the Weldon Spring site in St. Charles County, Missouri, under its Surplus Facilities Management Program. The site consists of a quarry and a chemical plant area located about 6.4 km (4 mi) northeast of the quarry. The quarry is surrounded by the Weldon Spring Wildfire Area and is near an alluvial well field that constitutes a major source of potable water for St. Charles County; the nearest supply well is located about 0.8 km (0.5 mi) southeast of the quarry. From 1942 to 1969, the quarry was used for the disposal of various radioactively and chemically contaminated materials. Bulk wastes in the quarry consist of contaminated soils and sediments, rubble, metal debris, and equipment. As part of overall site remediation, DOE is proposing to conduct an interim remedial action at the quarry to manage the radioactively and chemically contaminated bulk wastes contained therein. Potential remedial action alternatives for managing the quarry bulk wastes have been evaluated consistent with US Environmental Protection Agency (EPA) guidance for conducting remedial actions under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. The contents of these documents were developed in consultation with EPA Region VII and the state of Missouri and reflect the focused scope defined for this interim remedial action. 9 refs

Environmental remediation and waste management in the United States

International Nuclear Information System (INIS)

Muntzing, L.M.; Person, J.C.

1994-01-01

Environmental remediation of radioactively and chemically contaminated sites represents one of the most complex challenges of our age. It is currently a problem at nuclear weapons sites in the United States, but as the civilian nuclear industry everywhere deals with decommissioning and decontamination, the lessons learned from these early activities will be influential. The task is challenging for several reasons. First, standards governing remedial action are complex and constantly evolving. Second, unless contaminated material is to be stabilized in place, it must be removed and sent to another facility for storage and ultimate disposal. Third the task is technically demanding. Those who undertake the challenge must be technically sophisticated, creative, and innovative. Fourth, the challenge is a risky one. Those who seek to remediate past contamination may find themselves exposed to expanding and unfair allegations of liability for that very contamination. Finally, there is often a basic crisis of public confidence regarding remediation efforts

Cost considerations in remediation and disposal

International Nuclear Information System (INIS)

Dance, J.T.; Huddleston, R.D.

1999-01-01

Opportunities for assessing the costs associated with the reclamation and remediation of sites contaminated by oilfield wastes are discussed. The savings can be maximized by paying close attention to five different aspects of the overall site remediation and disposal process. These are: (1) highly focused site assessment, (2) cost control of treatment and disposal options, (3) value added cost benefits, (4) opportunities to control outside influences during the remedial process, and (5) opportunities for managing long-term liabilities and residual risk remaining after the remedial program is completed. It is claimed that addressing these aspects of the process will ultimately lower the overall cost of site remediation and waste disposal

Solid phase bio-electrofermentation of food waste to harvest value-added products associated with waste remediation.

Science.gov (United States)

Chandrasekhar, K; Amulya, K; Mohan, S Venkata

2015-11-01

A novel solid state bio-electrofermentation system (SBES), which can function on the self-driven bioelectrogenic activity was designed and fabricated in the laboratory. SBES was operated with food waste as substrate and evaluated for simultaneous production of electrofuels viz., bioelectricity, biohydrogen (H2) and bioethanol. The system illustrated maximum open circuit voltage and power density of 443 mV and 162.4 mW/m(2), respectively on 9 th day of operation while higher H2 production rate (21.9 ml/h) was observed on 19th day of operation. SBES system also documented 4.85% w/v bioethanol production on 20th day of operation. The analysis of end products confirmed that H2 production could be generally attributed to a mixed acetate/butyrate-type of fermentation. Nevertheless, the presence of additional metabolites in SBES, including formate, lactate, propionate and ethanol, also suggested that other metabolic pathways were active during the process, lowering the conversion of substrate into H2. SBES also documented 72% substrate (COD) removal efficiency along with value added product generation. Continuous evolution of volatile fatty acids as intermediary metabolites resulted in pH drop and depicted its negative influence on SBES performance. Bio-electrocatalytic analysis was carried out to evaluate the redox catalytic capabilities of the biocatalyst. Experimental data illustrated that solid-state fermentation can be effectively integrated in SBES for the production of value added products with the possibility of simultaneous solid waste remediation. Copyright © 2015 Elsevier Ltd. All rights reserved.

Tank waste remediation system retrieval and disposal mission readiness-to-proceed guidance and requirements to deliverables crosswalk

International Nuclear Information System (INIS)

Hall, C.E.

1998-01-01

In September 1996, the US Department of Energy, Richland Operations Office (RL) initiated the first of a two-phase program to remediate waste storage in tanks at the Hanford Site in Washington State. Initiating the first phase, RL signed contracts with two private companies who agreed to receive and vitrify a portion of the tank waste in a demonstration and to return the vitrified product and by-products to the Project Management Hanford Contract (PHMC) team for disposition. The first phase of the overall remediation effort is a demonstration of treatment concepts, and the second phase includes treatment of the remaining tank wastes. The demonstration phase, Phase 1 of the project, is further subdivided into two parts, A and B. During Phase 1A, the vitrification contractors are to establish the technical, operational, regulatory, business, and financial elements required to provide treatment services on a fixed unit price basis. Phase 1A deliverables will be evaluated by RL to determine whether it is in the best interest of the government to have one or more vitrification contractors proceed with Phase 1B, in which 6% to 13% of the tank waste would be treated in the demonstration. In addition, before RL can authorize proceeding with Phase 1B, the PHMC team must demonstrate its readiness to retrieve and deliver the waste to the private contractor(s) and to receive and dispose of the products and by-products returned from the treatment. The PHMC team has organized their plans for providing these vitrification-support services into the Retrieval and Disposal Mission within the Tank Waste Remediation System (TWRS) Project. Three RL core teams were established to assist in evaluating the PHMC team's readiness specifically in regard to three task areas: Waste feed delivery; Infrastructure and by-products delivery; and Immobilized products. The core teams each developed a set of criteria and plans to be used in evaluating the PHMC team's readiness to proceed (RTP)

Electrodialytic remediation of CCA-treated waste wood in a 2 m3 pilot plant

DEFF Research Database (Denmark)

Christensen, Iben Vernegren; Pedersen, Anne Juul; Ottosen, Lisbeth M.

2006-01-01

Waste wood that has been treated with chromated-copper-arsenate (CCA) poses a potential environmental problem due to the content of copper, chromium and arsenic. A pilot plant for electrodialytic remediation of up to 2 m3 wood has been designed and tested and the results are presented here. Sever...

Remediation of electronic waste polluted soil using a combination of persulfate oxidation and chemical washing.

Science.gov (United States)

Chen, Fu; Luo, Zhanbin; Liu, Gangjun; Yang, Yongjun; Zhang, Shaoliang; Ma, Jing

2017-12-15

Laboratory experiments were conducted to investigate the efficiency of a simultaneous chemical extraction and oxidation for removing persistent organic pollutants (POPs) and toxic metals from an actual soil polluted by the recycling activity of electronic waste. Various chemicals, including hydroxypropyl-β-cyclodextrin (HPCD), citric acid (CA) and sodium persulfate (SP) were applied synchronously with Fe 2+ activated oxidation to enhance the co-removal of both types of pollutants. It is found that the addition of HPCD can enhance POPs removal through solubilization of POPs and iron chelation; while the CA-chelated Fe 2+ activation process is effective for extracting metals and degrading residual POPs. Under the optimized reagent conditions, 69.4% Cu, 78.1% Pb, 74.6% Ni, 97.1% polychlorinated biphenyls, 93.8% polycyclic aromatic hydrocarbons, and 96.4% polybrominated diphenylethers were removed after the sequential application of SP-HPCD-Fe 2+ and SP-CA-Fe 2+ processes with a duration of 180 and 240 min, respectively. A high dehalogenation efficiency (84.8% bromine and 86.2% chlorine) is observed, suggesting the low accumulation of halogen-containing organic intermediates. The remediated soil can satisfy the national soil quality standard of China. Collectively, co-contaminated soil can be remediated with reasonable time and capital costs through simultaneous application of persulfate oxidation and chemical extraction. Copyright © 2017 Elsevier Ltd. All rights reserved.

Salmon Site Remedial Investigation Report

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

A strategy for end point criteria for Superfund remediation

International Nuclear Information System (INIS)

Hwang, S.T.

1992-06-01

Since the inception of cleanup for hazardous waste sites, estimating target cleanup levels has been the subject of considerable investigation and debate in the Superfund remediation process. Establishing formal procedures for assessing human health risks associated with hazardous waste sites has provided a conceptual framework for determining remediation goals and target cleanup levels (TCLs) based on human health and ecological risk consideration. This approach was once considered at variance with the concept of the pre-risk assessment period; that is, cleaning up to the background level, or using containment design or best available control technologies. The concept has been gradually adopted by the regulatory agencies and the parties responsible for cleanup. Evaluation of cleanup strategies at the outset of the planning stage will eventually benefit the parties responsible for cleanup and the oversight organizations, including regulatory agencies. Development of the strategies will provide an opportunity to promote an improvement in the pace and quality of many activities to be carried out. The strategies should help address the issues related to (1) improving remediation management activities to arrive at remediation as expeditiously as possible, (2) developing alternate remediation management activities, (3) identifying obstructing issues to management for resolution, (4) adapting the existing framework to correspond to the change in remediation statutes and guidelines, and (5) providing the basis for evaluating options for the record of decision process. This paper will discuss some of the issues and the research efforts that were addressed as part of the strategies requiring future discussion and comment

EM-54 Technology Development In Situ Remediation Integrated Program

International Nuclear Information System (INIS)

1993-08-01

The Department of Energy (DOE) established the Office of Technology Development (EM-50) as an element of Environmental Restoration and Waste Management (EM) in November 1989. EM manages remediation of all DOE sites as well as wastes from current operations. The goal of the EM program is to minimize risks to human health, safety and the environment, and to bring all DOE sites into compliance with Federal, state, and local regulations by 2019. EM-50 is charged with developing new technologies that are safer, more effective and less expensive than current methods. The In Situ Remediation Integrated Program (the subject of this report) is part of EM-541, the Environmental Restoration Research and Development Division of EM-54. The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: Significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces; in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP tends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years

Tank waste remediation system multi-year work plan

International Nuclear Information System (INIS)

1994-09-01

The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging open-quotes out sourcingclose quotes of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders

Tank waste remediation system multi-year work plan

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging {open_quotes}out sourcing{close_quotes} of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders.

Simulant composition for the Mixed Waste Management Facility (MWMF) groundwater remediation project

International Nuclear Information System (INIS)

Siler, J.L.

1992-01-01

A project has been initiated at the request of ER to study and remediate the groundwater contamination at the Mixed Waste Management Facility (MWMF). This water contains a wide variety of both inorganics (e.g., sodium) and organics (e.g., benzene, trichloroethylene). Most compounds are present in the ppB range, and certain components (e.g., trichloroethylene, silver) are present at concentrations that exceed the primary drinking water standards (PDWS). These compounds must be reduced to acceptable levels as per RCRA and CERCLA orders. This report gives a listing of the important constituents which are to be included in a simulant to model the MWMF aquifer. This simulant will be used to evaluate the feasibility of various state of the art separation/destruction processes for remediating the aquifer

Summary Report of Comprehensive Laboratory Testing to Establish the Effectiveness of Proposed Treatment Methods for Unremediated and Remediated Nitrate Salt Waste Streams

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-04

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report documents the effectiveness of two treatment methods proposed to stabilize both the unremediated and remediated nitrate salt waste streams (UNS and RNS, respectively) at Los Alamos National Laboratory (LANL). The two technologies include the addition of zeolite (with and without the addition of water as a processing aid) and cementation. Surrogates were developed to evaluate both the solid and liquid fractions expected from parent waste containers, and both the solid and liquid fractions were tested. Both technologies are shown to be effective at eliminating the characteristic of ignitability (D001), and the addition of zeolite was determined to be effective at eliminating corrosivity (D002), with the preferred option1 of adding zeolite currently planned for implementation at LANL’s Waste Characterization, Reduction, and Repackaging Facility (WCRRF). The course of this work verified the need to evaluate and demonstrate the effectiveness of the proposed remedy for debris material, if required. The evaluation determined that WypAlls, cheesecloth, and Celotex absorbed with saturated nitrate salt solutions exhibit the ignitability characteristic (all other expected debris is not classified as ignitable). Finally, liquid surrogates containing saturated nitrate salts did not exhibit the characteristic of ignitability in their pure form (those neutralized with Kolorsafe and mixed with sWheat did exhibit D001). Sensitivity testing and an analysis were conducted to evaluate the waste form for reactivity. Tests included subjecting surrogate material to mechanical impact, friction, electrostatic discharge and thermal insults. The testing confirmed that the waste does not exhibit the characteristic of

Role of biochar on composting of organic wastes and remediation of contaminated soils-a review.

Science.gov (United States)

Wu, Shaohua; He, Huijun; Inthapanya, Xayanto; Yang, Chunping; Lu, Li; Zeng, Guangming; Han, Zhenfeng

2017-07-01

Biochar is produced by pyrolysis of biomass residues under limited oxygen conditions. In recent years, biochar as an amendment has received increasing attention on composting and soil remediation, due to its unique properties such as chemical recalcitrance, high porosity and sorption capacity, and large surface area. This paper provides an overview on the impact of biochar on the chemical characteristics (greenhouse gas emissions, nitrogen loss, decomposition and humification of organic matter) and microbial community structure during composting of organic wastes. This review also discusses the use of biochar for remediation of soils contaminated with organic pollutants and heavy metals as well as related mechanisms. Besides its aging, the effects of biochar on the environment fate and efficacy of pesticides deserve special attention. Moreover, the combined application of biochar and compost affects synergistically on soil remediation and plant growth. Future research needs are identified to ensure a wide application of biochar in composting and soil remediation. Graphical abstract ᅟ.

Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 1: Executive summary

International Nuclear Information System (INIS)

Peters, B.B.; Cameron, R.J.; McCormack, W.D.

1994-08-01

This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program to aid technology development funding decisions for radioactive tank waste remediation. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. These methods do not show the relative effect of new technologies on tank remediation systems as a whole. Consequently, DOE may spend its resources on technologies that promise to improve a single function but have a small or possibly negative, impact on the overall system, or DOE may overlook a technology that does not address a high priority problem in the system but that does, if implemented, offer sufficient overall improvements. Systems engineering and detailed analyses often conducted under the National Environmental Policy Act (NEPA 1969) use a ''whole system'' approach but are costly, too time-consuming, and often not sufficiently focused to support the needs of the technology program decision-makers. An alternative approach is required to evaluate these systems impacts but still meet the budget and schedule needs of the technology program

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2

Energy Technology Data Exchange (ETDEWEB)

Lewis, BE

2003-10-07

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2

International Nuclear Information System (INIS)

Lewis, BE

2003-01-01

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and ∼420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed ∼5.5 years ahead of schedule and ∼$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team

Innovative technologies for the remediation of transuranic- contaminated landfills

International Nuclear Information System (INIS)

Kostelnik, K.M.

1995-01-01

The US Department of Energy (DOE) has initiated a comprehensive research,development, demonstration, testing and evaluation program to provide innovative technology systems to achieve its environmental management responsibilities. The Office of Technology Development (OTD) is responsible for this research in support of the Offices of Environmental Restoration and Waste Management efforts. In fiscal year (FY) 1992 the OTD established the Buried Waste Integrated Demonstration (BWID). The BWID mission was to support the development of emerging technologies for their application to the remediation of DOE buried waste site. During FY95, the BWID program was transitioned into a larger program which will focus its attention to DOE Landfills and Contaminated Soils. There search and activities formerly referred to as the BWID will now be associated with the Transuranic-contaminated Arid Landfill Stabilization Program.(TALS). The TALS Program supports these buried waste remediation efforts by seeking out the best talent to solve the technology challenges as identified in baseline remediation strategies. Experts from throughout the DOE complex, universities, private sector, and the international community are being included in this program to solve these challenges and ensure implementation and commercialization of innovative technologies

Cooperative expert system reasoning for waste remediations

International Nuclear Information System (INIS)

Bohn, S.J.; Pennock, K.A.; Franklin, A.L.

1991-12-01

The United States Department of Energy (DOE) is facing a large task in completing Remedial Investigations and Feasibility Studies (RI/FS) for hazardous waste sites across the nation. One of the primary objectives of an RI/FS is the specification of viable sequences of technology treatment trains which can provide implementable site solutions. We present a methodology which integrates expert system technology within an object-oriented framework to create a cooperative reasoning system designed to provide a comprehensive list of these implementable solutions. The system accomplishes its goal of specifying technology trains by utilizing a ''team'' of expert system objects. The system distributes the problem solving among the individual expert objects, and then coordinates the combination of individual decisions into a joint solution. Each expert object possesses the knowledge of an expert in a particular technology. An expert object can examine the parameters and characteristics of the waste site, seek information and support from other expert objects, and then make decisions concerning its own applicability. This methodology has at least two primary benefits. First, the creation of multiple expert objects provides a more direct mapping from the actual process to a software system, making the system easier to build. Second, the distribution of the inferencing among a number of loosely connected expert objects allows for a more robust and maintainable final product

Dissolution test for low-activity waste product acceptance

International Nuclear Information System (INIS)

Ebert, W. L.

1998-01-01

We have measured the mean and standard deviation of the solution concentrations of B, Na, and Si attained in replicate dissolution tests conducted at temperatures of 20, 40, and 70 C, for durations of 3 and 7 days, and at glass/water mass ratios of 1:10 and 1:1. These and other tests were conducted to evaluate the adequacy of the test methods specified in privatization contracts and to develop a data base that can be used to evaluate the reliability of reported results for tests performed on the waste products. Tests were conducted with a glass that we formulated to be similar to low-activity waste products that will be produced during the remediation of Hanford tank wastes. Statistical analyses indicated that, while the mean concentrations of B, Na, and Si were affected by the values of test parameters, the standard deviation of replicate tests was not. The precision of the tests was determined primarily by uncertainties in the analysis of the test solutions. Replicate measurements of other glass properties that must be reported for Hanford low-activity waste products were measured to evaluate the possible adoption of the glass used in these tests as a standard test material for the product acceptance process

Waste Derived Sorbents and Their Potential Roles in Heavy Metal Remediation Applications

Directory of Open Access Journals (Sweden)

Chiang Y. W.

2013-04-01

Full Text Available Inorganic waste materials that have the suitable inherent characteristics could be used as precursors for the synthesis of micro- and mesoporous materials, which present great potential to be re-utilized as sorbent materials for heavy metal remediation. Three inorganic waste materials were studied in the present work: water treatment residuals (WTRs from an integrated drinking water/wastewater treatment plant, and fly ash and bottom ash samples from a municipal solid waste incinerator (MSWI. These wastes were converted into three sorbent materials: ferrihydrite-like materials derived from drying of WTRs, hydroxyapatite-like material derived from ultrasound assisted synthesis of MSWI fly ash with phosphoric acid solution, and a zeolitic material derived from alkaline hydrothermal conversion of MSWI bottom ash. The performance of these materials, as well as their equivalent commercially available counterparts, was assessed for the adsorption of multiple heavy metals (As, Cd, Co, Ni, Pb, Zn from synthetic solutions, contaminated sediments and surface waters; and satisfactory results were obtained. In addition, it was observed that the combination of sorbents into sorbent mixtures enhanced the performance levels and, where applicable, stabilized inherently mobile contaminants from the waste derived sorbents.

Environmental remediation and waste management in the United States

International Nuclear Information System (INIS)

Muntzing, L.M.; Person, J.C.

