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Sample records for basalt waste isolation

  1. Basalt waste isolation project overview

    International Nuclear Information System (INIS)

    The proposed candidate site for a high-level nuclear waste repository is located beneath the Hanford Nuclear Reservation in southeastern Washington State. At this point, the Hanford Reservation has been selected as one of three preferred candidates in the draft environmental assessment. Project activities have concentrated on understanding the site location with respect to the 10CFR60, 40CFR191, and 10CFR960, identifying critical parameters for design of water package and repository seals, and identifying parameters for repository design. This paper describes the program to evaluate the site and to identify the natural processes that would effect isolation

  2. Site identification presentation: Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

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

  3. Technical program plan, Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project (BWIP) program as administered by the DOE's Richland Operations Office and Rockwell Hanford Operations is described. The objectives, scope and scientific technologies are discussed. The work breakdown structure of the project includes: project management and support, systems integration, geosciences, hydrology, engineered barriers, test facility design and construction, engineering testing, repository studies, and schedules. The budget of the program including operating and capital cost control is also included

  4. Technical program plan, Basalt Waste Isolation Project

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    The Basalt Waste Isolation Project (BWIP) program as administered by the DOE's Richland Operations Office and Rockwell Hanford Operations is described. The objectives, scope and scientific technologies are discussed. The work breakdown structure of the project includes: project management and support, systems integration, geosciences, hydrology, engineered barriers, test facility design and construction, engineering testing, repository studies, and schedules. The budget of the program including operating and capital cost control is also included. (DC)

  5. Basalt waste isolation project institutional activities

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project (BWIP) was established in 1976 as part of the National Waste Terminal Storage Program, and characterization studies to evaluate the Hanford Site have been ongoing since that time. In early 1983, the Nuclear Waste Policy Act (NWPA) became law and established the Office of Civilian Radioactive Waste Management, which includes the BWIP as part of that program. This paper describes the interaction process required by the NWPA and has been ongoing for the past 3 to 4 yr with the State of Washington, Yakima Indian Nation, Confederated Tribes of the Umatilla Indian Reservation, Nez Perce Tribe, other federal agencies, city and county governments, the public and news media, and many other organizations. It identifies the issues that the state and the US Department of Energy (DOE) have noted during the consultation and cooperation (C and C) process. In addition, this paper covers the site recommendation/nomination process for the first repository, including number of sites, location, and types of media being investigated. It covers the site recommendation/nomination process for the second repository, including types of media and where those investigations are being performed. Discussion covering the OCRWM program strategy, which includes documentation being prepared for site recommendation/nomination, site investigations required to determine site suitability, the licensing process for the first repository, etc., are provided

  6. Basalt Waste Isolation Program: monthly report

    Energy Technology Data Exchange (ETDEWEB)

    Deju, R A

    1978-01-31

    40 square miles were geologically mapped in the vicinity of Hanford. In the hydrologic program, testing procedures were established and preparation initiated to develop the tools needed for field testing. The waste/basalt interaction studies continued. The hydrothermal treatment experiments involving simulated waste-glass spheroids were conducted to determine the extent of alteration products. Large-volume reconnaissance experiments utilizing spent unreprocessed fuel, Hanford water, and actual basalt samples were initiated. Hydrologic Hole DC-5 was completed just below 3,500 feet. Cable tool operations at DC-8 were progressing normally, with a depth at the end of the reporting period of 428 feet. Core Hole DC-11 at Gable Mountain was completed Jan. 10 at a total depth of 385 feet. Core Hole DC-6 now has casing cemented to 1,100 feet and is being cored at 1,200 feet.

  7. Evaluation of basalt flows as a waste isolation medium

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Program within Rockwell Hanford Operations has the responsibility of conducting studies to determine the feasibility of using the basalt formations, which are in the Pacific Northwest and the Hanford Site, as a site for terminal storage of commercial nuclear waste. This program is divided into systems integration, geology, hydrology, engineered barrier studies, engineering testing, and the construction of a near-surface test facility. Brief descriptions of each task are presented

  8. Basalt Waste Isolation Project. Annual report, fiscal year 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-01

    During this fiscal year the information available in the fields of geology and hydrology of the Columbia Plateau was consolidated and two reports were issued summarizing this information. In addition, the information on engineered barriers was consolidated and a report summarizing the research to date on waste package development and design of borehole seals was prepared. The waste package studies, when combined with the hydrologic integration, revealed that even under extreme disruptive conditions, a repository in basalt with appropriately designed waste packages can serve as an excellent barrier for containment of radionuclides for the long periods of time required for waste isolation. On July 1, 1980, the first two heater tests at the Near-Surface Test Facility were started and have been successfully operated to this date. The papers on the Near-Surface Test Facility section of this report present the results of the equipment installed and the preliminary results of the testing. In October 1979, the US Department of Energy selected the joint venture of Kaiser Engineers/Parsons Brinckerhoff Quade and Douglas, Inc., to be the architect-engineer to produce a conceptual design of a repository in basalt. During the year, this design has progressed and concept selection has now been completed. This annual report presents a summary of the highlights of the work completed during fiscal year 1980. It is intended to supplement and summarize the nearly 200 papers and reports that have been distributed to date as a part of the Basalt Waste Isolation Project studies.