1994-01-01

Environmental remediation of radioactively and chemically contaminated sites represents one of the most complex challenges of our age. It is currently a problem at nuclear weapons sites in the Unites States, but as the civilian nuclear industry everywhere deals with decommissioning and decontamination, the lessons learned from these early activities will be influential. The task is challenging for several reasons. First, standards governing remedial action are complex and constantly evolving. Second, unless contaminated material is to be stabilized in place, it must be removed and sent to another facility for storage and ultimate disposal. Third, the task is technically demanding. Those who undertake the challenge must be technically sophisticated, creative, and innovative. Fourth, the challenge is a risky one. Those who seek to remediate past contamination may find themselves exposed to expanding and unfair allegations of liability for that very contamination. Finally, there is often a basic crisis of public confidence regarding remediation efforts. This paper briefly outlines some of the liabilities surrounding environmental contracting and ways to minimize risks

77 FR 72691 - Small Business Size Standards: Administrative and Support, Waste Management and Remediation Services

Science.gov (United States)

2012-12-06

... importantly, the Small Business Act requires SBA to establish one definition of what is a small business... SMALL BUSINESS ADMINISTRATION 13 CFR Part 121 RIN 3245-AG27 Small Business Size Standards: Administrative and Support, Waste Management and Remediation Services AGENCY: U.S. Small Business Administration...

Waste management plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-03-01

This waste management plan defines the procedures for control and management of waste generated as a result of the removal action of the YS-86O Firing Ranges site at the Oak Ridge Y-12 Plant. This document includes plan objectives; remediation activities; key personnel; waste generation activities; and waste treatment, storage, transportation, and disposal. Methods of control and characterization of waste generated as a result of remediation activities will be within the guidelines and procedures outlined herein. ENTECH personnel will make every effort when conducting remediation and decontamination activities to minimize the amount of generated waste

Tank waste remediation system systems engineering management plan

International Nuclear Information System (INIS)

Peck, L.G.

1998-01-01

This Systems Engineering Management Plan (SEMP) describes the Tank Waste Remediation System (TWRS) implementation of the US Department of Energy (DOE) systems engineering policy provided in 97-IMSD-193. The SEMP defines the products, process, organization, and procedures used by the TWRS Project to implement the policy. The SEMP will be used as the basis for tailoring the systems engineering applications to the development of the physical systems and processes necessary to achieve the desired end states of the program. It is a living document that will be revised as necessary to reflect changes in systems engineering guidance as the program evolves. The US Department of Energy-Headquarters has issued program management guidance, DOE Order 430. 1, Life Cycle Asset Management, and associated Good Practice Guides that include substantial systems engineering guidance

Final remediation of the provisional storage near Zavratec

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.

2000-01-01

In the Western part of Slovenia near the village of Zavratec radioactive waste from the decontamination of the Oncological Institute has been stored in an old abandoned military barracks for many decades. The ARAO Agency had been assigned to remediate this provisional storage. In 1996 the first phase of the remediation was concluded, in which the measurements, inventorying and repacking of radioactive waste were carried out. At the end of this phase the waste was restored. After three years of suspension, the remedial work continued in autumn 1999 with the separation of radioactive from non-radioactive waste and transportation of all radioactive waste to the Slovenian central storage for small producers near Ljubljana. At the beginning of the year 2000 the old storage near Zavratec was completely decontaminated to be released for unrestricted use. The preparation for and the implementation of remedial actions are presented in the paper. (author)

Public values related to decisions in the Tank Waste Remediation System Program

International Nuclear Information System (INIS)

Armacost, L.L.; Robershotte, M.; von Winterfeldt, D.; Creighton, J.

1994-10-01

Managers of the Tank Waste Remediation System (TWRS) Program have to make numerous decisions, ranging from the strategic decisions on the fundamental tank cleanup goals to technical decisions on which types of equipment to use in mechanical retrieval of wastes. Furthermore, many of these decisions have to be made repeatedly (e.g., the annual allocation of research and development funds to TWRS activities). These decisions have many potential consequences in terms of risks to workers, risks to the public, environmental impacts, and economic development and cost. Because these consequences affect the values of many parties, the consequences need to be evaluated in terms that are accepted and understood by the interested parties. Therefore, an effort needs to be made to incorporate public concerns and values into the TWRS decision-making process. The purpose of this report is to review and integrate this past work on values and to create a maser list of values in order to create a consistent value framework for the numerous TWRS decisions; efficiently and effectively use public values in the decision-making process by updating this report on a regular basis to ensure that the information represents the public's current views; provide guidance about using values in technical TWRS decisions

Tank waste remediation system retrieval and disposal mission readiness-to-proceed guidance and requirements to deliverables crosswalk

International Nuclear Information System (INIS)

Hall, C.E.

1998-01-01

Before RL can authorize proceeding with Phase 1B, the PHMC team must demonstrate its readiness to retrieve and deliver the waste to the private contractors and to receive and dispose of the products and byproducts returned from the treatment. The PHMC team has organized their plans for providing these vitrification-support services into the Retrieval and Disposal Mission within the Tank Waste Remediation System (TWRS) Program

Remedial action and waste disposal project -- 100-DR-1 remedial action readiness assessment report

International Nuclear Information System (INIS)

April, J.G.; Ard, J.A.; Corpuz, F.M.; DeMers, S.K.; Donahoe, R.L.; Frank, J.M.; Hobbs, B.J.; Roeck, F.V.

1997-02-01

This readiness assessment report presents the results of the project readiness assessment for the 100-DR-1 source sites remediation. The assessment was conducted at the conclusion of a series of project activities that began in August 1996. These activities included confirming the completion of project-specific procedures, training of staff, obtaining support equipment, receipt of subcontractor submittals, and mobilization and construction of site support systems

Program plan for evaluation and remediation of the generation and release of flammable gases in Hanford Site waste tanks

International Nuclear Information System (INIS)

Johnson, G.D.

1991-08-01

This program plan describes the activities being conducted for the resolution of the flammable gas problem that is associated with 23 high-level waste tanks at the Hanford Site. The classification of the wastes in all of these tanks is not final and some wastes may not be high-level wastes. However, until the characterization and classification is complete, all the tanks are treated as if they contain high-level waste. Of the 23 tanks, Tank 241-SY-101 (referred to as Tank 101-SY) has exhibited significant episodic releases of flammable gases (hydrogen and nitrous oxide) for the past 10 years. The major near-term focus of this program is for the understanding and stabilization of this tank. An understanding of the mechanism for gas generation and the processes for the episodic release will be obtained through sampling of the tank contents, laboratory studies, and modeling of the tank behavior. Additional information will be obtained through new and upgraded instrumentation for the tank. A number of remediation, or stabilization, concepts will be evaluated for near-term (2 to 3 years) applications to Tank 101-SY. Detailed safety assessments are required for all activities that will occur in the tank (sampling, removal of equipment, and addition of new instruments). This program plan presents a discussion of each task, provides schedules for near-term activities, and gives a summary of the expected work for fiscal years 1991, 1992, and 1993. 16 refs., 7 figs., 8 tabs

Program plan for evaluation and remediation of the generation and release of flammable gases in Hanford Site waste tanks

Energy Technology Data Exchange (ETDEWEB)

Johnson, G.D. (comp.)

1991-08-01

This program plan describes the activities being conducted for the resolution of the flammable gas problem that is associated with 23 high-level waste tanks at the Hanford Site. The classification of the wastes in all of these tanks is not final and some wastes may not be high-level wastes. However, until the characterization and classification is complete, all the tanks are treated as if they contain high-level waste. Of the 23 tanks, Tank 241-SY-101 (referred to as Tank 101-SY) has exhibited significant episodic releases of flammable gases (hydrogen and nitrous oxide) for the past 10 years. The major near-term focus of this program is for the understanding and stabilization of this tank. An understanding of the mechanism for gas generation and the processes for the episodic release will be obtained through sampling of the tank contents, laboratory studies, and modeling of the tank behavior. Additional information will be obtained through new and upgraded instrumentation for the tank. A number of remediation, or stabilization, concepts will be evaluated for near-term (2 to 3 years) applications to Tank 101-SY. Detailed safety assessments are required for all activities that will occur in the tank (sampling, removal of equipment, and addition of new instruments). This program plan presents a discussion of each task, provides schedules for near-term activities, and gives a summary of the expected work for fiscal years 1991, 1992, and 1993. 16 refs., 7 figs., 8 tabs.

Integration of biotechnology in remediation and pollution prevention activities

International Nuclear Information System (INIS)

Strong-Gunderson, J.M.

1996-01-01

The North American Free Trade Agreement/North American Agreement on Environmental Cooperation provides a mechanism for an international collaboration between the US, Canada, and Mexico to jointly develop, modify, or refine technologies that remediate or protect the environment. These countries have a vested interest in this type of collaboration because contaminants do not respect the boundaries of a manufacturing site, region, city, state, or country. The Environmental Sciences Division (ESD) at Oak Ridge National Laboratory (ORNL) consists of a diverse group of individuals who address a variety of environmental issues. ESD is involved in basic and applied research on the fate, transport, and remediation of contaminants; environmental assessment; environmental engineering; and demonstrations of advanced remediation technologies. The remediation and protection of the environment includes water, air, and soils for organic, inorganic, and radioactive contaminants. In addition to remediating contaminated sites, research also focuses on life-cycle analyses of industrial processes and the production of green technologies. The author focuses this discussion on subsurface remediation and pollution prevention; however, the research activities encompass water, soil and air and many of the technologies are applicable to all environments. The discussion focuses on the integration of biotechnology with remediation activities and subsequently linking these biological processes to other remediation technologies

Chemical and microbial remediation of hexavalent chromium from contaminated soil and mining/metallurgical solid waste: a review.

Science.gov (United States)

Dhal, B; Thatoi, H N; Das, N N; Pandey, B D

2013-04-15

Chromium is a highly toxic non-essential metal for microorganisms and plants, and its occurrence is rare in nature. Lower to higher chromium containing effluents and solid wastes released by activities such as mining, metal plating, wood preservation, ink manufacture, dyes, pigments, glass and ceramics, tanning and textile industries, and corrosion inhibitors in cooling water, induce pollution and may cause major health hazards. Besides, natural processes (weathering and biochemical) also contribute to the mobility of chromium which enters in to the soil affecting the plant growth and metabolic functions of the living species. Generally, chemical processes are used for Cr- remediation. However, with the inference derived from the diverse Cr-resistance mechanism displayed by microorganisms and the plants including biosorption, diminished accumulation, precipitation, reduction of Cr(VI) to Cr(III), and chromate efflux, bioremediation is emerging as a potential tool to address the problem of Cr(VI) pollution. This review focuses on the chemistry of chromium, its use, and toxicity and mobility in soil, while assessing its concentration in effluents/wastes which becomes the source of pollution. In order to conserve the environment and resources, the chemical/biological remediation processes for Cr(VI) and their efficiency have been summarised in some detail. The interaction of chromium with various microbial/bacterial strains isolated and their reduction capacity towards Cr(VI) are also discussed. Copyright © 2013 Elsevier B.V. All rights reserved.

Waste management, decommissioning and environmental restoration for Canada's nuclear activities. Proceedings

International Nuclear Information System (INIS)

2011-01-01

The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held in Toronto, Ontario, Canada on September 11-14, 2011. The conference provided a forum for discussion of the status and proposed future directions of technical, regularly, environmental, social and economic aspects of radioactive waste management, nuclear facility decommissioning, and environmental restoration activities for Canadian nuclear facilities. The conference included both plenary sessions and sessions devoted to more detailed technical issues. The plenary sessions were focussed on three broad themes: the overall Canadian program; low and intermediate waste; and, international perspectives. Topics of the technical sessions included: OPG's deep geologic repository for low and intermediate level waste; stakeholder interactions; decommissioning projects; uranium mine waste management; used fuel repository - design and safety assessment; federal policies, programs and oversight; regulatory considerations; aboriginal traditional knowledge; geological disposal - CRL site classification; geological disposal - modelling and engineered barriers; Port Hope Area Initiative; waste characterization; LILWM - treatment and processing; decommissioning projects and information management; international experience; environmental remediation; fuel cycles and waste processing.

Engineering Options Assessment Report. Nitrate Salt Waste Stream Processing

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-11-13

This report examines and assesses the available systems and facilities considered for carrying out remediation activities on remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The assessment includes a review of the waste streams consisting of 60 RNS, 29 above-ground UNS, and 79 candidate below-ground UNS containers that may need remediation. The waste stream characteristics were examined along with the proposed treatment options identified in the Options Assessment Report . Two primary approaches were identified in the five candidate treatment options discussed in the Options Assessment Report: zeolite blending and cementation. Systems that could be used at LANL were examined for housing processing operations to remediate the RNS and UNS containers and for their viability to provide repackaging support for remaining LANL legacy waste.

Engineering Options Assessment Report: Nitrate Salt Waste Stream Processing

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-11-18

This report examines and assesses the available systems and facilities considered for carrying out remediation activities on remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The assessment includes a review of the waste streams consisting of 60 RNS, 29 aboveground UNS, and 79 candidate belowground UNS containers that may need remediation. The waste stream characteristics were examined along with the proposed treatment options identified in the Options Assessment Report . Two primary approaches were identified in the five candidate treatment options discussed in the Options Assessment Report: zeolite blending and cementation. Systems that could be used at LANL were examined for housing processing operations to remediate the RNS and UNS containers and for their viability to provide repackaging support for remaining LANL legacy waste.

Oak Ridge K-25 Site Technology Logic Diagram. Volume 3, Technology evaluation data sheets; Part B, Remedial action, robotics/automation, waste management

Energy Technology Data Exchange (ETDEWEB)

Fellows, R.L. [ed.

1993-02-26

The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration (ER) and waste management (WN) problems at the Oak Ridge K-25 Site. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remediation, decontamination, and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This volume 3 B provides the Technology Evaluation Data Sheets (TEDS) for ER/WM activities (Remedial Action Robotics and Automation, Waste Management) that are referenced by a TEDS code number in Vol. 2 of the TLD. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than each technology in Vol. 2. The TEDS are arranged alphanumerically by the TEDS code number in the upper right corner of each data sheet. Volume 3 can be used in two ways: (1) technologies that are identified from Vol. 2 can be referenced directly in Vol. 3 by using the TEDS codes, and (2) technologies and general technology areas (alternatives) can be located in the index in the front of this volume.

Cost benefit of caustic recycle for tank waste remediation at the Hanford and Savannah River Sites

International Nuclear Information System (INIS)

DeMuth, S.

1998-01-01

The potential cost savings due to the use of caustic recycle used in conjunction with remediation of radioactive underground storage tank waste, is shown in a figure for the Hanford and Savannah River sites. Two cost savings estimates for each case have been made for Hanford, and one cost savings estimate for each case have been made for Hanford, and one cost savings estimate for each case has been made for the Savannah River site. This is due to the Hanford site remediation effort being less mature than that of Savannah River; and consequently, a range of cost savings being more appropriate for Hanford. This range of cost savings (rather than a ingle value) for each case at Hanford is due to cost uncertainties related to the LAW immobilization operation. Caustic recycle Case-1 has been defined as the sodium required to meet al identified caustic needs for the entire Site. Case-2 has been defined as the maximum sodium which can be separated from the low activity waste without precipitation of Al(OH) 3 . It has been determined that the potential cost savings at Hanford ranges from $194 M to $215 M for Case-1, and $293 M to $324 M for Case-2. The potential cost savings at Savannah River are $186 M for Case-1 and $281 M for Case-2. A discussion of the uncertainty associated with these cost savings estimates can be found in the Discussion and Conclusions section

Waste management facility remediation and decommissioning at a national nuclear research site

International Nuclear Information System (INIS)

Cameron, D.J.; Dolinar, G.M.; Killey, R.W.D.

1994-01-01

Historic waste management practices at eight locations on AECL's Chalk River site have resulted in the formation of contaminated groundwater plumes, some of which have surfaced and contaminated surface materials. A priority setting process has been used to establish a plan of attack that will lead to the eventual decommissioning of these facilities. In general terms, the preferred approach is to install impermeable covers to prevent further leaching of waste sources and to prevent escape of leachate to the biosphere, followed by cleanup of surface contamination and remediation of aquifers. Final disposal of the waste sources would be delayed for perhaps 20 years. Substantial progress has been made in the treatment of contaminated groundwater, with one field installation in place and another under development. This paper describes how the prioritization task was tackled to produce a long term plan of action and describes initial interventions that have been attempted and their results. 4 refs., 3 tabs., 3 figs

Tank Waste Remediation System Inactive Miscellaneous Underground Storage Tanks Program Plan

International Nuclear Information System (INIS)

Gustavson, R.D.

1995-12-01

The Program Management Plan (PMP) describes the approach that will be used to manage the Tank Waste Remediation System (TWRS) Inactive Miscellaneous Underground Storage Tank (IMUST) Program. The plan describes management, technical, and administrative control systems that will be used to plan and control the IMUSTs Program performance. The technical data to determine the IMUSTs status for inclusion in the Single Shell Tank Farm Controlled Clean and Stable (CCS) Program. The second is to identify and implement surveillance, characterization, stabilization, and modifications to support CCS prior to final closure

Site remediation techniques in India: a review

International Nuclear Information System (INIS)

Anomitra Banerjee; Miller Jothi

2013-01-01

India is one of the developing countries operating site remediation techniques for the entire nuclear fuel cycle waste for the last three decades. In this paper we intend to provide an overview of remediation methods currently utilized at various hazardous waste sites in India, their advantages and disadvantages. Over the years the site remediation techniques have been well characterized and different processes for treatment, conditioning and disposal are being practiced. Remediation Methods categorized as biological, chemical or physical are summarized for contaminated soils and environmental waters. This paper covers the site remediation techniques implemented for treatment and conditioning of wastelands arising from the operation of nuclear power plant, research reactors and fuel reprocessing units. (authors)

Remedial Design/Remedial Action Work Plan for Operable Units 6-05 and 10-04, Phase III

Energy Technology Data Exchange (ETDEWEB)

R. P. Wells

2006-09-19

The remedial design/remedial action for Operable Unit 6-05 (Waste Area Group 6) and Operable Unit 10-04 (Waste Area Group 10) - collectively called Operable Unit 10-04 has been divided into four phases. Phase I consists of developing and implementing institutional controls at Operable Unit 10-04 sites and developing and implementing Idaho National Laboratory-wide plans for both institutional controls and ecological monitoring. Phase II will remediate sites contaminated with trinitrotoluene and Royal Demolition Explosive. Phase III will remediate lead contamination at a gun range, and Phase IV will remediate hazards from unexploded ordnance. This Phase III remedial Design/Remedial Action Work Plan addresses the remediation of lead-contaminated soils found at the Security Training Facility (STF)-02 Gun Range located at the Idaho National Laboratory. Remediation of the STF-02 Gun Range will include excavating contaminated soils; physically separating copper and lead for recycling; returning separated soils below the remediation goal to the site; stabilizing contaminated soils, as required, and disposing of the separated soils that exceed the remediation goal; encapsulating and disposing of creosote-contaminated railroad ties and power poles; removing and disposing of the wooden building and asphalt pads found at the STF-02 Gun Range; sampling and analyzing soil to determine the excavation requirements; and when the remediation goals have been met, backfilling and contouring excavated areas and revegetating the affected area.

Biological technologies for the remediation of co-contaminated soil.

Science.gov (United States)

Ye, Shujing; Zeng, Guangming; Wu, Haipeng; Zhang, Chang; Dai, Juan; Liang, Jie; Yu, Jiangfang; Ren, Xiaoya; Yi, Huan; Cheng, Min; Zhang, Chen

2017-12-01

Compound contamination in soil, caused by unreasonable waste disposal, has attracted increasing attention on a global scale, particularly since multiple heavy metals and/or organic pollutants are entering natural ecosystem through human activities, causing an enormous threat. The remediation of co-contaminated soil is more complicated and difficult than that of single contamination, due to the disparate remediation pathways utilized for different types of pollutants. Several modern remediation technologies have been developed for the treatment of co-contaminated soil. Biological remediation technologies, as the eco-friendly methods, have received widespread concern due to soil improvement besides remediation. This review summarizes the application of biological technologies, which contains microbial technologies (function microbial remediation and composting or compost addition), biochar, phytoremediation technologies, genetic engineering technologies and biochemical technologies, for the remediation of co-contaminated soil with heavy metals and organic pollutants. Mechanisms of these technologies and their remediation efficiencies are also reviewed. Based on this study, this review also identifies the future research required in this field.

Strategic Considerations for the Sustainable Remediation of Nuclear Installations

International Nuclear Information System (INIS)

Miller, Susan; Wilson, Ian; Decung, Fabien; Ollivier Dehaye, Catherine; Pellenz, Gilles; Palut-Laurent, Odile; Nitzsche, Olaf; Rehs, Bernd; Altavilla, Massimo; Osimani, Celso; Florya, Sergey; Revilla, Jose-Luis; Efraimsson, Henrik; Baines, Kim; Clark, Anna; Cruickshank, Julian; Mitchell, Nick; Mobbs, Shelly; Orr, Peter; Abu-Eid, Rateb Boby; Durham, Lisa; Morse, John; Walker, Stuart; Weber, Inge; ); Monken-Fernandes, Horst; )

2016-01-01

Nuclear sites around the world are being decommissioned and remedial actions are being undertaken to enable sites, or parts of sites, to be reused. Although such activities are relatively straightforward for most sites, experience has suggested that preventative action is needed to minimise the impact of remediation activities on the environment and the potential burden to future generations. Removing all contamination in order to make a site suitable for any use generates waste and has associated environmental, social and economic drawbacks and benefits. Site remediation should thus be sustainable and result in an overall net benefit. This report draws on recent experience of NEA member countries in nuclear site remediation during decommissioning in order to identify strategic considerations for the sustainable remediation of subsurface contamination - predominantly contaminated soil and groundwater - to describe good practice, and to make recommendations for further research and development. It provides insights for the decision makers, regulators, implementers and stakeholders involved in nuclear site decommissioning so as to ensure the sustainable remediation of nuclear sites, now and in the future. (authors)

Data base management activities for the Remedial Action Program at ORNL, calendar year 1987

International Nuclear Information System (INIS)

Voorhees, L.D.; Hook, L.A.; Gentry, M.J.; McCord, R.A.; Faulkner, M.A.; Newman, K.A.; Owen, P.T.

1988-05-01

The Oak Ridge National Laboratory (ORNL) Remedial Action Program (RAP) was established in FY 1985 to apply corrective measures at areas contaminated with radioactive and/or hazardous chemical wastes. To achieve this goal, numerous and varied studies are being conducted to characterize the waste disposal sites. Environmental data collected in support of other programs at ORNL are also of use to RAP. These studies are generating a voluminous amount of data on a scale unprecedented for ORNL. A computerized Data and Information Management System (DIMS) was developed for RAP to (1) provide a centralized repository for data pertinent to RAP and (2) provide support for the investigations and assessments leading to the long-term remediation of contaminated facilities and sites. 10 refs., 25 figs., 16 tabs

Remediation Approach for the Integrated Facility Disposition Project at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kirk, P.G.; Stephens, Jr.J.M.

2009-01-01

The Integrated Facility Disposition Project (IFDP) is a multi-billion-dollar remediation effort being conducted by the U.S. Department of Energy (DOE) Office of Environmental Management in Oak Ridge, Tennessee. The scope of the IFDP encompasses remedial actions related to activities conducted over the past 65 years at the Oak Ridge National Laboratory (ORNL) and the Y-12 National Security Complex (Y-12). Environmental media and facilities became contaminated as a result of operations, leaks, spills, and past waste disposal practices. ORNL's mission includes energy, environmental, nuclear security, computational, and materials research and development. Remediation activities will be implemented at ORNL as part of IFDP scope to meet remedial action objectives established in existing and future decision documents. Remedial actions are necessary (1) to comply with environmental regulations to reduce human health and environmental risk and (2) to release strategic real estate needed for modernization initiatives at ORNL. The scope of remedial actions includes characterization, waste management, transportation and disposal, stream restoration, and final remediation of contaminated soils, sediments, and groundwater. Activities include removal of at or below-grade substructures such as slabs, underground utilities, underground piping, tanks, basins, pits, ducts, equipment housings, manholes, and concrete-poured structures associated with equipment housings and basement walls/floors/columns. Many interim remedial actions involving groundwater and surface water that have not been completed are included in the IFDP remedial action scope. The challenges presented by the remediation of Bethel Valley at ORNL are formidable. The proposed approach to remediation endeavors to use the best available technologies and technical approaches from EPA and other federal agencies and lessons learned from previous cleanup efforts. The objective is to minimize cost, maximize remedial

Remedial action and waste disposal project: 100-B/C remedial action readiness report

International Nuclear Information System (INIS)

April, J.G.; Bryant, D.L.; Cislo, G.B.

1996-07-01

This Readiness Evaluation Report presents the results of the project readiness evaluation to assess the readiness of the 100-B/C source sites remediation. The 100-B/C Area is located at the Hanford Site in Richland, Washington. The evaluation was conducted at the conclusion of a series of readiness activities that began in May 1996. These activities included confirming the completion of project specific procedures, training of staff, obtaining support equipment, receipt of subcontractor submittals, approval of subcontractor submittals, and mobilization and construction of site support systems

Remediation activities at the Fernald Environmental Management Project (FEMP)

International Nuclear Information System (INIS)

Walsh, T.J.; Danner, R.

1996-01-01

The Fernald Environmental Management Project (FEMP) is a United States Department of Energy (DOE) facility located in southwestern Ohio. The facility began manufacturing uranium products in the early 1950's and continued processing uranium ore concentrates until 1989. The facility used a variety of chemical and metallurgical processes to produce uranium metals for use at other DOE sites across the country. Since the facility manufactured uranium metals for over thirty years, various amounts of radiological contamination exists at the site. Because of the chemical and metallurgical processes employed at the site, some hazardous wastes as defined by the Resource Conservation and Recovery Act (RCRA) were also generated at the site. In 1989. the FEMP was placed on the National Priorities List (NPL) requiring cleanup of the facility's radioactive and chemical contamination under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This paper discusses the proposed remediation activities at the five Operable Units (OUs) designated at the FEMP. In addition, the paper also examines the ongoing CERCLA response actions and RCRA closure activities at the facility

Safe management of wastes from former mining and milling activities in Kyrgyzstan

International Nuclear Information System (INIS)

Nurabaev, A.

2012-01-01

254,4 million cubic meters of mining activity's wastes are accumulated in 92 sites on the territory of Kyrgyzstan. 36 tailings and 25 dumps with total volume of 15,7 million of cubic meters were to responsibility of Ministry of Emergency Situations of Kyrgyzstan Republic by Governmental Decree of Kyrgyzstan Republic after collapse of Soviet Union including: 31 tailings with radioactive wastes and volume of 7,2 million cubic meters; 5 tailings with toxic wastes and volume of 5,2 million cubic meters; 25 mountain dumps of non-conditioned ores and volume of 3,3 million cubic meters. Project proposal are submitted to donor countries and international organizations for consideration of possible technical assistance and grant means issuance for carrying out remediation works of tailings.

Factors for assessment of human health risk associated with remedial action at hazardous waste sites

International Nuclear Information System (INIS)

Stephenson, D.E.; King, C.M.; Looney, B.B.; Holmes, W.G.; Gordon, D.E.

1985-01-01

A risk assessment strategy that is cost effective and minimized human health risks was developed for closure of hazardous waste sites at the Savannah River Plant. The strategy consists of (1) site characterization, (2) contaminant transport modeling, and (3) determination of relative merits of alternative remedial actions according to the degree of health protection they provide

Chemical tailoring of steam to remediate underground mixed waste contaminents

Science.gov (United States)

Aines, Roger D.; Udell, Kent S.; Bruton, Carol J.; Carrigan, Charles R.

1999-01-01

A method to simultaneously remediate mixed-waste underground contamination, such as organic liquids, metals, and radionuclides involves chemical tailoring of steam for underground injection. Gases or chemicals are injected into a high pressure steam flow being injected via one or more injection wells to contaminated soil located beyond a depth where excavation is possible. The injection of the steam with gases or chemicals mobilizes contaminants, such as metals and organics, as the steam pushes the waste through the ground toward an extraction well having subatmospheric pressure (vacuum). The steam and mobilized contaminants are drawn in a substantially horizontal direction to the extraction well and withdrawn to a treatment point above ground. The heat and boiling action of the front of the steam flow enhance the mobilizing effects of the chemical or gas additives. The method may also be utilized for immobilization of metals by using an additive in the steam which causes precipitation of the metals into clusters large enough to limit their future migration, while removing any organic contaminants.

Process Control Plan for Tank 241-SY-101 Surface Level Rise Remediation

International Nuclear Information System (INIS)

ESTEY, S.D.

1999-01-01

The tank 241-SY-101 transfer system was conceived and designed to address the immediate needs presented by rapidly changing waste conditions in tank 241-SY-101. Within the last year or so, the waste in this tank has exhibited unexpected behavior (Rassat et al. 1999) in the form of rapidly increasing crust growth. This growth has been brought about by a rapidly increasing rate of gas entrapment within the crust. It has been conceived that the lack of crust agitation beginning upon the advent of mixer pump operations may have set-up a more consolidated, gas impermeable barrier when compared to a crust regularly broken up by the prior buoyant displacement events within the tank. As a result, a series of level-growth remediation activities have been developed for tank 241-SY-101. The initial activities are also known as near-term crust mitigation. The first activity of near-term mitigation is to perform the small transfer of convective waste from tank 241-SY-101 into tank 241-SY-102. A 100 kgal transfer represents about a 10% volume reduction allowing a 10% water in-tank dilution. Current thinking holds that this should be enough to dissolve nitrite solids in the crust and perhaps largely eliminate gas retention problem in the crust (Raymond 1999). Additional mitigation activities are also planned on less constrained schedules. The net affect of the small transfer and follow-on mitigation activities for tank 241-SY-101 is strongly believed to be the remediation of tank 241-SY-101 as a flammable gas safety concern. The process for remediating the tank will require two or more transfer/dilution cycles. In-tank dilution will begin shortly after the initial transfer and the total dilution required to reach the final state is estimated to be between 250 to 400K gallons. The final state of the waste will not require any active measures to safely store the waste and operation of the mixer pump will no longer be necessary. The remediation activities are centered on a purpose

ORNL Remedial Action Program strategy (FY 1987-FY 1992)

International Nuclear Information System (INIS)

Trabalka, J.R.; Myrick, T.E.

1987-12-01

Over 40 years of Oak Ridge National Laboratory (ORNL) operations have produced a diverse legacy of contaminated inactive facilities, research areas, and waste disposal areas that are potential candidates for remedial action. The ORNL Remedial Action Program (RAP) represents a comprehensive effort to meet new regulatory requirements and ensure adequate protection of on-site workers, the public, and the environment by providing appropriate corrective measures at over 130 sites contaminated historically with radioactive, hazardous chemical, or mixed wastes. A structured path of program planning, site characterization, alternatives assessment, technology development, engineering design, continued site maintenance and surveillance, interim corrective action, and eventual site closure or decommissioning is required to meet these objectives. This report documents the development of the Remedial Action Program, through its preliminary characterization, regulatory interface, and strategy development activities. It provides recommendations for a comprehensive, long-term strategy consistent with existing technical, institutional, and regulatory information, along with a six-year plan for achieving its initial objectives. 53 refs., 8 figs., 12 tabs

Hydrocarbon impacts and remedial action at an active service station

Energy Technology Data Exchange (ETDEWEB)

Haidar, S.A. [Keystone Environmental, Burnaby, BC (Canada); Linke, J. [Chevron Canada Ltd., Vancouver, BC (Canada)

2006-07-01

This presentation discussed a project that examined the hydrocarbon impacts and remedial action at an active service station. The presentation identified the project partners, discussed the background on the project and project goals. Chevron Canada was the site involved in the study and Keystone Environmental was responsible for testing soil samples, developing the detailed conceptual site model, and for conducting indoor air quality monitoring. The presentation also provided illustrations of the site layout, investigated areas, and soil and groundwater plume. The evaluation and selection of remedial options were also discussed as well as other project planning activities such as assembling the project team, obtaining agreement with stakeholders, and coordinating with the municipality, utility companies, residents, and neighbours. Remediation efforts that were described and illustrated in the presentation included: underpinning and shoring; excavation; and, barrier wall installation. Last, post remediation activities were identified including the installation of post remediation confirmatory wells; reinstating structures; reinstating rear yards, fences, and garages; reconnecting utilities; performance monitoring of barrier wall; and, preparing closure reports for certificates of compliance on off-site properties. 6 figs.

Salmon Site Remedial Investigation Report, Appendix C

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Exhibit 2

Energy Technology Data Exchange (ETDEWEB)

USDOE NV

1999-09-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Appendix D

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remediation Investigation Report, Appendix A

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Main Body

Energy Technology Data Exchange (ETDEWEB)

US DOE/NV

1999-09-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Exhibit 2

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Appendix C

Energy Technology Data Exchange (ETDEWEB)

US DOE/NV

1999-09-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Exhibit 5

Energy Technology Data Exchange (ETDEWEB)

USDOE/NV

1999-09-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Exhibit 5

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Summary Report of Laboratory Testing to Establish the Effectiveness of Proposed Treatment Methods for Unremediated and Remediated Nitrate Salt Waste Streams

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-05-12

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report documents the effectiveness of two treatment methods proposed to stabilize both the unremediated and remediated nitrate salt waste streams (UNS and RNS, respectively). The two technologies include the addition of zeolite (with and without the addition of water as a processing aid) and cementation. Surrogates were developed to evaluate both the solid and liquid fractions expected from parent waste containers, and both the solid and liquid fractions were tested. Both technologies are shown to be effective at eliminating the characteristic of ignitability (D001), and the addition of zeolite was determined to be effective at eliminating corrosivity (D002), with the preferred option1 of zeolite addition currently planned for implementation at the Waste Characterization, Reduction, and Repackaging Facility. During the course of this work, we established the need to evaluate and demonstrate the effectiveness of the proposed remedy for debris material, if required. The evaluation determined that Wypalls absorbed with saturated nitrate salt solutions exhibit the ignitability characteristic (all other expected debris is not classified as ignitable). Follow-on studies will be developed to demonstrate the effectiveness of stabilization for ignitable Wypall debris. Finally, liquid surrogates containing saturated nitrate salts did not exhibit the characteristic of ignitability in their pure form (those neutralized with Kolorsafe and mixed with sWheat did exhibit D001). As a result, additional nitrate salt solutions (those exhibiting the oxidizer characteristic) will be tested to demonstrate the effectiveness of the remedy.

Office of Technology Development integrated program for development of in situ remediation technologies

International Nuclear Information System (INIS)

Peterson, M.

1992-08-01

The Department of Energy's Office of Technology Development has instituted an integrated program focused on development of in situ remediation technologies. The development of in situ remediation technologies will focus on five problem groups: buried waste, contaminated soils, contaminated groundwater, containerized wastes and underground detonation sites. The contaminants that will be included in the development program are volatile and non volatile organics, radionuclides, inorganics and highly explosive materials as well as mixtures of these contaminants. The In Situ Remediation Integrated Program (ISR IP) has defined the fiscal year 1993 research and development technology areas for focusing activities, and they are described in this paper. These R ampersand D topical areas include: nonbiological in situ treatment, in situ bioremediation, electrokinetics, and in situ containment

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

Energy Technology Data Exchange (ETDEWEB)

Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

2012-02-26

The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. DOE must continue to maintain constructive relationships with the U

MGP site remediation: Working toward presumptive remedies

International Nuclear Information System (INIS)

Larsen, B.R.

1996-01-01

Manufactured Gas Plants (MGPs) were prevalent in the United States during the 19th and first half of the 20th centuries. MGPs produced large quantities of waste by-products, which varied depending on the process used to manufacture the gas, but most commonly were tars and polynuclear aromatic hydrocarbons. There are an estimated 3,000 to 5,000 abandoned MGP sites across the United States. Because these sites are not concentrated in one geographic location and at least three different manufacturing processes were used, the waste characteristics are very heterogeneous. The question of site remediation becomes how to implement a cost-effective remediation with the variety of cleanup technologies available for these sites. Because of the significant expenditure required for characterization and cleanup of MGP sites, owners and regulatory agencies are beginning to look at standardizing cleanup technologies for these sites. This paper discusses applicable cleanup technologies and the attitude of state regulatory agencies towards the use of presumptive remedies, which can reduce the amount of characterization and detailed analysis necessary for any particular site. Additionally, this paper outlines the process of screening and evaluating candidate technologies, and the progress being made to match the technology to the site

Superfund record of decision (EPA Region 4): Whitehouse Waste Oil Pits Site, Duval County, Jacksonville, FL. (First remedial action), (Amendment), June 1992. Final report

International Nuclear Information System (INIS)

1992-01-01

The 7-acre Whitehouse Waste Oil Pits site was used by Allied Petroleum Products (Allied) to dispose of acidic waste oil sludges from its oil reclamation process in Whitehouse, Duval County, Florida. A cypress swamp system and residential area are immediately adjacent to the site. The acid sludge produced in the first step and clay used to decolorize the oil were dumped into the unlined pits at the site. A 1985 ROD addressed source control as a containment remedy consisting of a slurry wall construction, soil cap, and a ground water recovery and treatment system; however, EPA has re-evaluated the 1985 ROD selection and determined that the containment remedy failed to meet the requirements of SARA. As a result, the ROD Amendment focuses on an alternative for treating Whitehouse wastes by eliminating direct contact risk associated with pit soil/sludge wastes and preventing contaminated ground water in the surficial aquifer from migrating laterally. The primary contaminants of concern that affect the soil, sediment, surface water, and ground water are VOCs, including benzene, toluene, and xylenes; organics, including PCBs and phenols; and metals, including arsenic, chromium, and lead. The amended remedial action for the site are included

Tank waste remediation system functions and requirements document

Energy Technology Data Exchange (ETDEWEB)

Carpenter, K.E

1996-10-03

This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle.

Tank waste remediation system functions and requirements document

International Nuclear Information System (INIS)

Carpenter, K.E

1996-01-01

This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle

Laboratory/industry partnerships for environmental remediation

International Nuclear Information System (INIS)

Beskid, N.J.; Zussman, S.K.

1994-01-01

There are two measures of ''successful'' technology transfer in DOE's environmental restoration and waste management program. The first is remediation of DOE sites, and the second is commercialization of an environmental remediation process or product. The ideal case merges these two in laboratory/industry partnerships for environmental remediation. The elements to be discussed in terms of their effectiveness in aiding technology transfer include: a decision-making champion; timely and sufficient funding; well organized technology transfer function; well defined DOE and commercial markets; and industry/commercial partnering. Several case studies are presented, including the successful commercialization of a process for vitrification of low-level radioactive waste, the commercial marketing of software for hazardous waste characterization, and the application of a monitoring technique that has won a prestigious technical award. Case studies will include: vitrification of low-level radioactive waste (GTS Duratek, Columbia, MD); borehole liner for emplacing instrumentation and sampling groundwater (Science and Engineering Associates, Inc., Santa Fe, NM); electronic cone penetrometer (Applied Research Associates, Inc., South Royalton, VT); and software for hazardous waste monitoring ConSolve, Inc. (Lexington, MA). The roles of the Department of Energy and Argonne National Laboratory in these successes will be characterized

Bench scale experiments for the remediation of Hanford Waste Treatment Plant low activity waste melter off-gas condensate

Energy Technology Data Exchange (ETDEWEB)

Taylor-Pashow, Kathryn M.L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Poirier, Michael [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-08-11

The Low Activity Waste (LAW) vitrification facility at the Hanford Waste Treatment and Immobilization Plant (WTP) will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The plan for disposition of this stream during baseline operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. The primary reason to recycle this stream is so that the semi-volatile 99Tc isotope eventually becomes incorporated into the glass. This stream also contains non-radioactive salt components that are problematic in the melter, so diversion of this stream to another process would eliminate recycling of these salts and would enable simplified operation of the LAW melter and the Pretreatment Facilities. This diversion from recycling this stream within WTP would have the effect of decreasing the LAW vitrification mission duration and quantity of glass waste. The concept being tested here involves removing the ⁹⁹Tc so that the decontaminated aqueous stream, with the problematic salts, can be disposed elsewhere.