  9. Basalt Waste Isolation Project. Annual report, fiscal year 1980

    International Nuclear Information System (INIS)

    During this fiscal year the information available in the fields of geology and hydrology of the Columbia Plateau was consolidated and two reports were issued summarizing this information. In addition, the information on engineered barriers was consolidated and a report summarizing the research to date on waste package development and design of borehole seals was prepared. The waste package studies, when combined with the hydrologic integration, revealed that even under extreme disruptive conditions, a repository in basalt with appropriately designed waste packages can serve as an excellent barrier for containment of radionuclides for the long periods of time required for waste isolation. On July 1, 1980, the first two heater tests at the Near-Surface Test Facility were started and have been successfully operated to this date. The papers on the Near-Surface Test Facility section of this report present the results of the equipment installed and the preliminary results of the testing. In October 1979, the US Department of Energy selected the joint venture of Kaiser Engineers/Parsons Brinckerhoff Quade and Douglas, Inc., to be the architect-engineer to produce a conceptual design of a repository in basalt. During the year, this design has progressed and concept selection has now been completed. This annual report presents a summary of the highlights of the work completed during fiscal year 1980. It is intended to supplement and summarize the nearly 200 papers and reports that have been distributed to date as a part of the Basalt Waste Isolation Project studies

  10. Basalt Waste Isolation Project exploratory shaft site: Final reclamation report

    International Nuclear Information System (INIS)

    The restoration of areas disturbed by activities of the Basalt Waste Isolation Project (BWIP) constitutes a unique operation at the US Department of Energy's (DOE) Hanford Site, both from the standpoint of restoration objectives and the time frame for accomplishing these objectives. The BWIP reclamation program comprises three separate projects: borehole reclamation, Near Surface Test Facility (NSTF) reclamation, and Exploratory Shaft Facility (ESF) reclamation. The main focus of this report is on determining the success of the revegetation effort 1 year after work was completed. This report also provides a brief overview of the ESF reclamation program. 21 refs., 7 figs., 14 tabs

  11. Environmental issue identification for the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    A preliminary evaluation of environmental issues is provided in this report. It contains summary of the thought process that was used during the area characterization studies for a geological repository for high-level radioactive wastes. Environmental issues are discussed separately for construction, operation, and long term isolation aspects of a repository in basalt. During construction the primary environmental concerns are public perception and water resources; intermediate concerns are air quality, ecosystems, physical resources, and cultural and social resources. During operation, the primary environmental issues concern the transport of radioactive materials and physical resources. Long term environmental issues envolve water resources and borehole plugging

  12. Underground engineering at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    A special task group was organized by the US National Committee for Rock Mechanics and the Board on Radioactive Waste Management of the National Research Council to address issues relating to the geotechnical site characterization program for an underground facility to house high-level radioactive waste of the Basalt Waste Isolation Project (BWIP). Intended to provide an overview of the geotechnical program, the study was carried out by a task group consisting of ten members with expertise in the many disciplines required to successfully complete such a project. The task group recognized from the outset that the short time frame of this study would limit its ability to address all geotechnical issues in detail. Geotechnical issues were considered to range from specific technical aspects such as in-situ testing for rock mass permeability; rock hardness testing in the laboratory; or geologic characterizations and quantification of joints, to broader aspects of design philosophy, data collection, and treatment of uncertainty. The task group chose to focus on the broader aspects of underground design and construction, recognizing that the BWIP program utilizes a peer review group on a regular basis which reviews the specific technical questions related to geotechnical engineering. In this way, it was hoped that the review provided by the task group would complement those prepared by the BWIP peer review group

  13. Briefing to US Nuclear Regulatory Commission - staff Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    Items covered in the briefing include issues, work elements and data needs in the basalt waste isolation project, site data in site characterization report (SCR), geology and hydrology, waste package and geochemistry data in SCR, performance assessment, near-surface test facility, hydrofracturing, repository design in basalt, drilling and testing, in-situ testing

  14. Interim reclamation report, Basalt Waste Isolation project: Boreholes, 1989

    International Nuclear Information System (INIS)

    In 1968, a program was started to assess the feasibility of storing Hanford Site defense waste in deep caverns constructed in basalt. This program was expanded in 1976 to include investigations of the Hanford Site as a potential location for a mined commercial nuclear waste repository. An extensive site characterization program was begun to determine the feasibility of using the basalts beneath the Hanford Site for the repository. Site research focused primarily on determining the direction and speed of groundwater movement, the uniformity of basalt layers, and tectonic stability. Some 98 boreholes were sited, drilled, deepened, or modified by BWIP between 1977 and 1988 to test the geologic properties of the Site. On December 22, 1987, President Reagan signed into law the Nuclear Waste Policy Amendments Act of 1987, which effectively stopped all repository-related activities except reclamation of disturbed lands at the Hanford Site. This report describes the development of the reclamation program for the BWIP boreholes, its implementation, and preliminary estimates of its success. The goal of the reclamation program is to return sites disturbed by the repository program as nearly as practicable to their original conditions using native plant species. 48 refs., 28 figs., 14 tabs

  15. Interim reclamation report, Basalt Waste Isolation project: Boreholes, 1989

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-03-01

    In 1968, a program was started to assess the feasibility of storing Hanford Site defense waste in deep caverns constructed in basalt. This program was expanded in 1976 to include investigations of the Hanford Site as a potential location for a mined commercial nuclear waste repository. An extensive site characterization program was begun to determine the feasibility of using the basalts beneath the Hanford Site for the repository. Site research focused primarily on determining the direction and speed of groundwater movement, the uniformity of basalt layers, and tectonic stability. Some 98 boreholes were sited, drilled, deepened, or modified by BWIP between 1977 and 1988 to test the geologic properties of the Site. On December 22, 1987, President Reagan signed into law the Nuclear Waste Policy Amendments Act of 1987, which effectively stopped all repository-related activities except reclamation of disturbed lands at the Hanford Site. This report describes the development of the reclamation program for the BWIP boreholes, its implementation, and preliminary estimates of its success. The goal of the reclamation program is to return sites disturbed by the repository program as nearly as practicable to their original conditions using native plant species. 48 refs., 28 figs., 14 tabs.

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

    International Nuclear Information System (INIS)

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

  17. Basalt Waste Isolation Project. Quarterly report, July 1, 1981-September 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Deju, R.A.