Waste management 86. Volume 1:General interest

International Nuclear Information System (INIS)

Post, R.G.

1986-01-01

This book presents the papers given at a symposium on radioactive waste management. Topics considered at the symposium included the status of radioactive waste disposal, the status of international nuclear waste management, waste management activities at the Idaho National Engineering Laboratory, legal and liability issues, risk perceptions and public involvement, waste transportation, waste processing, remedial action, decontamination, predisposal processing and treatment processes, low-level and mixed waste management, and mixed chemical and radioactive waste disposal

Recent developments in the DOE Waste Minimization Pollution Prevention Program

International Nuclear Information System (INIS)

Hancock, J.K.

1993-01-01

The U.S. Department of Energy (DOE) is involved in a wide variety of research and development, remediation, and production activities at more than 100 sites throughout the United States. The wastes generated cover a diverse spectrum of sanitary, hazardous, and radioactive waste streams, including typical office environments, power generation facilities, laboratories, remediation sites, production facilities, and defense facilities. The DOE's initial waste minimization activities pre-date the Pollution Prevention Act of 1990 and focused on the defense program. Little emphasis was placed on nonproduction activities. In 1991 the Office of Waste Management Operations developed the Waste Minimization Division with the intention of coordinating and expanding the waste minimization pollution prevention approach to the entire complex. The diverse nature of DOE activities has led to several unique problems in addressing the needs of waste minimization and pollution prevention. The first problem is developing a program that addresses the geographical and institutional hurdles that exist; the second is developing a monitoring and reporting mechanism that one can use to assess the overall performance of the program

Remedial investigation report on waste area grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 4, Appendix C, Risk assessment

International Nuclear Information System (INIS)

1995-09-01

Waste Area Grouping (WAG) 5 is part of Oak Ridge National Laboratory (ORNL) and is located on the United States Department of Energy's Oak Ridge Reservation (DOE-ORR). The site lies southeast of Haw Ridge in Melton Valley and comprises approximately 32 ha (80 ac) [12 ha (30 ac) of forested area and the balance in grassed fields]. Waste Area Grouping 5 consists of several contaminant source areas for the disposal of low-level radioactive, transuranic (TRU), and fissile wastes (1959 to 1973) as well as inorganic and organic chemical wastes. Wastes were buried in trenches and auger holes. Radionuclides from buried wastes are being transported by shallow groundwater to Melton Branch and White Oak Creek. Different chemicals of potential concern (COPCs) were identified (e.g., cesium-137, strontium-90, radium-226, thorium-228, etc.); other constituents and chemicals, such as vinyl chloride, bis(2-ethylhexyl)phthalate, trichloroethene, were also identified as COPCs. Based on the results of this assessment contaminants of concern (COCs) were subsequently identified. The objectives of the WAG 5 Baseline Human Health Risk Assessment (BHHRA) are to document the potential health hazards (i.e., risks) that may result from contaminants on or released from the site and provide information necessary for reaching informed remedial decisions. As part of the DOE-Oak Ridge Operations (ORO), ORNL and its associated waste/contamination sites fall under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), also known as Superfund under the Superfund Amendments and Reauthorization Act (SARA). The results of the BHHRA will (1) document and evaluate risks to human health, (2) help determine the need for remedial action, (3) determine chemical concentrations protective of current and future human receptors, and (4) help select and compare various remedial alternatives.

Development of the remedial action priority system: An improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

International Nuclear Information System (INIS)

Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

1985-01-01

The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to power significant problems to human health, safety and/or the environment. The HRS is used by the U.S. EPA to identify sites for nomination to the National Priorities List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the U.S. Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. To provide DOE with a better management tool for prioritizing funding and human resource allocations for further investigations and possible remediations at its inactive waste sites, PNL is developing the risk assessment methodology called RAPS. Use of RAPS will help DOE ensure that those sites posing the highest potential risk are addressed first

An overview of in situ waste treatment technologies

International Nuclear Information System (INIS)

Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

1992-01-01

In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified

Management assessment of tank waste remediation system contractor readiness to proceed with phase 1B privatization

International Nuclear Information System (INIS)

Honeyman, J.O.

1998-01-01

This Management Assessment of Tank Waste Remediation System (TWRS) Contractor Readiness to Proceed With Phase 1B Privatization documents the processes used to determine readiness to proceed with tank waste treatment technologies from private industry, now known as TWRS privatization. An overall systems approach was applied to develop action plans to support the retrieval and disposal mission of the TWRS Project. The systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed to ensure they exist when needed. Since October 1996 a robust system engineering approach to establishing integrated Technical Baselines, work breakdown structures, tank farms organizational structure and configurations, work scope, and costs has become part of the culture within the TWRS Project. An analysis of the programmatic, management, and technical activities necessary to declare readiness to proceed with execution of the mission demonstrates that the system, personnel, and hardware will be on-line and ready to support the private contractors. The systems approach included defining the retrieval and disposal mission requirements and evaluating the readiness of the Project Hanford Management Contract (PHMC) team to support initiation of waste processing by the private contractors in June 2002 and to receive immobilized waste shortly thereafter. The Phase 1 feed delivery requirements from the private contractor Requests for Proposal were reviewed. Transfer piping routes were mapped, existing systems were evaluated, and upgrade requirements were defined

Environmental Restoration Disposal Facility waste acceptance criteria. Revision 1

International Nuclear Information System (INIS)

Corriveau, C.E.

1996-01-01

The Environmental Restoration Disposal Facility (ERDF) is designed to be an isolation structure for low-level radioactive remediation waste, chemically contaminated remediation waste, and remediation waste that contains both chemical and radioactive constituents (i.e., mixed remediation waste) produced during environmental remediation of Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) past-practice units at the Hanford Site. Remedial action wastes, which will become a structural component of the ERDF, include bulk soil, demolition debris, and miscellaneous wastes from burial grounds. These wastes may originate from CERCLA past-practice sites (i.e., operable units) in the 100 Areas, the 200 Areas, and the 300 Area of the Hanford Site

Temporary septic holding tank at the 100-C remedial action support facility -- Engineering report

International Nuclear Information System (INIS)

Jackson, G.J.

1996-08-01

The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemically hazardous constituents. Investigation and remediation of these waste sites is governed by the Tri-Party Agreement. The agreement grouped the waste sites into 78 operable units, each of which was to be investigated and remediated separately. The 100 C Remedial Action Support Facility will be required near the 105-C Reactor to support the 105-C Interim Storage Project. This project is part of the decommissioning of the eight surplus reactor buildings along the Columbia River in the 100 Area. This facility, will be a temporary, modular building sized to provide office and work space for the supervisors, engineers, and technicians assigned to the project and engaged in the associated field work. This report describes the project location, geology and potential flooding, design criteria, operations, and maintenance

Advanced remediation, technology development in the underground storage tank

International Nuclear Information System (INIS)

Gates, T.E.; Gilchrist, R.L.

1992-01-01

Production of nuclear materials has been a major mission of the U. S. Department of Energy (DOE) over the last 50 years. These activities have contributed to a substantial accumulation of hazardous, radioactive, and mixed wastes. In 1989, the DOE established the Office of Environmental Restoration and Waste Management. This office coordinates and manages the DOE's remediation, waste minimization, and environmental compliance activities. It also has responsibility for waste generated by current operations. Within this office is the Office of Technology Development, which is responsible for providing technology improvements. This paper reports on integrated demonstrations which have been established to efficiently bring the best technologies to bear on the common needs of multiple DOE sites. One such need is resolution of the actions required for final closure and waste disposal of liquid (including sludge and salt cake) radioactive and chemical wastes that have been transferred to underground storage tanks

Data Base Management Plan for the remedial investigation of Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1992-07-01

The remedial investigation (RI) for Waste Area Grouping (WAG) 5 will involve gathering, verifying, analyzing, reporting, and archiving numerous types of field and analytical data. Field investigations will produce data documenting surficial and geophysical surveys, geologic and hydrogeologic logs, aquifer tests, water level measurements, geophysical logs, and stream and seepage flow measurements. Laboratory analyses will be performed on soil, surface water, groundwater, and sediment samples collected during field investigations. All data resulting from these activities will be contained in the Bechtel RI/feasibility study (FS) project data base and will be managed in accordance with the RI/FS Data Base Management Plan and this WAG-specific plan. This Data Base Management Plan describes the gathering, verifying, analyzing, reporting, and archiving of data generated during Bechtel's remedial investigation of Waste Area Grouping 5. This investigation will produce data documenting surficial surveys, geophysical surveys, geologic and hydrologic logs, aquifer tests, water level measurements, geophysical logs, and stream and seep flow measurements. Also, laboratory analyses will be performed on soil, surface water, groundwater, and sediment samples. The 1500 series of Bechtel project procedures, ''Data Base Management,'' and the project Data Base Management Plan will be used to ensure that data are handled properly

Green remediation and recycling of contaminated sediment by waste-incorporated stabilization/solidification.

Science.gov (United States)

Wang, Lei; Tsang, Daniel C W; Poon, Chi-Sun

2015-03-01

Navigational/environmental dredging of contaminated sediment conventionally requires contained marine disposal and continuous monitoring. This study proposed a green remediation approach to treat and recycle the contaminated sediment by means of stabilization/solidification enhanced by the addition of selected solid wastes. With an increasing amount of contaminated sediment (20-70%), the 28-d compressive strength of sediment blocks decreased from greater than 10MPa to slightly above 1MPa. For augmenting the cement hydration, coal fly ash was more effective than lime and ground seashells, especially at low sediment content. The microscopic and spectroscopic analyses showed varying amounts of hydration products (primarily calcium hydroxide and calcium silicate hydrate) in the presence of coal fly ash, signifying the influence of pozzolanic reaction. To facilitate the waste utilization, cullet from beverage glass bottles and bottom ashes from coal combustion and waste incineration were found suitable to substitute coarse aggregate at 33% replacement ratio, beyond which the compressive strength decreased accordingly. The mercury intrusion porosimetry analysis indicated that the increase in the total pore area and average pore diameter were linearly correlated with the decrease of compressive strength due to waste replacement. All the sediment blocks complied with the acceptance criteria for reuse in terms of metal leachability. These results suggest that, with an appropriate mixture design, contaminated sediment and waste materials are useful resources for producing non-load-bearing masonry units or fill materials for construction uses. Copyright © 2014 Elsevier Ltd. All rights reserved.

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

Decision support tools for evaluation and selection of technologies for soil remediation and disposal of halogenated waste

Energy Technology Data Exchange (ETDEWEB)

Khelifi, O.; Zinovyev, S.; Lodolo, A.; Vranes, S.; Miertus, S. [ICS-UNIDO, Trieste (Italy)

2004-09-15

One of the most justified demands in abating the pollution created by polychlorinated substances is the remediation of contaminated sites, mainly soil remediation, which is also the most complex technical task in removing pollution because of the necessity to process huge quantities of matrix and to account for numerous side factors. The commercial technologies are usually based on rather direct and simplified but also secure processes, which often approach remediation in a general way, where different types of pollutants can be decontaminated at the same time by each technology. A number of different soil remediation technologies are nowadays available and the continuous competition among environmental service companies and technology developers generates a further increase in the clean-up options. The demand for decision support tools that could help decision makers in selecting the most appropriate technology for the specific contaminated site has consequently increased. These decision support tools (DST) are designed to help decision makers (site owners, local community representatives, environmentalists, regulators, etc.) to assess available technologies and preliminarily select the preferred remedial options. The analysis for the identification of the most suitable options in the DST is based on technical, economic, environmental, and social criteria. These criteria are ranked by all parties involved in the decision process to determine their relative importance for a particular remediation project. The aim of the present paper is to present the new approach for building decision support tool to evaluate different technologies for remediation and disposal of halogenated waste.

Disposal Notifications and Quarterly Membership Updates for the Utility Solid Waste Group Members’ Risk-Based Approvals to Dispose of PCB Remediation Waste Under Title 40 of the Code of Federal Regulations Section 761.61(c)

Science.gov (United States)

Disposal Notifications and Quarterly Membership Updates for the Utility Solid Waste Group Members’ Risk-Based Approvals to Dispose of Polychlorinated Biphenyl (PCB) Remediation Waste Under Title 40 of the Code of Federal Regulations Section 761.61(c)

ICDF Complex Remedial Action Work Plan

Energy Technology Data Exchange (ETDEWEB)

W. M. Heileson

2006-12-01

This Remedial Action Work Plan provides the framework for operation of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility Complex (ICDF). This facility includes (a) an engineered landfill that meets the substantial requirements of DOE Order 435.1, Resource Conservation and Recovery Act Subtitle C, Idaho Hazardous Waste Management Act, and Toxic Substances Control Act polychlorinated biphenyl landfill requirements; (b) centralized receiving, inspections, administration, storage/staging, and treatment facilities necessary for CERCLA investigation-derived, remedial, and removal waste at the Idaho National Laboratory (INL) prior to final disposition in the disposal facility or shipment off-Site; and (c) an evaporation pond that has been designated as a corrective action management unit. The ICDF Complex, including a buffer zone, will cover approximately 40 acres, with a landfill disposal capacity of approximately 510,000 yd3. The ICDF Complex is designed and authorized to accept INL CERCLA-generated wastes, and includes the necessary subsystems and support facilities to provide a complete waste management system. This Remedial Action Work Plan presents the operational approach and requirements for the various components that are part of the ICDF Complex. Summaries of the remedial action work elements are presented herein, with supporting information and documents provided as appendixes to this work plan that contain specific detail about the operation of the ICDF Complex. This document presents the planned operational process based upon an evaluation of the remedial action requirements set forth in the Operable Unit 3-13 Final Record of Decision.

Bio-remediation in actual use and environmental impairment liability insurance. Bio remediation no jissai to kankyo hoken

Energy Technology Data Exchange (ETDEWEB)

Ooka, K [AIU Insurance Company, Tokyo (Japan)

1993-08-01

This paper introduces the American International Group (AIG) which makes conceptions and risks of bio-remediation its business, as to how the Group is really working on the business. Features of the continuing remediation involving corporations managed by AIG include the following: It has economical superiority; in-situ purification of contaminated soils is possible; and it can solve contamination issues in a short time, and makes reuse of lands possible. The remediation uses a principle of promoting the contamination purifying actions of the natural world. It activates microorganisms by supplying oxygen, water, and nutrients in suitable amounts for microbial activities to decompose chemical wastes and converts them into harmless substances such as CO2. Objects of purification include petroleum-based substances, herbicides, insecticides, and solvents. Establishing optimal parameters before purification (mediator variables and population parameters) and protocols is important. The system goes through the following steps: Hydraulic and geological experts identify patterns and levels of contamination; microorganism experts find optimal parameters in laboratories; engineers design treatment systems; and site technicians operate the system. 6 refs., 3 figs.

ORNL nuclear waste programs annual progress report for period ending September 30, 1982

International Nuclear Information System (INIS)

1983-05-01

Research progress is reported in 20 activities under the headings: spent fuels, defense waste management, commercial waste management, remedial action, and conventional reactors. Separate entries were prepared for each activity

Remediation of radiocesium-contaminated liquid waste, soil, and ash: a mini review since the Fukushima Daiichi Nuclear Power Plant accident.

Science.gov (United States)

Ding, Dahu; Zhang, Zhenya; Lei, Zhongfang; Yang, Yingnan; Cai, Tianming

2016-02-01

The radiation contamination after the Fukushima Daiichi Nuclear Power Plant accident attracts considerable concern all over the world. Many countries, areas, and oceans are greatly affected by the emergency situation other than Japan. An effective remediation strategy is in a highly urgent demand. Though plenty of works have been carried out, progressive achievements have not yet been well summarized. Here, we review the recent advances on the remediation of radiocesium-contaminated liquid waste, soil, and ash. The overview of the radiation contamination is firstly given. Afterwards, the current remediation strategies are critically reviewed in terms of the environmental medium. Special attentions are paid on the adsorption/ion exchange and electrically switched ion exchange methods. Finally, the present review outlines the possible works to do for the large-scale application of the novel remediation strategies.

Buried waste integrated demonstration fiscal year 1992 close-out report

International Nuclear Information System (INIS)

Cannon, P.G.; Kostelnik, K.M.; Owens, K.J.

1993-02-01

The mission of the Buried Waste Integrated Demonstration Program (BWID) is to support the development and demonstration of a suite of technologies that when integrated with commercially-available baseline technologies form a comprehensive remediation system for the effective and efficient remediation of buried waste disposed of throughout the US Department of Energy complex. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Office of Technology Development initiated the BWID at the Idaho National Engineering Laboratory in fiscal year (FY)-91. This report summarizes the activities of the BWID Program during FY-92

2013 Los Alamos National Laboratory Hazardous Waste Minimization Report

Energy Technology Data Exchange (ETDEWEB)

Salzman, Sonja L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); English, Charles J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-08-24

Waste minimization and pollution prevention are inherent goals within the operating procedures of Los Alamos National Security, LLC (LANS). The US Department of Energy (DOE) and LANS are required to submit an annual hazardous waste minimization report to the New Mexico Environment Department (NMED) in accordance with the Los Alamos National Laboratory (LANL or the Laboratory) Hazardous Waste Facility Permit. The report was prepared pursuant to the requirements of Section 2.9 of the LANL Hazardous Waste Facility Permit. This report describes the hazardous waste minimization program (a component of the overall Waste Minimization/Pollution Prevention [WMin/PP] Program) administered by the Environmental Stewardship Group (ENV-ES). This report also supports the waste minimization and pollution prevention goals of the Environmental Programs Directorate (EP) organizations that are responsible for implementing remediation activities and describes its programs to incorporate waste reduction practices into remediation activities and procedures. LANS was very successful in fiscal year (FY) 2013 (October 1-September 30) in WMin/PP efforts. Staff funded four projects specifically related to reduction of waste with hazardous constituents, and LANS won four national awards for pollution prevention efforts from the National Nuclear Security Administration (NNSA). In FY13, there was no hazardous, mixedtransuranic (MTRU), or mixed low-level (MLLW) remediation waste generated at the Laboratory. More hazardous waste, MTRU waste, and MLLW was generated in FY13 than in FY12, and the majority of the increase was related to MTRU processing or lab cleanouts. These accomplishments and analysis of the waste streams are discussed in much more detail within this report.

Control of a long reach manipulator with suspension cables for waste storage tank remediation. Final report

International Nuclear Information System (INIS)

Wang, S.L.

1994-01-01

A long reach manipulator will be used for waste remediation in large underground storage tanks. The manipulator's slenderness makes it flexible and difficult to control. A low-cost and effective method to enhance the manipulator's stiffness is proposed in this research by using suspension cables. These cables can also be used to accurately measure the position of the manipulator's wrist

The sonophysics and sonochemistry of liquid waste quantification and remediation. 1998 annual progress report

International Nuclear Information System (INIS)

Matula, T.J.