    1981-11-01

    This document reports progress made in the Basalt Waste Isolation Project during the fourth quarter of fiscal year 1981. Efforts are described for the following programs of the project work breakdown structure: systems, waste package, site, repository, regulatory and institutional, test facilities, and in-situ test facilities.

  18. Basalt Waste Isolation Project. Annual report, fiscal year 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-11-01

    This project is aimed at examining the feasibility and providing the technology to design and construct a radwaste repository in basalt formations beneath and within the Hanford Site. The project is divided into seven areas: systems integration, geosciences, hydrologic studies, engineered barriers, near-surface test facility, engineering testing, and repository engineering. This annual report summarizes key investigations in these seven areas. (DLC)

  19. Basalt Waste Isolation Project. Annual report, fiscal year 1979

    International Nuclear Information System (INIS)

    This project is aimed at examining the feasibility and providing the technology to design and construct a radwaste repository in basalt formations beneath and within the Hanford Site. The project is divided into seven areas: systems integration, geosciences, hydrologic studies, engineered barriers, near-surface test facility, engineering testing, and repository engineering. This annual report summarizes key investigations in these seven areas

  20. Performance allocation traceable to regulatory criteria as applied to site characterization work at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project has developed a method for defining in detail the work required to demonstrate the feasibility of emplacing and providing for the safe isolation of nuclear wastes in a repository in the deep basalts at the Hanford Site near Richland, Washington. Criteria analysis allows the identification of areas of significant technical uncertainty or controversy that can be highlighted as issues. A preliminary analysis has been conducted, which, by identifying key radionuclides and allocating performance among the multiple barriers in a repository constructed in a basalt, allows the design and development testing activities at the Basalt Waste Isolation Project to be put into perspective. Application of sophisticated uncertainty analysis techniques will allow refinements in the analysis to be made and to further guide characterization and testing activities. Preliminary results suggest that a repository constructed in basalt will provide for the safe isolation of nuclear wastes in a cost-effective and reliable manner with a high degree of confidence

  1. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

    Energy Technology Data Exchange (ETDEWEB)

    1978-04-01

    This volume, Y/OWI/TM-36/7 Baseline Rock Properties--Basalt, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report contains an evaluation of the results of a literature survey to define the rock mass properties of a generic basalt, which could be considered as a geological medium for storing radioactive waste. The general formation and structure of basaltic rocks is described. This is followed by specific descriptions and rock property data for the Dresser Basalt, the Amchitka Island Basalt, the Nevada Test Site Basalt and the Columbia River Group Basalt. Engineering judgment has been used to derive the rock mass properties of a typical basalt from the relevant intact rock property data and the geological information pertaining to structural defects, such as joints and faults.

  2. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

    International Nuclear Information System (INIS)

    This volume, Y/OWI/TM-36/7 Baseline Rock Properties--Basalt, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report contains an evaluation of the results of a literature survey to define the rock mass properties of a generic basalt, which could be considered as a geological medium for storing radioactive waste. The general formation and structure of basaltic rocks is described. This is followed by specific descriptions and rock property data for the Dresser Basalt, the Amchitka Island Basalt, the Nevada Test Site Basalt and the Columbia River Group Basalt. Engineering judgment has been used to derive the rock mass properties of a typical basalt from the relevant intact rock property data and the geological information pertaining to structural defects, such as joints and faults

  3. The Basalt Waste Isolation Project technical program evaluation process: A criteria-based method

    International Nuclear Information System (INIS)

    The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the BWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (NWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP will be further formalized and further applied to the review of BWIP technical activities

  4. Hydrogeologic testing strategy for the Basalt Waste Isolation Project site

    International Nuclear Information System (INIS)

    At the time of licensing for a proposed deep geologic repository for high-level nuclear waste, the Department of Energy (DOE) has the responsibility to present and defend a complete licensing/performance assessment of the geologic repository system. As part of its responsibilities, the Nuclear Regulatory Commission (NRC) staff will be required to perform an independent assessment of the groundwater flow system with respect to the technical criteria of 10 Code of Federal Regulations (CFR) Part 60. Specifically, the staff expects to use mathematical models to predict pre-emplacement and post-emplacement groundwater flow paths and travel times. These predictive assessments will be used to reach findings on compliance with the proposed EPA Standards (10 CFR 60.112), which apply to post-emplacement groundwater travel time along the path of likely radionuclide travel (10 CFR 60.113(2)). Predictive modeling of groundwater flow will require defensible conceptual models of the flow system, defensible boundary conditions, and defensible values of hydraulic parameters. The purpose fo this technical position is to provide guidance to DOE on an approach that the NRC staff considers acceptable in determining what hydrogeologic testing (including types of tests, scale of tests, and number of tests) at the Hanford site will be required to produce the hydraulic data necessary and sufficient to perform rigorous, quantitative modeling to support predictions of repository performance. 2 figures

  5. Project characteristics monitoring report: BWIP (Basalt Waste Isolation Program) repository project

    Energy Technology Data Exchange (ETDEWEB)

    Friedli, E.A.; Herborn, D.I.; Taylor, C.D.; Tomlinson, K.M.

    1988-03-01

    This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs.

  6. Project characteristics monitoring report: BWIP [Basalt Waste Isolation Program] repository project

    International Nuclear Information System (INIS)

    This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs

  7. Basalt Waste Isolation Project. Quarterly report, January 1-March 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Deju, R.A.

    1980-04-01

    This report addresses the technical progress for the Basalt Waste Isolation Project for the second quarter of fiscal year 1980. Seismic design values were developed for preliminary repository design purposes; 0.25 g horizontal and 0.125 g vertical maximum accelerations for surface, zero-period conditions. Preliminary seismic data indicate broad, smooth areas exist in the bedrock surface in the western portion of the Cold Creek syncline and a gently undulating bedrock surface in the eastern portion. Test results indicate hydraulic property values fall within the range previously reported for sedimentary and interflow zones in basalt formations at the Hanford Site. Preliminary results of available hydrochemical data obtained from several borehole sites indicate that little, if any, vertical mixing of groundwaters is taking place across this stratigraphic boundary. Multiple barrier studies indicate that the primary candidate canister/overpack alloys are TiCode-12, Inconel 625, Incoloy 825, and Zircaloy 2. Low-carbon steel and cast iron are among the list of secondary candidate canister alloys. Laboratory tests of borehole plug designs have shown that it is feasible to design a composite plug system that will satisfactorily seal a nuclear waste repository in Columbia River basalt. The National Lead Industries, Inc., NLI-1/2 Universal Spent Fuel Shipping Cask was selected for use in Phase II operations. Creep test results of samples of Umtanum basalt from borehole DC-6 were plotted and show the day-to-day variation in deformation versus time. The concept selection phase of repository conceptual design was completed in March 1980. A test plan for the Exploratory Shaft Test Facility was developed and is scheduled for submittal to the US Department of Energy in May 1980.

  8. Basalt Waste Isolation Program. Quarterly report, April 1, 1979-June 30, 1979

    International Nuclear Information System (INIS)

    During the quarter, progress was made in all areas of the Basalt Waste Isolation Program. In the Geosciences, Hydrology, and Engineered Barriers areas, work continued on schedule aimed at being able to make a site selection decision in 1981, as scheduled. Emphasis continued to be placed on geologic mapping studies, on hydrologic data gathering, and on definition of waste/basalt interactions and needed engineered barriers. Progress at the end of the quarter on the Near-Surface Test Facility was approximately on schedule and the rate of work was accelerating to better than scheduled due to some equipment improvements and tunnel design modifications. In the Engineering Testing area, design work, test planning, and fabrication of heaters and auxiliary equipment continued on schedule. In the Repository area, an Architect/Engineer Evaluation Board was formally designed by the US Department of Energy-Headquarters during October 1978. The evaluation board will select an architect/engineer for repository conceptual design with an option for follow-on Title I, Title II, and Title III engineering services. Selection will be completed by October 1979. Questionnaire information was received from a number of interested architect/engineer firms by the US Department of Energy-Richland Operations Office and has been evaluated. Onsite visits with the qualified firms were completed during April 1979. In addition, repository preconceptual design studies continued on schedule with emphasis on compilation of repository functional design criteria by July 1979, and the repository preconceptual design report in September 1979

  9. Assessment of environmental corrosion effects on Basalt Waste Isolation Project exploratory shaft liner

    International Nuclear Information System (INIS)

    As part of the Basalt Waste Isolation Project (BWIP), two Exploratory Shafts, called ES I and ES II, will be sunk to a depth of 3400 ft by the blind boring method. The shafts' steel liners will have a design life of ∼100 years. The carbon steel and the high-strength low-alloy steel (ASTM A588) materials to be used are expected to be exposed to a moist air atmosphere on the interior liner surface that will result in a zone continuous wetting. The exterior surface of the liners will be exposed to a layer of grout and possibly groundwater, should there be a discontinuity in the grout. A set of environmental conditions were selected and corrosion rate studies were performed on carbon steel and high-strength low-alloy steel, to evaluate possible corrosion effects. 21 refs., 5 figs

  10. Community interviews task report: Working draft: BWIP [Basalt Waste Isolation Project] Repository Project

    International Nuclear Information System (INIS)

    The socioeconomic program for the Basalt Waste Isolation Project (BWIP) requires the collection of information about economic, social and cultural conditions, demographic, housing and settlement patterns, and the provision of public services and facilities in order to monitor and assess the impacts of the project on the study area. Much of the information needed by the socioeconomic program is compiled, maintained, and used by officials or staff members of local, regional, state, or tribal agencies or organizations. Because much of this information is prepared for internal use, the documents are often not published or advertised and it can be difficult for researchers to identify many obscure, yet useful, sources of information. In order to identify and gain access to this information, it is often most efficient to talk directly with officials and staff members of pertinent agencies or organizations who may have knowledge of these documents or who may have useful information themselves. Consequently, interviews in the study communities with persons knowledgeable about the socioeconomic or sociocultural characteristics of the area constitute an important source of data for the socioeconomic program. In addition to identifying various data sources, these interviews provide a mechanism for understanding and interpreting those data. Knowledge of specific local conditions is often necessary to correctly interpret quantitative data. The purpose of this paper is to summarize the objectives of the community interviews task and the general methods that will be used in conducting the community interviews. 3 refs

  11. Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington Site. Main report and Appendices A through D

    International Nuclear Information System (INIS)

    On November 12, 1982, the US Department of Energy submitted to the US Nuclear Regulatory Commission the Site Characterization Report for the Basalt Waste Isolation Project (DOE/RL 82-3). The Basalt Waste Isolation Project is located on DOE's Hanford Reservation in the State of Washington. NUREG-0960 contains the detailed analysis, by the NRC staff, of the site characterization report. Supporting technical material is contained in Appendices A through W

  12. A review of drilled shaft sealing for the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    Questions have been raised concerning the ability of the drillers of the exploratory shaft for the Basalt Waste Isolation program to develop an effective seal against water inflow down the annular space between the shaft casing and shaft wall into the mined chambers. We understand the need for shaft integrity and the concern of those responsible for the shaft planning. The purpose of this report is to give documentation to allay the fears of those who may have questions remaining in their minds concerning the prospects for a dry shaft. Included in this report are discussions of five projects where shaft sealing was effective in drilled shafts and one project where the material which is recommended for the exploratory shaft was used effectively in a conventional shaft. Also discussed is the recommended multitier approach toward shaft sealing which will, if adopted, use all of the current state of the art techniques to assure the watertightness of the shaft. It should be pointed out that none of the projects described here used all of the safeguards which are recommended in this program. If any of the materials and procedures recommended here are omitted, then of course the possibility increases for water migration through the casing-borehole annulus. It is our considered opinion that if the program recommended is adopted there will be no water inflow into the shaft, but if we are wrong or if, through human error, the program is not executed correctly, that we have devices and procedures available to us which will facilitate remedial work to perfect seal in the shaft. 4 refs., 3 figs., 1 tab