1998-01-01

'To perform an in-depth and comprehensive study of the fundamentals of acoustic cavitation and nonlinear bubble dynamics, to elucidate the fundamental physics of sonochemical reactions, to examine the potential of sonoluminescence to quantify and to monitor the presence of alkali metals and other elements in waste liquids, to design and to evaluate more effective sonochemical reactors for waste remediation, and to determine the optimal acoustical parameters in the use of sonochemistry for liquid-waste-contaminant remediation. This report summarizes work performed during year 2 of a 3-year project. The goals included performing near-IR spectroscopy of sonoluminescence. Cells have been designed for multi-bubble sonoluminescence (MBSL) and single-bubble sonoluminescence (SBSL) spectroscopy experiments. The MBSL cells are designed around a 20 kHz acoustic horn with replaceable titanium tips from Sonics and Materials. The horn is pressure-fitted into a stainless steel cell via O-rings and a compression ring, to seal the cell up to 100 psi for pressure experiments. The cell is thermostated by circulating coolant in a jacket, as well as flowing the cell fluid (at 4L/min.) through a temperature control bath. Several ports are located on the cell for gas ports (one for headspace, another for bubbling), a pressure transducer, a thermocouple, a needle hydrophone, and a septum port for addition or withdrawal of samples. The total volume is approximately 80 mL with a 10 mL head space. Directly opposite the horn tip is a 2 cm quartz window against which a fiber optic bundle is placed. Light collected through the fiber optic is imaged onto one of several detection systems.'

Engineered Option Treatment of Remediated Nitrate Salts: Surrogate Batch-Blending Testing

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-11

This report provides results from batch-blending test work for remediated nitrate salt (RNS) treatment. Batch blending was identified as a preferred option for blending RNS and unremediated nitrate salt (UNS) material with zeolite to effectively safe the salt/Swheat material identified as ignitable (U.S. Environmental Protection Agency code D001). Blending with zeolite was the preferred remediation option identified in the Options Assessment Report and was originally proposed as the best option for remediation by Clark and Funk in their report, Chemical Reactivity and Recommended Remediation Strategy for Los Alamos Remediated Nitrate Salt (RNS) Wastes, and also found to be a preferred option in the Engineering Options Assessment Report: Nitrate Salt Waste Stream Processing. This test work evaluated equipment and recipe alternatives to achieve effective blending of surrogate waste with zeolite.

Minutes from Department of Energy/Hazardous Waste Remedial Actions Program, research and development technology needs assessment review meeting for FY 1990, September 1989, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1990-08-01

On September 20--21, 1989, representatives of the Department of Energy (DOE) Headquarters, DOE Operations Offices, DOE contractors, and the Hazardous Waste Remedial Actions Program met in Oak Ridge, Tennessee, to select and prioritize candidate waste problems in need of research and development. The information gained will be used in planning for future research and development tasks and in restructuring current research activities to address the priority needs. Consistent with the ongoing reevaluation of DOE's plans for environmental restoration and waste management, an attempt was made to relate the needs developed in this meeting to the needs expressed in the draft Applied Research, Development, Demonstration, Testing, and Evaluation Plan. Operations Offices were represented either by DOE staff or by contractor delegates from the area. This document summarizes the results of the meeting and lists the priority waste problems established.

Environmental restoration and remediation technical data management plan

International Nuclear Information System (INIS)

Key, K.T.; Fox, R.D.

1994-02-01

The tasks performed in the Remedial Investigation/Feasibility Study (RI/FS) work plan for each Hanford Site operable unit must meet the requirements of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al 1992). An extensive amount of data will be generated in the evaluation and remediation of hazardous waste sites at the Site. The data must be of sufficient quality, as they will be used to evaluate the need, select the method(s), and support the full remediation of the waste sites as stipulated in the Tri-Party Agreement. In particular, a data management plan (DMP) is to be included in an RI/FS work plan for managing the technical data obtained during the characterization of an operable unit, as well as other data related to the study of the operable unit. Resource Conservation and Recovery Act of 1976 (RCRA) sites are involved in the operable unit. Thus, the data management activities for the operable unit should be applied consistently to RCRA sites in the operable unit as well. This DMP provides common direction for managing-the environmental technical data of all defined operable units at the Hanford Site during the RI/FS activities. Details specific to an operable unit will be included in the actual work plan of that operable unit

Characterization and Potential Use of Biochar for the Remediation of Coal Mine Waste Containing Efflorescent Salts

Directory of Open Access Journals (Sweden)

Luis Carlos Díaz Muegue

2017-11-01

Full Text Available In open pit coal mining, soil and vegetation are removed prior to the start of mining activities, causing physical, chemical, and microbiological changes to the soil and landscape. The present work shows the results of an integrated study of the remediation of mine waste with a high level of salt contamination in areas of the Cesar Department (Colombia, employing biochar as an amendment. Physical-chemical properties including Munsell color, texture, pH, electrical conductivity, water-holding capacity, cation exchange capacity, metal content, organic carbon, sulfates, extractable P, and total nitrogen were characterized both in the soils contaminated with mine residues and the biochar sample. A high concentration of sulfates, calcium, iron, and aluminum and a significant presence of Na, followed by minor amounts of Mg, K, Cu, and Mn, were observed in efflorescent salts. X-ray diffraction indicated a high presence of quartz and gypsum and the absence of pyrite and Schwertmannite in the efflorescent salt, while showing broad peaks belonging to graphene sheets in the biochar sample. Soil remediation was evaluated in Petri dish seed germination bioassays using Brachiaria decumbens. Biochar was shown to be effective in the improvement of pH, and positively influenced the germination percentage and root length of Brachiaria grass seeds.

Double-shell tank waste system assessment status and schedule

International Nuclear Information System (INIS)

Walter, E.J.

1995-01-01

The integrated program for completing the integrity assessments of the dangerous waste tank systems managed by the Tank Waste Remediation System (TWRS) Division of Westinghouse Hanford Company is presented in the Tank Waste Remediation System Tank System Integrity Assessments Program Plan, WHC-SD-AP017, Rev. 1. The program plan identified the assessment requirements and the general scope to which these requirements applied. Some of these assessment requirements have been met and others are either in process of completion or scheduled to be worked. To define the boundary of the double-shell tank (DST) system and the boundaries of the DST system components (or system parts) for the purpose of performing integrity assessment activities; To identify the planned activities to meet the assessment requirements for each component; Provide the status of the assessment activities; and Project a five year assessment activity schedule

Environmental remediation of the Wismut legacy and utilization of the reclaimed areas, waste rock piles and tailings ponds

International Nuclear Information System (INIS)

Hagen, M.; Jakubick, A.T.

2006-01-01

Between 1945 and reunification (1989) of Germany more than 232 000 t of U 3 O 8 has been produced in Saxony and Thuringia, East Germany. This affected an area of approximately 100 km 2 and left behind an extensive legacy of contaminated operations areas, underground and open pit mines, waste rock piles and tailings ponds. Following reunification, DM 13 billion (Euro 6.6 billion) were committed (and later revised to Euro 6.2 billion) to remediation of the liabilities and the government owned corporation, Wismut GmbH entrusted with the implementation of the Environmental Remediation (ER) of the liabilities. The prime goal of the ER Project follows from the legal requirements to abate health risks, mitigate existing and prevent future environmental damages. During the investigations and assessment of risks, development of remediation concepts, adoption of suitable technologies and work procedures as well as physical implementation of the remedial measures extensive use was made of international (mostly US and Canadian) ER experience. The extent of remedial measures was based on object-specific Environmental Assessments rather than on uniformly applied health/environmental standards. The ER workflow is more an iterative process than a linear succession of tasks, such as common for civil engineering projects. The internal (technical) parts of the problems were partly resolved by using Conceptual Site Models (CSM) for selection and prioritization of remedial measures. Reclamation of the waste rock piles is by covering in situ, relocation to a central pile or backfilling into an open pit. The backfilling of the open pit at Ronneburg with acid generating waste rock has been optimized from a geochemical point of view. For tailings ponds reclamation in form of dry landforms is being followed. To increase release (and reuse) of scrap metal from demolition, a fast and reliable method of discrimination of the non-contaminated metal has been developed. The flooding of

A remedial alternative prioritization method

International Nuclear Information System (INIS)

Richter, S.A.; Travis, C.C.

1987-01-01

This study develops and tests a technique for evaluating and prioritizing alternative remedial actions for hazardous waste sites. The method is based on criteria involving risk, benefit and cost, and identifies the most cost-effective solution to a given remedial problem. Four sites on the Department of Energy's Oak Ridge National Laboratory (ORNL) property in Oak Ridge, Tennessee, were used in a case study to develop and test the method. Results of the case study indicate that even if the cap providing in situ containment must be replaced every 10 years, it is a superior alternative to total excavation of the waste sites

Assessment of international remedial technologies for application to Superfund sites

International Nuclear Information System (INIS)

Sanning, D.E.

1990-01-01

This paper presents some of the logical arguments for conducting research on remedial technologies for contaminated land and groundwater at an international level. It gives information on many of the international organizations that are involved in environmental programs, but it especially gives emphasis to the NATO-CCMS pilot study on Demonstration of Remedial Action Technologies for Contaminated Land and Groundwater. The purpose of the study is to field demonstrate and evaluate new/innovative technologies for remedial action at uncontrolled hazardous waste sites. This study is a logical international extension of the US EPA SITE program. It offers the opportunity to obtain a multiple data base on various remedial action unit processes without any single country having to commit a disproportionate amount of its internal resources to any specific activity. Each participating country provides the necessary resources for those demonstrations which they are contributing to the study. Sites are selected by a majority vote of all participating countries (no country is permitted to vote for its own sites). The study is a 5 year program with participants from Canada, Denmark, Federal Republic of Germany, France, Greece, Italy, Japan, the Netherlands, Norway, Spain, and the US. The need for cost-effective remedial action technologies for hazardous waste sites is a problem of all industrialized countries. The need to build a knowledge base of emerging remedial technologies was the impetus behind the USEPA's lead role and commitment to this pilot study

Remediation of the Maxey Flats Site

International Nuclear Information System (INIS)

1990-01-01

This report describes issues associated with remedial action of Maxey Flats, a low-level radioactive waste disposal site from 1963-1977, located in Fleming County, Kentucky. Present remedial action alternatives being considered are discussed along with emergency plans, ground water monitoring plans, and budgets

Site characterization techniques used in environmental remediation activities

International Nuclear Information System (INIS)

Kostelnik, K.M.

2000-01-01

As a result of decades of nuclear energy research, weapons production, as well as ongoing operations, a significant amount of radioactive contamination has occurred throughout the United States Department of Energy (DOE) complex. DOE facility are in the process of assessing and potentially remediating various sites according to the regulations imposed by a Federal Facility Agreement and Consent order (FFA/CO) between DOE, the state in which the facility is located, and the U.S. Environmental Protection Agency (EPA). In support of these active site remediation efforts, the DOE has devoted considerable resources towards the development of innovative site characterization techniques that support environmental restoration activities. These resources and efforts have focused on various aspects of this complex problem. Research and technology development conducted at the Idaho National Engineering and Environmental Laboratory (INEEL) has resulted in the ability and state-of-the-art equipment required to obtain real-time, densely spaced, in situ characterization data (i.e. detection, speciation, and location) of various radionuclides and contaminants. The Remedial Action Monitoring System (RAMS), developed by the INEEL, consists of enhanced sensor technology, measurement modeling and interpretation techniques, and a suite of deployment platforms which can be interchanged to directly support remedial cleanup and site verification operations. In situ characterization techniques have advanced to the point where they are being actively deployed in support of remedial operations. The INEEL has deployed its system at various DOE and international sites. The deployment of in situ characterization systems during environmental restoration operations has shown that this approach results in several significant benefits versus conventional sampling techniques. A flexible characterization system permits rapid modification to satisfy physical site conditions, available site resources

Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3, Appendix B, Technical findings and conclusions

International Nuclear Information System (INIS)

1995-03-01

This Remedial Investigation Report on Waste Area Grouping, (NVAG) 5 at Oak Ridge National Laboratory was prepared in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for reporting, the results of a site chacterization for public review. This work was performed under Work Breakdown Structure 1.4.12.6.1.05.40.02 (Activity Data Sheet 3305, ''WAG 5''). Publication of this document meets a Federal Facility Agreement milestone of March 31, 1995. This document provides the Environmental Restoration Program with information about the results of investigations performed at WAG 5. It includes information on risk assessments that have evaluated long-term impacts to human health and the environment. Information provided in this document forms the basis for decisions regarding, the need for subsequent remediation work at WAG 5

Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3, Appendix B, Technical findings and conclusions

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

This Remedial Investigation Report on Waste Area Grouping, (NVAG) 5 at Oak Ridge National Laboratory was prepared in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for reporting, the results of a site chacterization for public review. This work was performed under Work Breakdown Structure 1.4.12.6.1.05.40.02 (Activity Data Sheet 3305, ``WAG 5``). Publication of this document meets a Federal Facility Agreement milestone of March 31, 1995. This document provides the Environmental Restoration Program with information about the results of investigations performed at WAG 5. It includes information on risk assessments that have evaluated long-term impacts to human health and the environment. Information provided in this document forms the basis for decisions regarding, the need for subsequent remediation work at WAG 5.

Immobilized low-activity waste site borehole 299-E17-21

International Nuclear Information System (INIS)

Reidel, S.P.; Reynolds, K.D.; Horton, D.G.

1998-08-01

The Tank Waste Remediation System (TWRS) is the group at the Hanford Site responsible for the safe underground storage of liquid waste from previous Hanford Site operations, the storage and disposal of immobilized tank waste, and closure of underground tanks. The current plan is to dispose of immobilized low-activity tank waste (ILAW) in new facilities in the southcentral part of 200-East Area and in four existing vaults along the east side of 200-East Area. Boreholes 299-E17-21, B8501, and B8502 were drilled at the southwest corner of the ILAW site in support of the Performance Assessment activities for the disposal options. This report summarizes the initial geologic findings, field tests conducted on those boreholes, and ongoing studies. One deep (480 feet) borehole and two shallow (50 feet) boreholes were drilled at the southwest corner of the ILAW site. The primary factor dictating the location of the boreholes was their characterization function with respect to developing the geohydrologic model for the site and satisfying associated Data Quality Objectives. The deep borehole was drilled to characterize subsurface conditions beneath the ILAW site, and two shallow boreholes were drilled to support an ongoing environmental tracer study. The tracer study will supply information to the Performance Assessment. All the boreholes provide data on the vadose zone and saturated zone in a previously uncharacterized area

Estimating air emissions from a remediation of a petroleum sump using direct measurement and modeling

International Nuclear Information System (INIS)

Schmidt, C.E.

1991-01-01

A technical approach was developed for the remediation of a petroleum sump near a residential neighborhood. The approach evolved around sludge handling/in-situ solidification and on-site disposal. As part of the development of the engineering approach, a field investigation and modeling program was conducted to predict air emissions from the proposed remediation. Field measurements using the EPA recommended surface isolation flux chamber were conducted to represent each major activity or air exposure involving waste at the site. Air emissions from freshly disturbed petroleum waste, along with engineering estimates were used to predict emissions from each phase of the engineering approach. This paper presents the remedial approach and the measurement/modeling technologies used to predict air toxic emissions from the remediation. Emphasis will be placed on the measurement approaches used in obtaining the emission rate data and the assumptions used in the modeling to estimate emissions from engineering scenarios

Configuration management plan for waste tank farms and the 242-A evaporator of tank waste remediation system

International Nuclear Information System (INIS)

Laney, T.

1994-01-01

The configuration management architecture presented in this Configuration Management Plan is based on the functional model established by DOE-STD-1073-93, ''Guide for Operational Configuration Management Program.'' The DOE Standard defines the configuration management program by the five basic program elements of ''program management,'' ''design requirements,'' ''document control,'' ''change control,'' and ''assessments,'' and the two adjunct recovery programs of ''design reconstitution,'' and ''material condition and aging management.'' The CM model of five elements and two adjunct programs strengthen the necessary technical and administrative control to establish and maintain a consistent technical relationship among the requirements, physical configuration, and documentation. Although the DOE Standard was originally developed for the operational phase of nuclear facilities, this plan has the flexibility to be adapted and applied to all life-cycle phases of both nuclear and non-nuclear facilities. The configuration management criteria presented in this plan endorses the DOE Standard and has been tailored specifically to address the technical relationship of requirements, physical configuration, and documentation during the full life cycle of the Waste Tank Farms and 242-A Evaporator of Tank Waste Remediation System

Case study of an approved corrective action integrating active remediation with intrinsic remediation

International Nuclear Information System (INIS)

Teets, D.B.; Guest, P.R.; Blicker, B.R.

1996-01-01

Parsons Engineering Science, Inc., performed UST removals and/or site assessments at UST system locations at a former US Air Force Base (AFB) in Denver, Colorado. Four UST systems, incorporating 17 USTs, were located within the petroleum, oils, and lubricants bulk storage yard (POL Yard) of the former AFB. During the tank removals and subsequent site investigations, petroleum hydrocarbon contamination was found in soils at each site. Significant releases from two of the UST systems resulted in a dissolved benzene, toluene, ethylbenzene, and xylenes (BTEX) plume in the groundwater, and smear-zone contamination of soils beneath the majority of the POL Yard. Because of the close proximity of the UST systems, and the presence of the groundwater plume beneath the POL Yard, a corrective action plan (CAP) was prepared that encompassed all four UST systems. An innovative, risk-based CAP integrated active remediation of petroleum-contaminated soils with intrinsic remediation of groundwater. A natural attenuation evaluation for the dissolved BTEX was performed to demonstrate that natural attenuation processes are providing adequate remediation of groundwater and to predict the fate of the groundwater plume. BTEX concentrations versus distance were regressed to obtain attenuation rates, which were then used to calculate BTEX degradation rates using a one-dimensional, steady-state analytical solution. Additionally, electron acceptor concentrations in groundwater were compared to BTEX concentrations to provide evidence that natural attenuation of BTEX compounds was occurring. The natural attenuation evaluation was used in the CAP to support the intrinsic remediation with long-term monitoring alternative for groundwater, thereby avoiding the installation of an expensive groundwater remediation system

Salmon Site Remedial Investigation Report, Appendix B (Part 2)

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Salmon Site Remedial Investigation Report, Appendix B (Part 1)

International Nuclear Information System (INIS)

1999-01-01

This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides into the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the

Nationwide Risk-Based PCB Remediation Waste Disposal Approvals under Title 40 of the Code of Federal Regulations (CFR) Section 761.61(c)

Science.gov (United States)

This page contains information about Nationwide Risk-Based Polychlorinated Biphenyls (PCBs) Remediation Waste Disposal Approvals under Title 40 of the Code of Federal Regulations (CFR) Section 761.61(c)

Hazardous Waste Remedial Actions Program requirements for quality control of analytical data

International Nuclear Information System (INIS)

Miller, M.S.; Zolyniak, J.W.

1988-08-01

The Hazardous Waste Remedial Action Program (HAZWRAP) is involved in performing field investigations and sample analysis pursuant to the NCP for the Department of Energy and other federal agencies. The purpose of this document is to specify the requirements for the control of the accuracy, precision and completeness of the samples, and data from the point of collection through analysis. The requirements include data reduction and reporting of the resulting environmentally related data. Because every instance and concern may not be addressed in this document, HAZWRAP subcontractors are encouraged to discuss any questions with the HAZWRAP Project Manager hereafter identified as the Project Manager

Remediation of a historically Pb contaminated soil using a model natural Mn oxide waste.

Science.gov (United States)

McCann, Clare M; Gray, Neil D; Tourney, Janette; Davenport, Russell J; Wade, Matthew; Finlay, Nina; Hudson-Edwards, Karen A; Johnson, Karen L

2015-11-01

A natural Mn oxide (NMO) waste was assessed as an in situ remediation amendment for Pb contaminated sites. The viability of this was investigated using a 10 month lysimeter trial, wherein a historically Pb contaminated soil was amended with a 10% by weight model NMO. The model NMO was found to have a large Pb adsorption capacity (qmax 346±14 mg g(-1)). However, due to the heterogeneous nature of the Pb contamination in the soils (3650.54-9299.79 mg kg(-1)), no treatment related difference in Pb via geochemistry could be detected. To overcome difficulties in traditional geochemical techniques due to pollutant heterogeneity we present a new method for unequivocally proving metal sorption to in situ remediation amendments. The method combines two spectroscopic techniques; namely electron probe microanalysis (EPMA) and X-ray photoelectron spectroscopy (XPS). Using this we showed Pb immobilisation on NMO, which were Pb free prior to their addition to the soils. Amendment of the soil with exogenous Mn oxide had no effect on microbial functioning, nor did it perturb the composition of the dominant phyla. We conclude that NMOs show excellent potential as remediation amendments. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

Waste feed delivery environmental permits and approvals plan

International Nuclear Information System (INIS)

Papp, I.G.