  13. Elk and deer studies related to the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    A study of elk (Cervus elaphus) and deer (Odocoileus hemionus) was conducted in the vicinity of planned site characterization activities for the Basalt Waste Isolation Project (BWIP). Both species are known to be sensitive to disturbance and are considered important species because they are recreationally and/or commercially valuable. The principal objectives of the study were to (1) estimate pre-activity (site characterization) recruitment of deer and elk, (2) characterize deer and elk use of limited habitats critical to their survival (e.g., riparian areas), (3) describe preferential habitat use by deer and elk during critical seasons (i.e., winter and summer), and (4) document pre-activity distributions of seasonal home range centers of deer and elk. Early termination of BWIP prevented some of the objectives from being fully addressed. Fifteen adult elk (11 females and 4 males) and 19 female deer equipped with radio transmitters were studied on the Arid Lands Ecology (ALE) Reserve from February through December 1987. More than 1800 relocations of the marked elk and deer were made during aerial and ground tracking sessions. Deer confined their activities to within 2 km of water sources. In contrast, elk used 6-12 times the average area used by deer. As with deer, female elk were closely associated with available water sources during the summer and fall, presumably because of the physiological demands of lactation. However, during the winter, female elk showed no preference for areas near water, as did male elk throughout the study. Riparian areas, which are scarce on the arid Hanford Site, are particularly valuable habitat to both elk and deer because they provide drinking water and succulent forage during the dry summer and early fall months

  14. Demonstration of a performance assessment methodology for nuclear waste isolation in basalt formations

    International Nuclear Information System (INIS)

    This paper summarizes the results of the demonstration of a performance assessment methodology developed by Sandia National Laboratories, Albuquerque for the US Nuclear Regulatory Commission for use in the analysis of high-level radioactive waste disposal in deep basalts. Seven scenarios that could affect the performance of a repository in basalts were analyzed. One of these scenarios, normal ground-water flow, was called the base-case scenario. This was used to demonstrate the modeling capabilities in the methodology necessary to assess compliance with the ground-water travel time criterion. The scenario analysis consisted of both scenario screening and consequence modeling. Preliminary analyses of scenarios considering heat released from the waste and the alteration of the hydraulic properties of the rock mass due to loads created by a glacier suggested that these effects would not be significant. The analysis of other scenarios indicated that those changing the flow field in the vicinity of the repository would have an impact on radionuclide discharges, while changes far from the repository may not be significant. The analysis of the base-case scenario was used to show the importance of matrix diffusion as a radionuclide retardation mechanism in fractured media. The demonstration of the methodology also included an overall sensitivity analysis to identify important parameters and/or processes. 15 refs., 13 figs., 2 tabs

  15. Geother evaluation and improvement: A progress report including test cases for two-dimensional BWIP (Basalt Waste Isolation Project) analysis

    Energy Technology Data Exchange (ETDEWEB)

    Bian, S.H.; Budden, M.J.; Bartley, C.L.; Yung, S.C.

    1988-03-01

    The objective of the work is to evaluate the GEOTHER code and peform necessary improvements to make it specifically suitable for predicting the environmental conditions of the waste package for the Basalt Waste Isolation Project (BWIP); and to perform resaturation analyses, that is, the analyses of steam formation and condensation, for the repository and waste package using the improved GEOTHER code. This is a progress report to BWIP documenting the status of GEOTHER code testing, evaluation, and improvements. The computational results documented in this report reflect the current condition of the code and the condition before code improvements. The test cases used are intended for examining the code features in sufficient detail and are not intended to be taken as final conclusions for BWIP applications.

  16. Site characterization report for the basalt waste isolation project. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-11-01

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment.

  17. Site characterization report for the basalt waste isolation project. Volume II

    International Nuclear Information System (INIS)

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment

  18. Site characterization report for the basalt waste isolation project. Volume III

    International Nuclear Information System (INIS)

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 3 contains chapters 13 through 19: site issues and plans; geoengineering and repository design issues and plans; waste package and site geochemistry issues and plans; performance-assessment issues and plans; site characterization program; quality assurance; and identification of alternate sites

  19. Site characterization report for the basalt waste isolation project. Volume I

    International Nuclear Information System (INIS)

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 1 contains chapters 1 through 5: introduction; decision process for choosing a reference repository location and an alternate repository location; geologic description of the reference repository location and the surrounding area; geoengineering; and hydrogeology;

  20. Techniques for measuring the vertical hydraulic conductivity of flood basalts at the Basalt Waste Isolation Project site

    Energy Technology Data Exchange (ETDEWEB)

    Javandel, I.

    1983-06-01

    A regional model that can predict groundwater movement through the reference repository location and surrounding area is essential to assessing the site suitability for a nuclear waste repository. During the last two decades, several models have been developed to handle complicated flow patterns through complex geologic materials. The basic problem, however, is obtaining the data base needed to apply these models. The hydrological data needed include the spatial distribution of effective porosity, the hydraulic conductivity tensor and its variation in space, values of specific storage, the hydraulic head distribution, and the fluid properties. In this report, we discuss conventional methods of obtaining vertical hydraulic conductivity and examine their applicability to the BWIP site. 39 references, 12 figures, 4 tables.

  1. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 14. Repository preconceptual design studies: basalt

    International Nuclear Information System (INIS)

    This document describes a preconceptual design for a nuclear waste storage facility in basalt. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/15, ''Drawings for Repository Preconceptual Design Studies: Basalt.''