1998-01-01

This document describes the range of environmental actions, including required permits and other agency approvals, that may affect waste feed delivery (WFD) activities in the Hanford Site's Tank Waste Remediation System (TWRS). This plan expands on the summary level information in the Tank Waste Remediation System Environmental Program Plan (HNF 1773) to address requirements that are most pertinent to WFD. This plan outlines alternative approaches to satisfying applicable environmental standards, and describes selected strategies for acquiring permits and other approvals needed for WFD to proceed. Appendices at the end of this plan provide preliminary cost and schedule estimates for implementing the selected strategies. The rest of this section summarizes the scope of WFD activities, including important TWRS operating information, and describes in more detail the objectives, structure, and content of this plan

BACTERICIDAL COATINGS ON TEXTILES FOR REMEDIATION OF INTERMICROBE ACTIVITY (BaCTeRIA) SUMMARY REPORT

Science.gov (United States)

2017-07-07

TEXTILES FOR REMEDIATION OF INTERMICROBE ACTIVITY (BaCTeRIA) SUMMARY REPORT by Tobyn A. Branck Courtney M. Cowell Jennifer M. Rego and...October 2011 – September 2015 4. TITLE AND SUBTITLE BACTERICIDAL COATINGS ON TEXTILES FOR REMEDIATION OF INTERMICROBE ACTIVITY (BaCTeRIA) SUMMARY REPORT... REMEDIATION OF INTERMICROBE ACTIVITY (BaCTeRIA) SUMMARY REPORT Introduction The Biological Sciences and Technology Team (BSTT), Warfighter

Maximizing Operational Efficiencies in Waste Management on the Hanford Plateau Remediation Contract in a Down-turned Market - 13484

Energy Technology Data Exchange (ETDEWEB)

Simiele, Connie J.; Blackford, L. Ty [CH2M HILL Plateau Remediation Contract - CHPRC (United States); West, Lori D. [East Tennessee Materials and Energy Corporation - M and EC (United States)

2013-07-01

Recent changes in DOE priorities and funding have pressed DOE and its contractors to look for innovative methods to sustain critical operations at sites across the Complex. At the Hanford Site, DOE Richland Operations and its prime contractor, CH2M Hill Plateau Remediation Company (CHPRC), have completed in-depth assessments of the Plateau Remediation Contract (PRC) operations that compared available funding to mission and operational objectives in an effort to maintain requisite safety and compliance margins while realizing cost savings that meet funding profiles. These assessments included confirmation of current baseline activities, identification of potential efficiencies, barriers to implementation, and potential increased risks associated with implementation. Six operating PRC waste management facilities were evaluated against three possible end-states: complete facility closure, maintaining base operations, and performing minimum safe surveillance and maintenance activities. The costs to completely close evaluated facilities were determined to be prohibitively high and this end-state was quickly dropped from consideration. A summary of the analysis of remaining options by facility, efficiencies identified, impact to risk profiles, and expected cost savings is provided in Table I. The expected cost savings are a result of: - right-sizing and cross-training work crews to address maintenance activities across facilities; - combining and sequencing 'like-moded' operational processes; - cross-cutting emergency planning and preparedness staffing; - resource redistribution and optimization; - reducing areas requiring routine surveillance and inspection. For the efficiencies identified, there are corresponding increases in risk, including a loss of breadth and depth of available resources; lengthened response time to emergent issues; inability to invest in opportunities for improvement (OFIs); potential single-point failures or non-compliancies due to

Maximizing Operational Efficiencies in Waste Management on the Hanford Plateau Remediation Contract in a Down-turned Market - 13484

International Nuclear Information System (INIS)

Simiele, Connie J.; Blackford, L. Ty; West, Lori D.

2013-01-01

Recent changes in DOE priorities and funding have pressed DOE and its contractors to look for innovative methods to sustain critical operations at sites across the Complex. At the Hanford Site, DOE Richland Operations and its prime contractor, CH2M Hill Plateau Remediation Company (CHPRC), have completed in-depth assessments of the Plateau Remediation Contract (PRC) operations that compared available funding to mission and operational objectives in an effort to maintain requisite safety and compliance margins while realizing cost savings that meet funding profiles. These assessments included confirmation of current baseline activities, identification of potential efficiencies, barriers to implementation, and potential increased risks associated with implementation. Six operating PRC waste management facilities were evaluated against three possible end-states: complete facility closure, maintaining base operations, and performing minimum safe surveillance and maintenance activities. The costs to completely close evaluated facilities were determined to be prohibitively high and this end-state was quickly dropped from consideration. A summary of the analysis of remaining options by facility, efficiencies identified, impact to risk profiles, and expected cost savings is provided in Table I. The expected cost savings are a result of: - right-sizing and cross-training work crews to address maintenance activities across facilities; - combining and sequencing 'like-moded' operational processes; - cross-cutting emergency planning and preparedness staffing; - resource redistribution and optimization; - reducing areas requiring routine surveillance and inspection. For the efficiencies identified, there are corresponding increases in risk, including a loss of breadth and depth of available resources; lengthened response time to emergent issues; inability to invest in opportunities for improvement (OFIs); potential single-point failures or non-compliancies due to resource

Buried Waste Integrated Demonstration fiscal Year 1994 close-out report

International Nuclear Information System (INIS)

Owen, K.J.

1995-07-01

The Buried Waste integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the US Department of Energy Environmental Restoration and Waste Management needs and objectives. BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Department of Energy Office of Technology Development initiated BMD at the Idaho National Engineering Laboratory. This report summarizes the activities of the BWID program during Fiscal Year 1994. In Fiscal Year 1995, these activities are transitioning into the Landfill Stabilization Focus Area

Field sampling and analysis plan for the remedial investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Boston, H.L.; Ashwood, T.L.; Borders, D.M.; Chidambariah, V.; Downing, D.J.; Fontaine, T.A.; Ketelle, R.H.; Lee, S.Y.; Miller, D.E.; Moore, G.K.; Suter, G.W.; Tardiff, M.F.; Watts, J.A.; Wickliff, D.S.

1992-02-01

This field sampling and analysis (S ampersand A) plan has been developed as part of the Department of Energy's (DOE's) remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) located in Oak Ridge, Tennessee. The S ampersand A plan has been written in support of the remedial investigation (RI) plan for WAG 2 (ORNL 1990). WAG 2 consists of White Oak Creek (WOC) and its tributaries downstream of the ORNL main plant area, White Oak Lake (WOL), White Oak Creek embayment (WOCE) on the Clinch River, and the associated floodplain and subsurface environment (Fig. 1.1). The WOC system is the surface drainage for the major ORNL WAGs and has been exposed to a diversity of contaminants from operations and waste disposal activities in the WOC watershed. WAG 2 acts as a conduit through which hydrologic fluxes carry contaminants from upgradient areas to the Clinch River. Water, sediment, soil, and biota in WAG 2 are contaminated and continue to receive contaminants from upgradient WAGs. This document describes the following: an overview of the RI plan, background information for the WAG 2 system, and objectives of the S ampersand A plan; the scope and implementation of the first 2 years of effort of the S ampersand A plan and includes recent information about contaminants of concern, organization of S ampersand A activities, interactions with other programs, and quality assurance specific to the S ampersand A activities; provides details of the field sampling plans for sediment, surface water, groundwater, and biota, respectively; and describes the sample tracking and records management plan

Pollution Prevention/Waste Minimization

International Nuclear Information System (INIS)

Fowler, Kimberly M.; Hyman, Marvin H.

2002-01-01

This chapter offers pollution prevention techniques for design, industrial process, maintenance, and environmental remediation activities. It provides examples of waste reduction, tools for identifying pollution prevention opportunities, and ways of calculating the payback or return on investment associated with the opportunities

Test Area for Remedial Actions (TARA) site characterization and dynamic compaction of low-level radioactive waste trenches. FY 1988 progress report

Energy Technology Data Exchange (ETDEWEB)

Davis, E. C.; Spalding, B. P.; Lee, S. Y.; Hyder, L. K.

1989-01-01

As part of a low-level radioactive waste burial ground stabilization and closure technology demonstration project, a group of five burial trenches in Oak Ridge National Laboratory (ORNL) Solid Waste Storage Area (SWSA) 6 was selected as a demonstration site for testing trench compaction, trench grouting, and trench cap installation and performance. This report focuses on site characterization, trench compaction, and grout-trench leachate compatibility. Trench grouting and cap design and construction will be the subject of future reports. The five trenches, known as the Test Area for Remedial Actions (TARA) site, are contained within a hydrologically isolated area of SWSA 6; for that reason, any effects of stabilization activities on site performance and groundwater quality will be separable from the influence of other waste disposal units in SWSA 6. To obviate the chronic problem of burial trench subsidence and to provide support for an infiltration barrier cap, these five trenches were dynamically compacted by repeated dropping of a 4-ton weight onto each trench from heights of approximately 7 m.

Application of international recommendations and guidance on low level radioactive waste management and remediation of contaminated land at the national level: Experience of regulatory support in Northwest Russia

International Nuclear Information System (INIS)

Sneve, M.; Smith, G.M.; Kerrigan, E

2005-01-01

This paper notes the developments in international recommendations on radioactive waste management and remediation of contaminated land and considers their implementation in the context of the Norwegian Plan of Action to improve nuclear safety in North West Russia. Summary information is provided on projects to implement waste management activities (so-called Industrial Projects) and on projects to support regulatory supervision of waste management activities (so-called Regulatory Support Projects). The links between international recommendations and national practice are discussed and it is concluded that, in practice, the details of national standards differ both among themselves and, in some respects, from the recommendations of the ICRP and IAEA. Examples of further potential collaboration projects are listed. While separate responsibilities among organisations have to clear and maintained, combined involvement of operators and regulators is recognised as a prioritised area in future cooperation between NRPA and Russia. (author)

The role of performance assessment in the evaluation of remedial action alternatives for the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rood, A.S.; Case, M.J.

1988-01-01

The Idaho National Engineering Laboratory (INEL) is operated by the Department of Energy (DOE) and is involved in nuclear research and development. The Radioactive Waste Management Complex (RWMC) at the INEL serves as a disposal facility for low level radioactive wastes generated onsite. Transuranic (TRU) wastes received from other DOE sites are currently stored at the RWMC, but were buried at the facility from 1952 until 1970. Recent findings of the Subsurface Investigations Program have determined that migration of TRU nuclides and hazardous materials from the RWMC has occurred. The primary source of organics in the buried TRU waste was generated by the Rocky Flats Plant. The INEL has proposed an aggressive four-year action plan for buried TRU waste. As a part of this plan, a task has been identified to evaluate existing remedial technologies for preventing further contaminant migration or removing the source of TRU radionuclides and nonradioactive hazardous material from the RWMC. A systems approach is being applied to evaluate, compare and recommend technologies or combinations of technologies. One criterion used in the evaluation is the net risk reduction afforded by each proposed remedial action. The method used to develop the criterion relies on models to assess the potential pathways and scenarios for the migration of radioactive and nonradioactive materials and the subsequent exposure of individuals to those materials. This paper describes the approach used to assess the performance of various remedial actions and the results obtained to date

Case study: remediation of a former uranium mining/processing site in Hungary

International Nuclear Information System (INIS)

Csovari, M. et al.

2004-01-01

The Hungarian uranium mining activities near Pecs lasted from 1958 to 1997. Approximately 46 Mt of rock were mined, from which 18.8 Mt of upgraded ore were processed. Some ore had been exported prior to the construction of the processing plant at the site. Remediation of the former uranium-related industrial sites is being carried out by the Mecsek Ore Environment Ltd. and started in the 1990s. Today the former mines and their surroundings are rehabilitated, former heap piles and a number of smaller waste rock piles have been relocated to a more protected area (waste rock pile N 3). Ongoing core remediation activities are directed to the remediation of the tailings ponds, and also water treatment issues are most important. Three water treatment facilities are currently in operation: a mine water treatment system with the objective to remove uranium and gain a marketable by-product; a pump-and-treat system to restore the groundwater quality in the vicinity of the tailing ponds; a pilot-scale, experimental passive in-situ groundwater treatment system to avoid migration of uranium contaminated groundwater. Refs. 5 (author)

Waste Information Data System user guide

International Nuclear Information System (INIS)

Dietz, L.A.

1996-09-01

The Waste Information Data System (also known as the Environmental Sites Database) is a computerized system that provides a traceable source of information about environmental waste sites at the U.S. Department of Energy's Hanford Site in Richland, Washington. The system includes discovery, rejected, and accepted waste sites. The purpose of the system is to assist long-range waste management and environmental restoration planning by providing validated and reliable information about waste sites. The system is used to track site investigation, remediation, and closure-action activities

Final report of the systems engineering technical advisory board for the Tank Waste Remediation Program

Energy Technology Data Exchange (ETDEWEB)

Baranowski, F.P.; Goodlett, C.B.; Beard, S.J.; Duckworth, J.P.; Schneider, A.; Zahn, L.L.

1993-03-01

The Tank Waste Remediation System (TWRS) is one segment of the environmental restoration program at the Hanford site. The scope is to retrieve the contents of both the single shell and double shell tanks and process the wastes into forms acceptable for long term storage and/or permanent disposal. The quantity of radioactive waste in tanks is significantly larger and substantially more complex in composition than the radioactive waste stored in tanks at other DOE sites. The waste is stored in 149 single shell tanks and 28 double shell tanks. The waste was produced over a period from the mid 1940s to the present. The single shell tanks have exceeded their design life and are experiencing failures. The oldest of the double shell tanks are approaching their design life. Spar double shell tank waste volume is limited. The priorities in the Board`s view are to manage safely the waste tank farms, accelerate emptying of waste tanks, provide spare tank capacity and assure a high degree of confidence in performance of the TWRS integrated program. At its present design capacity, the glass vitrification plant (HWVP) will require a period of about 15 years to empty the double shell tanks; the addition of the waste in single shell tanks adds another 100 years. There is an urgent need to initiate now a well focused and centralized development and engineering program on both larger glass melters and advanced separations processes that reduce radioactive constituents in the low-level waste (LLW). The Board presents its conclusions and has other suggestions for the management plan. The Board reviews planning schedules for accelerating the TWRS program.

Final report of the systems engineering technical advisory board for the Tank Waste Remediation Program

International Nuclear Information System (INIS)

Baranowski, F.P.; Goodlett, C.B.; Beard, S.J.; Duckworth, J.P.; Schneider, A.; Zahn, L.L.

1993-03-01

The Tank Waste Remediation System (TWRS) is one segment of the environmental restoration program at the Hanford site. The scope is to retrieve the contents of both the single shell and double shell tanks and process the wastes into forms acceptable for long term storage and/or permanent disposal. The quantity of radioactive waste in tanks is significantly larger and substantially more complex in composition than the radioactive waste stored in tanks at other DOE sites. The waste is stored in 149 single shell tanks and 28 double shell tanks. The waste was produced over a period from the mid 1940s to the present. The single shell tanks have exceeded their design life and are experiencing failures. The oldest of the double shell tanks are approaching their design life. Spar double shell tank waste volume is limited. The priorities in the Board's view are to manage safely the waste tank farms, accelerate emptying of waste tanks, provide spare tank capacity and assure a high degree of confidence in performance of the TWRS integrated program. At its present design capacity, the glass vitrification plant (HWVP) will require a period of about 15 years to empty the double shell tanks; the addition of the waste in single shell tanks adds another 100 years. There is an urgent need to initiate now a well focused and centralized development and engineering program on both larger glass melters and advanced separations processes that reduce radioactive constituents in the low-level waste (LLW). The Board presents its conclusions and has other suggestions for the management plan. The Board reviews planning schedules for accelerating the TWRS program

ANALYSIS OF REMEDIATION PROCESS OF THE GROUDWATER COTAMINATION IN AN ILLEGAL DUMPING SITE

Science.gov (United States)

Nishida, Norikazu; Furuichi, Toru; Ishii, Kazuei

Among on-site remediation technologies applied to illegal dumping sites, a technology to remedy contaminated groundwater without removal of the dumped waste is expected to provide a great opportunity to fulfill a societal need due to its economic advantage compared to removal of all waste. However heterogeneously-distributed waste makes the remedial process difficult. In this study, an in situflushing technology was applied to an illegal dumping site in Kuwana city, Mie, in order to remedy groundwater contaminated with several volatile organic compounds (VOCs) within five years. The key to successfully achieve the target was to conduct a series of advanced remediation processes; introducing a new indicator by which multiple VOCs can be estimated integratelly, monitoring the progress of remediation with a contour map of VOC concentration as well as the weighted averages of the concentration derived from the indicator, pinpointing residual contaminants area, reexamining the plan, and taking additional steps that promote further remediation.

Solid waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

1994-06-01

A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management: Waste reduction workshop 7

International Nuclear Information System (INIS)

1991-11-01

The focus of this workshop was on goal setting and the methods of establishing meaningful goals for a waste minimization program. These workshops assist DOE waste-generating sites in implementing waste minimization plans and programs, thus providing for optimal waste reduction within the DOE complex. All wastes are considered liquid, solid, and airborne within the categories of high-level waste, transuranic waste (TRU), low-level waste (LLW), hazardous waste, mixed waste, office waste, and sanitary waste. Topics of discussion within workshops encompass a wide range of subjects. Subjects include any method or technical activity from waste generation to disposal, such as process design or improvements, substitution of materials, waste segregation and recycling/reuse, waste treatment and processing, and administrative controls (procurement and waste awareness training). Consideration is also given to activities for remedial action and for decontamination and decommissioning

Recent developments in health risks modeling techniques applied to hazardous waste site assessment and remediation

International Nuclear Information System (INIS)

Mendez, W.M. Jr.

1990-01-01

Remediation of hazardous an mixed waste sites is often driven by assessments of human health risks posed by the exposures to hazardous substances released from these sites. The methods used to assess potential health risk involve, either implicitly or explicitly, models for pollutant releases, transport, human exposure and intake, and for characterizing health effects. Because knowledge about pollutant fate transport processes at most waste sites is quite limited, and data cost are quite high, most of the models currently used to assess risk, and endorsed by regulatory agencies, are quite simple. The models employ many simplifying assumptions about pollutant fate and distribution in the environment about human pollutant intake, and toxicologic responses to pollutant exposures. An important consequence of data scarcity and model simplification is that risk estimates are quite uncertain and estimates of the magnitude uncertainty associated with risk assessment has been very difficult. A number of methods have been developed to address the issue of uncertainty in risk assessments in a manner that realistically reflects uncertainty in model specification and data limitations. These methods include definition of multiple exposure scenarios, sensitivity analyses, and explicit probabilistic modeling of uncertainty. Recent developments in this area will be discussed, along with their possible impacts on remediation programs, and remaining obstacles to their wider use and acceptance by the scientific and regulatory communities

A Potential Bio-Sorbent for Heavy Metals in the Remediation of Waste Water

Directory of Open Access Journals (Sweden)

Mohammad Laskar

2016-12-01

Full Text Available Bay leaves are used for flavoring in cold drinks production, in bakery goods, sauces, confectionary products and liquors. The waste generated from these sources has been valorized by attempting the remediation of waste water. Hence, adsorption of toxic metals onto Bay leaves has been investigated after optimizing the experimental parameters, namely the pH, contact time, adsorbent and Zn (II concentrations as well as the temperature of the equilibrium mixture (consisting of the metal solution in contact with the adsorbent. The participation of the constituent functional groups, of the adsorbent, was ascertained with Fourier Transform spectroscopic studies. The mode of adsorption was examined by employing important isotherm models, namely Langmuir, Freundlich and Dubinin-Radushkevich models. The adsorption process was found to follow pseudo-first order kinetic model and also followed the intraparticle diffusion up to 60 minutes of contact time. The thermodynamic parameters suggest the spontaneous nature of adsorption

Application of a World Wide Web technology to environmental remediation

International Nuclear Information System (INIS)

Johnson, R.; Durham, L. A.