  2. Hydrothermal conditions and resaturation times in underground openings for a nuclear waste repository in the Umtanum flow at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    Numerical simulation techniques have been used to study heat flow and pore fluid migration in the near field of storage tunnels and canister storage holes in a proposed high-level nuclear waste repository in the Umtanum Basalt at the Basalt Waste Isolation Project site at Hanford, Washington. Particular emphasis was placed on evaluating boiling conditions in the host rock. Sensitivity studies were performed to determine the influence of variations in critical site-specific parameters which are not presently accurately known. The results indicate that, even when rather extreme values are assumed for key hydrothermal parameters, the volume of rock dried by boiling of pore fluids is negligible compared to the volume of excavated openings. The time required for saturation of backfilling materials is thus controlled by the volume of the mined excavations. When realistic values for the parameters of the natural and man-made systems are used resaturation is predicted to occur within less than two years after backfilling is placed. The approximations used in the analyses, and their limitations, are discussed in the body of the report. Recommendations are made for additional studies of the thermohydrological behavior of a high-level nuclear waste repository. 31 references, 76 figures, 7 tables

  3. Proposed methodology for completion of scenario analysis for the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    This report presents the methodology to complete an assessment of postclosure performance, considering all credible scenarios, including the nominal case, for a proposed repository for high-level nuclear waste at the Hanford Site, Washington State. The methodology consists of defensible techniques for identifying and screening scenarios, and for then assessing the risks associated with each. The results of the scenario analysis are used to comprehensively determine system performance and/or risk for evaluation of compliance with postclosure performance criteria (10 CFR 60 and 40 CFR 191). In addition to describing the proposed methodology, this report reviews available methodologies for scenario analysis, discusses pertinent performance assessment and uncertainty concepts, advises how to implement the methodology (including the organizational requirements and a description of tasks) and recommends how to use the methodology in guiding future site characterization, analysis, and engineered subsystem design work. 36 refs., 24 figs., 1 tab

  4. AEGIS technology demonstration for a nuclear waste repository in basalt. Assessment of effectiveness of geologic isolation systems

    Energy Technology Data Exchange (ETDEWEB)

    Dove, F.H.; Cole, C.R.; Foley, M.G.

    1982-09-01

    A technology demonstration of current performance assessment techniques as applied to a nuclear waste repository in the Columbia Plateau Basalts was conducted. Hypothetical repository coordinates were selected for an actual geographical setting on the Hanford Reservation in the state of Washington. Published hydrologic and geologic data used in the analyses were gathered in 1979 or earlier. The following report documents the technology demonstration in basalt. Available information has been used to establish the data base and initial hydrologic and geologic interpretations for this site-specific application. A simplified diagram of the AEGIS analyses is shown. Because an understanding of the dynamics of ground-water flow is essential to the development of release scenarios and consequence analyses, a key step in the demonstration is the systems characterization contained in the conceptual model. Regional and local ground-water movement patterns have been defined with the aid of hydrologic computer models. Hypothetical release scenarios have been developed and evaluated by a process involving expert opinion and a Geologic Simulation Model for basalt. (The Geologic Simulation Model can also be used to forecast future boundary conditions for the hydrologic simulation.) Chemical reactivity of the basalt with ground water will influence the leaching and transport of radionuclides; solubility equilibria based on available data are estimated with geochemical models. After the radionuclide concentrations are mathematically introduced into the ground-water movement patterns, waste movement patterns are outlined over elapsed time. Contaminant transport results are summarized for significant radionuclides that are hypothetically released to the accessible environment and to the biosphere.

  5. AEGIS technology demonstration for a nuclear waste repository in basalt. Assessment of effectiveness of geologic isolation systems

    International Nuclear Information System (INIS)

    A technology demonstration of current performance assessment techniques as applied to a nuclear waste repository in the Columbia Plateau Basalts was conducted. Hypothetical repository coordinates were selected for an actual geographical setting on the Hanford Reservation in the state of Washington. Published hydrologic and geologic data used in the analyses were gathered in 1979 or earlier. The following report documents the technology demonstration in basalt. Available information has been used to establish the data base and initial hydrologic and geologic interpretations for this site-specific application. A simplified diagram of the AEGIS analyses is shown. Because an understanding of the dynamics of ground-water flow is essential to the development of release scenarios and consequence analyses, a key step in the demonstration is the systems characterization contained in the conceptual model. Regional and local ground-water movement patterns have been defined with the aid of hydrologic computer models. Hypothetical release scenarios have been developed and evaluated by a process involving expert opinion and a Geologic Simulation Model for basalt. (The Geologic Simulation Model can also be used to forecast future boundary conditions for the hydrologic simulation.) Chemical reactivity of the basalt with ground water will influence the leaching and transport of radionuclides; solubility equilibria based on available data are estimated with geochemical models. After the radionuclide concentrations are mathematically introduced into the ground-water movement patterns, waste movement patterns are outlined over elapsed time. Contaminant transport results are summarized for significant radionuclides that are hypothetically released to the accessible environment and to the biosphere

  6. The AEGIS technology demonstration for a nuclear waste repository in basalt. Assessment of effectiveness of geologic isolation systems

    Science.gov (United States)

    Dove, F. H.; Cole, C. R.; Foley, M. G.

    1982-09-01

    A technology demonstration of performance assessment techniques as applied to a nuclear waste repository in the Columbia Plateau Basalts was conducted. Hypothetical repository coordinates were selected for an acutal geographical setting on the Hanford Reservation in the state of Washington. Available information was used to establish the data base and initial hydrologic and geologic interpretations for this site-specific application. A simplified diagram of the AEGIS analyses is shown. Because an understanding of the dynamics of ground water flow is essential to the development of release scenarios and consequence analyses, a key step in the demonstration is the systems characterization contained in the conceputal model. Regional and local ground water movement patterns were defined with the aid of hydrologic computer models.

  7. Probability encoding of hydrologic parameters for basalt. Elicitation of expert opinions from a panel of three basalt waste isolation project staff hydrologists

    International Nuclear Information System (INIS)

    The present study implemented a probability encoding method to estimate the probability distributions of selected hydrologic variables for the Cohassett basalt flow top and flow interior, and the anisotropy ratio of the interior of the Cohassett basalt flow beneath the Hanford Site. Site-speciic data for these hydrologic parameters are currently inadequate for the purpose of preliminary assessment of candidate repository performance. However, this information is required to complete preliminary performance assessment studies. Rockwell chose a probability encoding method developed by SRI International to generate credible and auditable estimates of the probability distributions of effective porosity and hydraulic conductivity anisotropy. The results indicate significant differences of opinion among the experts. This was especially true of the values of the effective porosity of the Cohassett basalt flow interior for which estimates differ by more than five orders of magnitude. The experts are in greater agreement about the values of effective porosity of the Cohassett basalt flow top; their estimates for this variable are generally within one to two orders of magnitiude of each other. For anisotropy ratio, the expert estimates are generally within two or three orders of magnitude of each other. Based on this study, the Rockwell hydrologists estimate the effective porosity of the Cohassett basalt flow top to be generally higher than do the independent experts. For the effective porosity of the Cohassett basalt flow top, the estimates of the Rockwell hydrologists indicate a smaller uncertainty than do the estimates of the independent experts. On the other hand, for the effective porosity and anisotropy ratio of the Cohassett basalt flow interior, the estimates of the Rockwell hydrologists indicate a larger uncertainty than do the estimates of the independent experts

  8. Probability encoding of hydrologic parameters for basalt. Elicitation of expert opinions from a panel of three basalt waste isolation project staff hydrologists

    Energy Technology Data Exchange (ETDEWEB)

    Runchal, A.K.; Merkhofer, M.W.; Olmsted, E.; Davis, J.D.

    1984-11-01

    The present study implemented a probability encoding method to estimate the probability distributions of selected hydrologic variables for the Cohassett basalt flow top and flow interior, and the anisotropy ratio of the interior of the Cohassett basalt flow beneath the Hanford Site. Site-speciic data for these hydrologic parameters are currently inadequate for the purpose of preliminary assessment of candidate repository performance. However, this information is required to complete preliminary performance assessment studies. Rockwell chose a probability encoding method developed by SRI International to generate credible and auditable estimates of the probability distributions of effective porosity and hydraulic conductivity anisotropy. The results indicate significant differences of opinion among the experts. This was especially true of the values of the effective porosity of the Cohassett basalt flow interior for which estimates differ by more than five orders of magnitude. The experts are in greater agreement about the values of effective porosity of the Cohassett basalt flow top; their estimates for this variable are generally within one to two orders of magnitiude of each other. For anisotropy ratio, the expert estimates are generally within two or three orders of magnitude of each other. Based on this study, the Rockwell hydrologists estimate the effective porosity of the Cohassett basalt flow top to be generally higher than do the independent experts. For the effective porosity of the Cohassett basalt flow top, the estimates of the Rockwell hydrologists indicate a smaller uncertainty than do the estimates of the independent experts. On the other hand, for the effective porosity and anisotropy ratio of the Cohassett basalt flow interior, the estimates of the Rockwell hydrologists indicate a larger uncertainty than do the estimates of the independent experts.

  9. Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge

    International Nuclear Information System (INIS)

    This document represents a compilation of data and interpretive studies conducted as part of the engineered barriers program of the Basalt Waste Isolation Project. The overall objective of these studies is to provide information on barrier system designs, emplacement and isolation techniques, and chemical reactions expected in a nuclear waste repository located in the basalts underlying the Hanford Site within the state of Washington. Backfills, waste-basalt interactions, sorption, borehole plugging, etc., are among the topics discussed

  10. Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge

    Energy Technology Data Exchange (ETDEWEB)

    Smith, M.J.

    1980-05-01

    This document represents a compilation of data and interpretive studies conducted as part of the engineered barriers program of the Basalt Waste Isolation Project. The overall objective of these studies is to provide information on barrier system designs, emplacement and isolation techniques, and chemical reactions expected in a nuclear waste repository located in the basalts underlying the Hanford Site within the state of Washington. Backfills, waste-basalt interactions, sorption, borehole plugging, etc., are among the topics discussed.

  11. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 3. Stratigraphies of salt, granite, shale, and basalt

    International Nuclear Information System (INIS)

    This study presents the methodology and basic literature used to develop generic stratigraphic sections for the various geologic repository host rocks under considerations: salt, granite, shale and basalt

  12. Nuclear waste repository in basalt: preconceptual design guidelines

    International Nuclear Information System (INIS)

    The development of the basalt waste isolation program parallels the growing need for permanent, environmentally safe, and secure means to store nuclear wastes. The repository will be located within the Columbia Plateau basalt formations where these ends can be met and radiological waste can be stored. These wastes will be stored such that the wastes may be retrieved from storage for a period after placement. After the retrieval period, the storage locations will be prepared for terminal storage. The terminal storage requirements will include decommissioning provisions. The facility boundaries will encompass no more than several square miles of land which will be above a subsurface area where the geologic makeup is primarily deep basaltic rock. The repository will receive, from an encapsulation site(s), nuclear waste in the form of canisters (not more than 18.5 feet x 16 inches in diameter) and containers (55-gallon drums). Canisters will contain spent fuel (after an interim 5-year storage period), solidified high-level wastes (HLW), or intermediate-level wastes (ILW). The containers (drums) will package the low-level transuranic wastes (LL-TRU). The storage capacity of the repository will be expanded in a time-phased program which will require that subsurface development (repository expansion) be conducted concurrently with waste storage operations. The repository will be designed to store the nuclear waste generated within the predictable future and to allow for reasonable expansion. The development and assurance of safe waste isolation is of paramount importance. All activities will be dedicated to the protection of public health and the environment. The repository will be licensed by the US Nuclear Regulatory Commission (NRC). Extensive efforts will be made to assure selection of a suitable site which will provide adequate isolation

  13. Assessing social and economic effects of perceived risk: Workshop summary: Draft: BWIP Repository Project. [Basalt Waste Isolation Program

    Energy Technology Data Exchange (ETDEWEB)

    Nealey, S.M.; Liebow, E.B. (eds.)