2000-01-01

As part of the Formerly Utilized Site Remedial Action Program (FUSRAP), the United States Army Corps of Engineers (USACE), Buffalo District, is responsible for overseeing the remediation of several sites within its jurisdiction. FUSRAP sites are largely privately held facilities that were contaminated by activities associated with the nuclear weapons program in the 1940s, 50s, and 60s. The presence of soils and structures contaminated with low levels of radionuclides is a common problem at these sites. Typically, contaminated materials must be disposed of off-site at considerable expense (up to several hundred dollars per cubic yard of waste material). FUSRAP is on an aggressive schedule, with most sites scheduled for close-out in the next couple of years. Among the multitude of tasks involved in a typical remediation project is the need to inform and coordinate with active stakeholder communities, including local, state, and federal regulators

Remedial design and remedial action guidance for the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1993-10-01

The US Department of Energy, Idaho Operations Office (DOE-ID), the US Environmental Protection Agency, Region X (EPA), and the Idaho Department of Health and Welfare (IDHW) have developed this guidance on the remedial design and remedial action (RD/RA) process. This guidance is applicable to activities conducted under the Idaho National Engineering Laboratory (INEL) Federal Facility Agreement and Consent Order (FFA/CO) and Action Plan. The INEL FFA/CO and Action Plan provides the framework for performing environmental restoration according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The guidance is intended for use by the DOE-ID, the EPA, and the IDHW Waste Area Group (WAG) managers and others involved in the planning and implementation of CERCLA environmental restoration activities. The scope of the guidance includes the RD/RA strategy for INEL environmental restoration projects and the approach to development and review of RD/RA documentation. Chapter 2 discusses the general process, roles and responsibilities, and other elements that define the RD/RA strategy. Chapters 3 through 7 describe the RD/RA documents identified in the FFA/CO and Action Plan. Chapter 8 provides examples of how this guidance can be applied to restoration projects. Appendices are included that provide excerpts from the FFA/CO pertinent to RD/RA (Appendix A), a applicable US Department of Energy (DOE) orders (Appendix B), and an EPA Engineering ''Data Gaps in Remedial Design'' (Appendix C)

Activation/waste management

International Nuclear Information System (INIS)

Maninger, C.

1984-10-01

The selection of materials and the design of the blankets for fusion reactors have significant effects upon the radioactivity generated by neutron activation in the materials. This section considers some aspects of materials selection with respect to waste management. The activation of the materials is key to remote handling requirements for waste, to processing and disposal methods for waste, and to accident severity in waste management operations. In order to realize the desirable evnironmental potentials of fusion power systems, there are at least three major goals for waste management. These are: (a) near-surface burial; (b) disposal on-site of the fusion reactor; (c) acceptable radiation doses at least cost during and after waste management operations

Final Hazard Categorization for the Remediation of Six 300-FF-2 Operable Unit Solid Waste Burial Grounds

International Nuclear Information System (INIS)

Ludowise, J.D.

2006-01-01

This report provides the final hazard categorization (FHC) for the remediation of six solid waste disposal sites (referred to as burial grounds) located in the 300-FF-2 Operable Unit (OU) on the Hanford Site. These six sites (618-1, 618-2, 618-3, 618-7, 618-8, and 618-13 Burial Grounds) were determined to have a total radionuclide inventory (WCH 2005a, WCH 2005d, WCH 2005e and WCH 2006b) that exceeds the DOE-STD-1027 Category 3 threshold quantity (DOE 1997) and are the subject of this analysis. This FHC document examines the hazards, identifies appropriate controls to manage the hazards, and documents the FHC and commitments for the 300-FF-2 Burial Grounds Remediation Project

Final Hazard Categorization for the Remediation of Six 300-FF-2 Operable Unit Solid Waste Burial Grounds

Energy Technology Data Exchange (ETDEWEB)

J. D. Ludowise

2006-12-12

This report provides the final hazard categorization (FHC) for the remediation of six solid waste disposal sites (referred to as burial grounds) located in the 300-FF-2 Operable Unit (OU) on the Hanford Site. These six sites (618-1, 618-2, 618-3, 618-7, 618-8, and 618-13 Burial Grounds) were determined to have a total radionuclide inventory (WCH 2005a, WCH 2005d, WCH 2005e and WCH 2006b) that exceeds the DOE-STD-1027 Category 3 threshold quantity (DOE 1997) and are the subject of this analysis. This FHC document examines the hazards, identifies appropriate controls to manage the hazards, and documents the FHC and commitments for the 300-FF-2 Burial Grounds Remediation Project.

Remediation of former uranium mining and milling activities in Central Asia

International Nuclear Information System (INIS)

Waggitt, Peter

2007-01-01

Available in abstract form only. Full text of publication follows: Several of the Central Asian countries of the former Soviet Union were involved in the uranium mining and milling industry from about 1945 for varying periods until the break up of the Soviet Union in 1991 and beyond. Some facilities are still producing in Uzbekistan and Kazakhstan. However, before the break up, many facilities had been abandoned and in only a few cases had any remediation been undertaken. Since 1991 the newly independent states of the region have been seeking assistance for the remediation of the multitude of tailings piles, waste rock stockpiles and abandoned, and often semi dismantled, production facilities that may be found throughout the region. Many of these sites are close to settlements that were established as service towns for the mines. Most towns still have populations, although the mining industry has departed. In some instances there are cases of pollution and contamination and in many locations there is a significant level of public concern. The IAEA has been undertaking a number of Technical Cooperation (TC) projects throughout the region for some time to strengthen the institutions in the relevant states and assist them to establish monitoring and surveillance programs as an integral part of the long term remediation process. The IAEA is liaising with other agencies and donors who are also working on these problems to optimise the remediation effort. The paper describes the objectives and operation of the main TC regional program, liaison efforts with other agencies, the achievements so far and the long term issues for remediation of these legacies of the 'cold war' era. (authors)

Remedial investigation/feasibility study work plan for the 300-FF-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1990-03-01

Over 1,400 waste facilities have been identified on the Hanford Site. Most of the waste facilities are located within geographic areas on the Hanford Site that are referred to as the 100, 200, 300, 400, and 1100 areas. The purpose of this work plan is to document the project scoping process and to outline all remedial investigation/feasibility study (RI/FS) activities, to determine the nature and extent of the threat presented by releases of hazardous substances from the operable unit, and to evaluate proposed remedies for such releases. The goal of the 300-FF-1 remedial investigation (RI) is to provide sufficient information needed to conduct the feasibility study (FS), by determining the nature and extent of the threat to public health and the environment posed by releases of hazardous substances from 300-FF-1, and the performance of specific remedial technologies. 62 refs., 28 figs., 48 tabs

Implementation of the buried waste integrated demonstration

International Nuclear Information System (INIS)

Kostelnik, K.M.; Merrill, S.K.

1992-01-01

The Department of Energy (DOE), Office of Technology Development (OTD) has initiated the Buried Waste Integrated Demonstration (BWID) to resolve technological deficiencies associated with the remediation of radioactive and hazardous buried waste. The BWID mission is to identify, demonstrate, and transfer innovative technologies for the remediation of DOE buried waste. To accomplish the mission, BWID is using a systems approach which supports the development of a suite of advanced and innovative technologies for the effective and efficient remediation of buried waste. This systems approach includes technologies for theentire remediation cycle. Specifically, BWID sponsors technology development in the following technology categories: site and waste characterization, retrieval, preprocessing, ex situ treatment, packaging, transportation, storage, disposal, and post-disposal monitoring

Regulatory supervision of industrial waste containing very low activities of man-made radionuclides at SevRAO facility

International Nuclear Information System (INIS)

Sneve, Malgorzata K.; Kochetkov, Oleg; Monastyrskaya, Svetlana; Barchukov, Valerie; Romanov, Vladimir

2008-01-01

Full text: Large amounts of waste and materials with very low activity level are generated during operation and especially during decommissioning of nuclear facilities. Selection of the optimum economic and ecologically safe management option of such material is complicated by its specific features: very low level radiation exposure to individuals but rather large initial amounts of waste. On the one hand, it is a poor use of limited resources to em place such low activity waste into expensive facilities for radioactive waste storage and disposal if the radiological impact would be very small even for a much less expensive option; on the other hand, there is some apprehension regarding safety both about its disposal to landfills for conventional (non-radioactive) waste disposal, and about its limited or unlimited re-use or re-cycling. To regulate such waste management, a special waste category is introduced - very low level waste (VLLW). This category includes waste containing radionuclides with specific activity levels, which are higher than clearance levels, but do not need high containment and isolation. This paper discusses experience of regulatory development for VLLW control during remediation of radiation hazardous facilities in northwest Russia. The work has promoted identification of some challenges, whose solution has affected the waste management strategy at the sites. One of the main problems resolved was the selection of criteria according to which waste is allocated to the VLLW category. These is turn were partly determined by the radiological criteria chosen for protection of the public during this waste disposal. Elaboration of safe VLLW management strategy depends upon a source of waste generation and of its radiological composition. The VLLW management strategy at an operating enterprise, e.g. a nuclear power plant is rather different from the strategy implemented at the plant under decommissioning, or at storage facilities for the legacy waste

Remedial site evaluation report for the waste area grouping 10 wells associated with the new hydrofracture facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2: Field activities and well summaries

International Nuclear Information System (INIS)

1996-08-01

Four hydrofracture sites at the Oak Ridge National Laboratory (ORNL) were used for development, demonstration, and disposal from 1959 to 1984. More than 10 million gal of waste grout mix was disposed of via hydrofracture. Various types of wells were installed to monitor the hydrofracture operations. The primary goal of this remedial investigation was to gather information about the wells in order to recommend the type and best method of final disposition for the wells. Evaluations were performed to determine the integrity of well castings, confirm construction details for each well, evaluate the extent of contamination, assist in planning for future activities, and determine the suitability of the wells for future temporary site monitoring

Tank waste concentration mechanism study

International Nuclear Information System (INIS)

Pan, L.C.; Johnson, L.J.

1994-09-01

This study determines whether the existing 242-A Evaporator should continue to be used to concentrate the Hanford Site radioactive liquid tank wastes or be replaced by an alternative waste concentration process. Using the same philosophy, the study also determines what the waste concentration mechanism should be for the future TWRS program. Excess water from liquid DST waste should be removed to reduce the volume of waste feed for pretreatment, immobilization, and to free up storage capacity in existing tanks to support interim stabilization of SSTS, terminal cleanout of excess facilities, and other site remediation activities

Tank waste remediation system process engineering instruction manual

International Nuclear Information System (INIS)

ADAMS, M.R.

1998-01-01

The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees

DEVELOPMENT, QUALIFICATION, AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE

International Nuclear Information System (INIS)

Sams, T.L.; Edge, J.A.; Swanberg, D.J.; Robbins, R.A.

2011-01-01

Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

Completion report for the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-02-01

This report documents the results of the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory (ORNL). The work performed is compared with that proposed in the statement of work and the service contract specification for the maintenance action to remediate tanks 3013, 3004-B, T-30, and 3001-B. The Federal Facility Agreement (FFA) among the U.S. Environmental Protection Agency (EPA), the Tennessee Department of Environment and Conservation (TDEC), and the U.S. Department of Energy (DOE) requires that all tanks, which have been removed from service and are designated in the FFA as Category D, must be remediated in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. The Environmental Restoration Program's inactive tank removal program strategy and plans for remediating the inactive LLLW tanks were documented in a report issued in January 1995 (Inactive Tanks Remediation Program Strategy and Plans for Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-297). The inactive (Category D) tanks were initially screened for remediation according to risk, remediation technology required, level of instrumentation available, interferences with other piping and equipment, location, and available sludge removal techniques and storage requirements. On the basis of this preliminary screening, the tanks were assigned to one of five batches (I through V) for consideration of remedial action alternatives, and these batches were tentatively scheduled for remedial actions. The eight links tentatively assigned to Batch I were divided into two groups (Series I and Series II)

Contamination-remedying technology based on biotechnology. ; Bioremediation. Biotechnology wo mochiita osen shufuku gijutsu. ; Bioremediation

Energy Technology Data Exchange (ETDEWEB)

Nishimura, M [The Japan Research Institute, Ltd., Osaka (Japan)

1993-08-01

Bioremediation technology is outlined. The bioremediation technology is a contamination-remedying technology for the injurious chemical matter discharged in the environment to be made innocuous by utilizing the decomposing ability of microorganisms. That technology is characterized by its energywise economical performance, secondary waste which is not producible and remedy which is possible on site against the contamination. As a treatment system, that technology comprises solid phase bioremediation (The contaminated soil is purified in a soil treatment unit.), slurry phase bioremediation (The contaminated soil is made slurry and decomposed by microorganisms.) and in-situ bioremediation (The treatment is made by injecting nutrients and microorganisms underground.). As for how to use the microorganisms, there are two methods: One in which living groups of microorganisms are activated and the other in which microorganisms are artificially cultivated. As contaminants in the US, listed are organic solvent, wood preservative, high-molecular aromatic halide, agricultural chemical, military waste, heavy metal waste and radioactive waste. 11 refs., 5 figs., 1 tab.

Remediating sites contaminated with heavy metals

International Nuclear Information System (INIS)

Swartzbaugh, J.; Sturgill, J.; Cormier, B.; Williams, H.D.

1992-01-01

This article is intended to serve as a reference for decision makers who must choose an approach to remediate sites contaminated with heavy metals. Its purpose is to explain pertinent chemical and physical characteristics of heavy metals, how to use these characteristics to select remedial technologies, and how to interpret and use data from field investigations. Different metal species are typically associated with different industrial processes. The contaminant species behave differently in various media (i.e., groundwater, soils, air), and require different technologies for containment and treatment. We focus on the metals that are used in industries that generate regulated waste. These include steelmaking, paint and pigment manufacturing, metal finishing, leather tanning, papermaking, aluminum anodizing, and battery manufacturing. Heavy metals are also present in refinery wastes as well as in smelting wastes and drilling muds

Temporary septic holding tank at the 100-C remedial action restroom facility -- Engineering report

International Nuclear Information System (INIS)

Jackson, G.J.

1996-10-01

The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemically hazardous constituents. Investigation and remediation of these waste sites is governed by the Tri-Party Agreement. The agreement grouped the waste sites into 78 operable units, each of which was to be investigated and remediated separately. The 100-C Remedial Action Restroom Trailer Facility will be required near the 105-C Reactor to support the 105-C Interim Storage Project. This project is part of the decommissioning of the eight surplus reactor buildings along the Columbia River in the 100 Area. This facility will be a temporary, modular building sized to provide restroom facilities for the supervisors, engineers, technicians, and craft personnel assigned to the project and engaged in the associated field work. This facility will be a temporary, modular building sized to provide restroom facilities for the supervisors, engineers, technicians, and raft personnel assigned to the project and engaged in the associated field work. The paper describes the project location, geology and flooding potential, design criteria, and operations and maintenance

SRS Burial Ground Complex: Remediation in Progress

International Nuclear Information System (INIS)

Griffin, M.; Crapse, B.; Cowan, S.

1998-01-01

Closure of the various areas in the Burial Ground Complex (BGC) represents a major step in the reduction of risk at the Savannah River Site (SRS) and a significant investment of resources. The Burial Ground Complex occupies approximately 195 acres in the central section of the SRS. Approximately 160 acres of the BGC consists of hazardous and radioactive waste disposal sites that require remediation. Of these source acres, one-third have been remediated while two-thirds are undergoing interim or final action. These restoration activities have been carried out in a safe and cost effective manner while minimizing impact to operating facilities. Successful completion of these activities is in large part due to the teamwork demonstrated by the Department of Energy, contractor/subcontractor personnel, and the regulatory agencies. The experience and knowledge gained from the closure of these large disposal facilities can be used to expedite closure of similar facilities

Utilization of waste materials, non-refined materials, and renewable energy in in situ remediation and their sustainability benefits.

Science.gov (United States)

Favara, Paul; Gamlin, Jeff

2017-12-15

In the ramp-up to integrating sustainability into remediation, a key industry focus area has been to reduce the environmental footprint of treatment processes. The typical approach to integrating sustainability into remediation projects has been a top-down approach, which involves developing technology options and then applying sustainability thinking to the technology, after it has been conceptualized. A bottom-up approach allows for systems thinking to be included in remedy selection and could potentially result in new or different technologies being considered. When using a bottom-up approach, there is room to consider the utilization of waste materials, non-refined materials, and renewable energy in remediation technology-all of which generally have a smaller footprint than processed materials and traditional forms of energy. By integrating more systems thinking into remediation projects, practitioners can think beyond the traditional technologies typically used and how technologies are deployed. To compare top-down and bottom-up thinking, a traditional technology that is considered very sustainable-enhanced in situ bioremediation-is compared to a successful, but infrequently deployed technology-subgrade biogeochemical reactors. Life Cycle Assessment is used for the evaluation and shows the footprint of the subgrade biogeochemical reactor to be lower in all seven impact categories evaluated, sometimes to a significant degree. Copyright © 2017 Elsevier Ltd. All rights reserved.

Hanford's Radioactive Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

McKenney, D.E.

1995-01-01

The Radioactive Mixed Waste Disposal Facility, is located in the Hanford Site Low-Level Burial Grounds and is designated as Trench 31 in the 218-W-5 Burial Ground. Trench 31 is a Resource Conservation and Recovery Act compliant landfill and will receive wastes generated from both remediation and waste management activities. On December 30, 1994, Westinghouse Hanford Company declared readiness to operate Trench 31, which is the Hanford Site's (and the Department of Energy complex's) first facility for disposal of low-level radioactive mixed wastes

Radon impact at a remediated uranium mine site in Japan

International Nuclear Information System (INIS)

Ishimori, Yuu

2011-01-01

This paper mainly illustrates the radon impact of the closed uranium mine site remediated in 2007. The site remediated is the waste rock site located on the steep slope of a hill about 1.5 km upstream from a residential area along a main ravine. Major remedial action was to cover these waste rock yards with weathering granite soil. The radon flux density after remediation was intended to be 0.1 Bqm -2 s -1 in consideration with the natural background level around Ningyo-toge because there is no value of radon flux density regulated in Japan. Our action decreased the radon concentration in the site to natural background level, approximately from 10 to 40 Bqm -3 , although relatively high concentration in excess of 100 Bqm -3 was observed before remediation. On the other hand, our action did not decrease the radon concentrations around the site in general. This fact proved that the limited source such as waste rocks affected the radon concentrations at neighboring area only. The similar tendencies were also observed in other environmental data such as radon progeny concentrations. In conclusion, these findings proved that our remedial action was successful against radon. This fact will lead to more reasonable action plans for other closed mine sites. (author)

Remediation of Highland Drive Landfill: Technical Challenges of Segregating Co-Mingled LLRW and Municipal Solid Waste in an Urbanized Area - 13319

Energy Technology Data Exchange (ETDEWEB)

Daniel, Jeff [Conestoga-Rovers and Associates, 651 Colby Drive, Waterloo, ON (Canada); Lawrence, Dave [Public Works and Government Services Canada, 115 Toronto Road, Port Hope, ON (Canada); Case, Glenn [Atomic Energy of Canada Limited, 115 Toronto Road, Port Hope, ON (Canada); Fergusson Jones, Andrea [MMM Group Ltd., 100 Commerce Valley Drive West, Thornhill, ON (Canada)

2013-07-01

Highland Drive Landfill is an inactive Municipal Solid Waste (MSW) Landfill which received waste from the 1940's until its closure in 1991. During a portion of its active life, the Landfill received low-level radioactive waste (LLRW) which currently exists both in a defined layer and co-mingled with MSW. Remediation of this site to remove the LLRW to meet established cleanup criteria, forms part of the Port Hope Project being undertaken by Atomic Energy Canada Limited (AECL) and Public Works and Government Services Canada (PWGSC) as part of the Port Hope Area Initiative (PHAI). The total volume of LLRW and co-mingled LLRW/MSW estimated to require removal from the Highland Drive Landfill is approximately 51,900 cubic metres (m{sup 3}). The segregation and removal of LLRW at the Highland Drive Landfill presents a number of unique technical challenges due to the co-mingled waste and location of the Landfill in an urbanized area. Key challenges addressed as part of the design process included: delineation of the extent of LLRW, development of cut lines, and estimation of the quantity of co-mingled LLRW in a heterogeneous matrix; protection of adjacent receptors in a manner which would not impact the use of adjacent facilities which include residences, a recreational facility, and a school; coordination and phasing of the work to allow management of six separate material streams including clean soil, MSW, co-mingled LLRW/MSW, LLRW, un-impacted water, and impacted water/leachate within a confined environment; and development of a multi-tiered and adaptive program of monitoring and control measures for odour, dust, and water including assessment of risk of exceedance of monitoring criteria. In addition to ensuring public safety and protection of the environment during remedy implementation, significant effort in the design process was paid to balancing the advantages of increased certainty, including higher production rates, against the costs of attaining increased

Remediation of Highland Drive Landfill: Technical Challenges of Segregating Co-Mingled LLRW and Municipal Solid Waste in an Urbanized Area - 13319

International Nuclear Information System (INIS)

Daniel, Jeff; Lawrence, Dave; Case, Glenn; Fergusson Jones, Andrea

2013-01-01

Highland Drive Landfill is an inactive Municipal Solid Waste (MSW) Landfill which received waste from the 1940's until its closure in 1991. During a portion of its active life, the Landfill received low-level radioactive waste (LLRW) which currently exists both in a defined layer and co-mingled with MSW. Remediation of this site to remove the LLRW to meet established cleanup criteria, forms part of the Port Hope Project being undertaken by Atomic Energy Canada Limited (AECL) and Public Works and Government Services Canada (PWGSC) as part of the Port Hope Area Initiative (PHAI). The total volume of LLRW and co-mingled LLRW/MSW estimated to require removal from the Highland Drive Landfill is approximately 51,900 cubic metres (m 3 ). The segregation and removal of LLRW at the Highland Drive Landfill presents a number of unique technical challenges due to the co-mingled waste and location of the Landfill in an urbanized area. Key challenges addressed as part of the design process included: delineation of the extent of LLRW, development of cut lines, and estimation of the quantity of co-mingled LLRW in a heterogeneous matrix; protection of adjacent receptors in a manner which would not impact the use of adjacent facilities which include residences, a recreational facility, and a school; coordination and phasing of the work to allow management of six separate material streams including clean soil, MSW, co-mingled LLRW/MSW, LLRW, un-impacted water, and impacted water/leachate within a confined environment; and development of a multi-tiered and adaptive program of monitoring and control measures for odour, dust, and water including assessment of risk of exceedance of monitoring criteria. In addition to ensuring public safety and protection of the environment during remedy implementation, significant effort in the design process was paid to balancing the advantages of increased certainty, including higher production rates, against the costs of attaining increased certainty

Remediating MGP brownfields

International Nuclear Information System (INIS)

Larsen, B.R.

1997-01-01

Before natural gas pipelines became widespread in this country, gas fuel was produced locally in more than 5,000 manufactured gas plants (MGPs). The toxic wastes from these processes often were disposed onsite and have since seeped into the surrounding soil and groundwater. Although the MGPs--commonly called gas plants, gas-works or town gas plants--have closed and most have been demolished, they have left a legacy of environmental contamination. At many MGP sites, underground storage tanks were constructed of wood or brick, with process piping and equipment which frequently leaked. Waste materials often were disposed onsite. Releases of coal tars, oils and condensates produced within the plants contributed to a wide range of contamination from polycyclic aromatic hydrocarbons, phenols, benzene and cyanide. Remediation of selected MGP sites has been sporadic. Unless the site has been identified as a Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) Superfund site, the regulatory initiative to remediate often remains with the state in which the MGP is located. A number of factors are working to change that picture and to create a renewed interest in MGP site remediation. The recent Brownfield Initiative by the US Environmental Protection Agency (EPA) is such an example

Field sampling and analysis plan for the remedial investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

Boston, H.L.; Ashwood, T.L.; Borders, D.M.; Chidambariah, V.; Downing, D.J.; Fontaine, T.A.; Ketelle, R.H.; Lee, S.Y.; Miller, D.E.; Moore, G.K.; Suter, G.W.; Tardiff, M.F.; Watts, J.A.; Wickliff, D.S.

1992-02-01

This field sampling and analysis (S & A) plan has been developed as part of the Department of Energy`s (DOE`s) remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) located in Oak Ridge, Tennessee. The S & A plan has been written in support of the remedial investigation (RI) plan for WAG 2 (ORNL 1990). WAG 2 consists of White Oak Creek (WOC) and its tributaries downstream of the ORNL main plant area, White Oak Lake (WOL), White Oak Creek embayment (WOCE) on the Clinch River, and the associated floodplain and subsurface environment (Fig. 1.1). The WOC system is the surface drainage for the major ORNL WAGs and has been exposed to a diversity of contaminants from operations and waste disposal activities in the WOC watershed. WAG 2 acts as a conduit through which hydrologic fluxes carry contaminants from upgradient areas to the Clinch River. Water, sediment, soil, and biota in WAG 2 are contaminated and continue to receive contaminants from upgradient WAGs. This document describes the following: an overview of the RI plan, background information for the WAG 2 system, and objectives of the S & A plan; the scope and implementation of the first 2 years of effort of the S & A plan and includes recent information about contaminants of concern, organization of S & A activities, interactions with other programs, and quality assurance specific to the S & A activities; provides details of the field sampling plans for sediment, surface water, groundwater, and biota, respectively; and describes the sample tracking and records management plan.

Field test plan: Buried waste technologies, Fiscal Year 1995

International Nuclear Information System (INIS)

Heard, R.E.; Hyde, R.A.; Engleman, V.S.; Evans, J.D.; Jackson, T.W.

1995-06-01

The US Department of Energy, Office of Technology Development, supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that, when integrated with commercially available baseline technologies, form a comprehensive remediation system for the effective and efficient remediation of buried waste. The Fiscal Year 1995 effort is to deploy and test multiple technologies from four functional areas of buried waste remediation: site characterization, waste characterization, retrieval, and treatment. This document is the basic operational planning document for the deployment and testing of the technologies that support the field testing in Fiscal Year 1995. Discussed in this document are the scope of the tests; purpose and objective of the tests; organization and responsibilities; contingency plans; sequence of activities; sampling and data collection; document control; analytical methods; data reduction, validation, and verification; quality assurance; equipment and instruments; facilities and utilities; health and safety; residuals management; and regulatory management

Remediation of uranium impacted sediments in a watercourse

Energy Technology Data Exchange (ETDEWEB)

Shephard, Eugene; Walter, Nelson; Downey, Heath [AMEC, Inc., Portland, Maine (United States); Collopy, Peter [AMEC, Inc., San Diego, California (United States); Conant, John [ABB, Inc., Windsor, Connecticut (United States)

2013-07-01

In 2009, remediation was initiated for a non-operational fuel cycle facility previously used for government contract work located in Windsor, Connecticut, USA. Radiological contaminants consisted primarily of high enriched uranium (HEU). Other radionuclides encountered in relatively minor amounts in certain areas of the clean-up included Co-60, Cs- 137, Ra-226, Th-232 and low enriched uranium (LEU).Between 2009 and the spring of 2011, remediation efforts were focused on demolition of contaminated buildings and removal of contaminated soil. In the late spring of 2011, the last phase of remediation commenced involving the removal of contaminated sediments from portions of a 1,200 meter long gaining stream. Planning and preparation for remediation of the stream began in 2009 with submittal of permit applications to undertake construction activities in a wetland area. The permitting process was lengthy and involved securing permits from multiple agencies. However, early and frequent communication with stakeholders played an integral role in efficiently obtaining the permit approvals. Frequent communication with stakeholders throughout the planning and remediation process also proved to be a key factor in timely completion of the project. The remediation of the stream involved the use of temporary bladder berms to divert surface water flow, water diversion piping, a sediment vacuum removal system, excavation of sediments using small front-end loaders, sediment dewatering, and waste packaging, transportation and disposal. Many safeguards were employed to protect several species of concern in the work area, water management during project activities, challenges encountered during the project, methods of Final Status Survey, and stream restoration. (authors)

Natural Remediation at Savannah River Site

International Nuclear Information System (INIS)

Lewis, C. M.; Van Pelt, R.

2002-01-01

Natural remediation is a general term that includes any technology or strategy that takes advantage of natural processes to remediate a contaminated media to a condition that is protective of human health and the environment. Natural remediation techniques are often passive and minimally disruptive to the environment. They are generally implemented in conjunction with traditional remedial solutions for source control (i.e., capping, stabilization, removal, soil vapor extraction, etc.). Natural remediation techniques being employed at Savannah River Site (SRS) include enhanced bio-remediation, monitored natural attenuation, and phytoremediation. Enhanced bio-remediation involves making nutrients available and conditions favorable for microbial growth. With proper precautions and feeding, the naturally existing microbes flourish and consume the contaminants. Case studies of enhanced bio-remediation include surface soils contaminated with PCBs and pesticides, and Volatile Organic Compound (VOC) contamination in both the vadose zone and groundwater. Monitored natural attenuation (MNA) has been selected as the preferred alternative for groundwater clean up at several SRS waste units. Successful implementation of MNA has been based on demonstration that sources have been controlled, groundwater modeling that indicates that plumes will not expand or reach surface water discharge points at levels that exceed regulatory limits, and continued monitoring. Phytoremediation is being successfully utilized at several SRS waste units. Phytoremediation involves using plants and vegetation to uptake, break down, or manage contaminants in groundwater or soils. Case studies at SRS include managing groundwater plumes of tritium and VOCs with pine trees that are native to the area. Significant decreases in tritium discharge to a site stream have been realized in one phytoremediation project. Studies of other vegetation types, methods of application, and other target contaminants are

Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- monitoring technology

International Nuclear Information System (INIS)

Johnson, H.R.; Overbey, W.K. Jr.; Molnar, D.L.

1994-02-01

The objective of this study was to investigate and evaluate existing proven technologies for the monitoring of hazardous waste sites during remediation activities and to protect the health and safety of all related entities while complying with government regulations. The study began with a literature search to determine manufacturers and related instrumentation which would be applicable to the most complex (in terms of toxicity and mediums affected) sites. Criteria for monitoring and analyses were established and a functional analysis was performed to select the most appropriate instrumentation available. Gas Chromatography/Mass Spectrometry is the most widely accepted method for generating quantitative data given the characterization of the Winfield site. Fourier Transform Infrared Spectroscopy, while not a new technology, has the distinct advantage of measuring simultaneously hundreds of gaseous pollutants which can also be sparged from water and this technology received the highest score as per the functional analysis. To protect workers and the public surrounding remediation sites which are known to contain VOCs, on site monitoring prior to, and during the excavation operations, is recommended until enough data are obtained to assess the health risks to workers. The conclusion of this study is to recommend evaluation of both the mobile GC/MS and FTIR systems simultaneously in identical operating conditions

Field Sampling Plan for the Operable Units 6-05 and 10-04 Remedial Action, Phase IV

Energy Technology Data Exchange (ETDEWEB)

R. Wells

2006-11-14

This Field Sampling Plan outlines the collection and analysis of samples in support of Phase IV of the Waste Area Group 10, Operable Units 6-05 and 10-04 remedial action. Phase IV addresses the remedial actions to areas with the potential for unexploded ordnance at the Idaho National Laboratory Site. These areas include portions of the Naval Proving Ground, the Arco High-Altitude Bombing Range, and the Twin Buttes Bombing Range. The remedial action consists of removal and disposal of ordnance by high-order detonation, followed by sampling to determine the extent, if any, of soil that might have been contaminated by the detonation activities associated with the disposal of ordnance during the Phase IV activities and explosives during the Phase II activities.

Analysis of waste management issues arising from a field study evaluating decontamination of a biological agent from a building.

Science.gov (United States)

Lemieux, P; Wood, J; Drake, J; Minamyer, S; Silvestri, E; Yund, C; Nichols, T; Ierardi, M; Amidan, B

2016-01-01

The Bio-response Operational Testing and Evaluation (BOTE) Project was a cross-government effort designed to operationally test and evaluate a response to a biological incident (release of Bacillus anthracis [Ba] spores, the causative agent for anthrax) from initial public health and law enforcement response through environmental remediation. The BOTE Project was designed to address site remediation after the release of a Ba simulant, Bacillus atrophaeus spp. globigii (Bg), within a facility, drawing upon recent advances in the biological sampling and decontamination areas. A key component of response to a biological contamination incident is the proper management of wastes and residues, which is woven throughout all response activities. Waste is generated throughout the response and includes items like sampling media packaging materials, discarded personal protective equipment, items removed from the facility either prior to or following decontamination, aqueous waste streams, and materials generated through the application of decontamination technologies. The amount of residual contaminating agent will impact the available disposal pathways and waste management costs. Waste management is an integral part of the decontamination process and should be included through "Pre-Incident" response planning. Overall, the pH-adjusted bleach decontamination process generated the most waste from the decontamination efforts, and fumigation with chlorine dioxide generated the least waste. A majority of the solid waste generated during pH-adjusted bleach decontamination was the nonporous surfaces that were removed, bagged, decontaminated ex situ, and treated as waste. The waste during the two fumigation rounds of the BOTE Project was associated mainly with sampling activities. Waste management activities may represent a significant contribution to the overall cost of the response/recovery operation. This paper addresses the waste management activities for the BOTE field test

Development of the Remedial Action Priority System: an improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

International Nuclear Information System (INIS)

Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

1985-08-01

The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment, and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to pose significant problems to human health, safety, and/or the environment. The HRS is used by the US Environmental Protection Agency to identify sites for nomination to the National Priorites List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. 15 refs., 6 figs., 3 tabs

DOE complex buried waste characterization assessment

International Nuclear Information System (INIS)

Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

1993-01-01

The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m 3 of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993)

Hazardous and mixed waste transportation program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1993-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas. (J.P.N.)

Hazardous and Mixed Waste Transportation Program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1991-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas

DOE's plan for buried transuranic (TRU) contaminated waste

International Nuclear Information System (INIS)

Mathur, J.; D'Ambrosia, J.; Sease, J.

1987-01-01

Prior to 1970, TRU-contaminated waste was buried as low-level radioactive waste. In the Defense Waste Management Plan issued in 1983, the plan for this buried TRU-contaminated waste was to monitor the buried waste, take remedial actions, and to periodically evaluate the safety of the waste. In March 1986, the General Accounting Office (GAO) recommended that the Department of Energy (DOE) provide specific plans and cost estimates related to buried TRU-contaminated waste. This plan is in direct response to the GAO request. Buried TRU-contaminated waste and TRU-contaminated soil are located in numerous inactive disposal units at five DOE sites. The total volume of this material is estimated to be about 300,000 to 500,000 m 3 . The DOE plan for TRU-contaminated buried waste and TRU-contaminated soil is to characterize the disposal units; assess the potential impacts from the waste on workers, the surrounding population, and the environment; evaluate the need for remedial actions; assess the remedial action alternatives; and implement and verify the remedial actions as appropriate. Cost estimates for remedial actions for the buried TRU-contaminated waste are highly uncertain, but they range from several hundred million to the order of $10 billion

BioKonversion technology recovers, remediates and reuses waste and hydrocarbons from oil drilling

Energy Technology Data Exchange (ETDEWEB)

Topf, A.

2008-01-15

Houston-based Nopal Group has developed a solution to dispose of oilfield waste in a safe and cost-effective manner. The company is actively engaged in a large-scale project to remediate a 400-hectare site on the Aspheron Peninsula in Azerbaijan. The site is currently regarded as the most polluted place in the world after a century of oil extraction with little regard for the surrounding environment. The Nopal Group will use its patented BioKonversion technology, which cleanses the soil of hydrocarbons in a two-part process using a large machine known as the Green Machine. Several pipelines will need to be relocated, and ancient drilling rigs that have been there as long as 100 years will have to be dealt with. The cleanup cost has been estimated at between $20 million to $40 million, and will take between 18 and 36 months, depending on how deep into the ground the machines have to dig for hydrocarbons. The 90-foot by 40-foot machine processes drill cuttings, contaminated soil and drill fluids by first separating the dirt from the liquid hydrocarbons, which can be recycled or refined for resale. The remaining dirt, which still contains 3 to 7 percent oil, is then placed into a centrifuge and mixed with a heating agent and other elements, including naturally oleophilic kenaf powder. The process micronizes and absorbs hydrocarbons. Once the process is finished, the hydrocarbons are immediately non-detectable and non-leachable. The leftover benign dirt can be used as landfill cover, or mixed with road aggregate. BioKonversion can also be adapted for use on oil rigs. This article demonstrated that the process has clear advantages over traditional oilfield remediation methods such as land farming. Opportunities exist to utilize the process in Venezuela and Kuwait. 1 fig.

Guidance document for the preparation of waste management plans for the Environmental Restoration Program at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Clark, C. Jr.

1993-07-01

A project waste management (WM) plan is required for all Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) Program remedial investigation, decommission and decontamination (D ampersand D), and remedial action (RA) activities. The project WM plan describes the strategy for handling, packaging, treating, transporting, characterizing, storing, and/or disposing of waste produced as part of ORNL ER Program activities. The project WM plan also contains a strategy for ensuring worker and environmental protection during WM activities

Temporary septic holding tank at the 100-D remedial action support facility -- Engineering report. Revision 1

International Nuclear Information System (INIS)

Kelty, G.G.

1996-09-01

This document provides an engineering evaluation for the temporary septic holding tank that will be installed at the 100-D Remedial Action Support Facility at the 100-DR-1 Operable Unit in the Hanford Site. This support facility will be installed at the 100-DR-1 Operable Unit to provide office and work space for the workers involved in remediation activities of the various waste sites located at the Hanford Site

Results of Remediation and Verification Sampling for the 600-270 Horseshoe Landfill

Energy Technology Data Exchange (ETDEWEB)

W. S. Thompson

2005-12-14

This report presents the results of the 2005 remedial action and verification soil sampling conducted at the 600-270 waste site after removal of soil containing residual concentrations of dichlorodiphenyl trichloroethane and its breakdown products dichlorodiphenyl dichloroethylene and dichlorodiphenyl dichloroethane. The remediation was performed in response to post-closure surface soil sampling performed between 1998 and 2003 that indicated the presence of residual DDT contamination exceeding the Record of Decision for the 1100 Area National Priorities List site cleanup criteria of 1 mg/kg that was established for the original 1994 cleanup activities.

Results of Remediation and Verification Sampling for the 600-270 Horseshoe Landfill

International Nuclear Information System (INIS)

Thompson, W.S.

2005-01-01

This report presents the results of the 2005 remedial action and verification soil sampling conducted at the 600-270 waste site after removal of soil containing residual concentrations of dichlorodiphenyl trichloroethane and its breakdown products dichlorodiphenyl dichloroethylene and dichlorodiphenyl dichloroethane. The remediation was performed in response to post-closure surface soil sampling performed between 1998 and 2003 that indicated the presence of residual DDT contamination exceeding the Record of Decision for the 1100 Area National Priorities List site cleanup criteria of 1 mg/kg that was established for the original 1994 cleanup activities.

Close-out of open pit and waste rock piles of a uranium mine in Guangxi province of China