    1988-03-01

    The US Department of Energy sponsored a one-day workshop to discuss the complex dimensions of risk judgment formation and the assessment of social and economic effects of risk perceptions related to the permanent underground storage of highly radioactive waste from commercial nuclear power plants. Affected parties have publicly expressed concerns about potentially significant risk-related effects of this approach to waste management. A selective review of relevant literature in psychology, decision analysis, economics, sociology, and anthropology was completed, along with an examination of decision analysis techniques that might assist in developing suitable responses to public risk-related concerns. The workshop was organized as a forum in which a set of distinguished experts could exchange ideas and observations about the problems of characterizing the effects of risk judgments. Out of the exchange emerged the issues or themes of problems with probabilistic risk assessment techniques are evident; differences exist in the way experts and laypersons view risk, and this leads to higher levels of public concern than experts feel are justified; experts, risk managers, and decision-makers sometimes err in assessing risk and in dealing with the public; credibility and trust are important contributing factors in the formation of risk judgments; social and economic consequences of perceived risk should be properly anticipated; improvements can be made in informing the public about risk; the role of the public in risk assessment, risk management and decisions about risk should be reconsidered; and mitigation and compensation are central to resolving conflicts arising from divergent risk judgments. 1 tab.

  14. Basalt nuclear-waste repository remote sensing using electromagnetic techniques

    International Nuclear Information System (INIS)

    The electromagnetic permittivity and attenuation rate of basalt, from the Near Surface Test Facility of the Basalt Waste Isolation Project at Hanford, Washington, have been measured in the laboratory as a function of water content at frequencies from 25 MHz to 1000 MHz. Both the permittivity and the attenuation rate are strongly related to water content of basalt in this frequency range. Completely dehydrated, the rock has a frequency-independent relative permittivity of about 8 and attenuation rates (inverse skin depths) of 0.04 m-1 and 3.2 m-1 at 25 MHz and 1000 MHz, respectively. When completely saturated by tap water to 6% by volume, the relative permittivity ranges from 16.5 to 10.0 and the attenuation ranges from 0.3 m-1 to 5.5 m-1 between 25 MHz and 1000 MHz. The data indicate that high-frequency electromagnetic remote sensing techniques, such as those used in radar, cross-borehole tomography, and borehole logging, may be useful in characterizing proposed basalt repositories and monitoring established waste repositories. Electromagnetic methods are particularly suited to delineating water content of the rock and, when completely saturated, crack and pore porosity of the rock mass within a repository. 7 references, 3 figures

  15. Nanoparticulate mineral matter from basalt dust wastes.

    Science.gov (United States)

    Dalmora, Adilson C; Ramos, Claudete G; Querol, Xavier; Kautzmann, Rubens M; Oliveira, Marcos L S; Taffarel, Silvio R; Moreno, Teresa; Silva, Luis F O

    2016-02-01

    Ultra-fine and nano-particles derived from basalt dust wastes (BDW) during "stonemeal" soil fertilizer application have been the subject of some concern recently around the world for their possible adverse effects on human health and environmental pollution. Samples of BDW utilized were obtained from companies in the mining district of Nova Prata in southern Brazil for chemical characterization and nano-mineralogy investigation, using an integrated application of advanced characterization techniques such as X-ray diffraction (XRD), High Resolution-Transmission Electron microscopy (HR-TEM)/(Energy Dispersive Spectroscopy) EDS/(selected-area diffraction pattern) SAED, Field Emission-Scanning Electron Microscopy (FE-SEM)/EDS and granulometric distribution analysis. The investigation has revealed that BDW materials are dominated by SiO2, Al2O3 and Fe2O3, with a complex micromineralogy including alkali feldspar, augite, barite, labradorite, hematite, heulandrite, gypsum, kaolinite, quartz, and smectite. In addition we have identified a number of trace metals such as Cd, Cu, Cr, Zn that are preferentially concentrated into the finer, inhalable, dust fraction and could so present a health hazard in the urban areas around the basalt mining zone. The implication of this observation is that use of these nanometric-sized particulates as soil fertilizer may present different health challenges to those of conventional fertilizers, inviting future work regarding the relative toxicities of these materials. Our investigation on the particle size distribution, nano-particle mineralogy and chemical composition in typical BDW samples highlights the need to develop cleaning procedures to minimise exposure to these natural fertilizing basalt dust wastes and is thus of direct relevance to both the industrial sector of basalt mining and to agriculture in the region. PMID:26551199

  16. Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington site. Appendices E through W

    International Nuclear Information System (INIS)

    Volume 2 contains Appendices E through W: potential for large-scale pump tests in the Grande Ronde; review of hydrochemical characterization related to flow system interpretation in Hanford basalts; limitations of packer-testing for head evaluation in Hanford basalts; hydrogeologic data integration for conceptual groundwater flow models; drilling mud effects on hydrogeologic testing; site issue analyses related to the nature at the present groundwater system at the Hanford site, Washington; structural and stratigraphic characteristics related to groundwater flow at the Hanford site, Washington; seismic hazard and some examples of hazard studies at Hanford; earthquake swarms in the Columbia Plateau; seismic ground motion at depth; failure modes for the metallic waste package component; degradation mechanisms of borosilicate glass; transport and retardation of radionuclides in the waste package; determination and interpretation of redox conditions and changes in underground high-level repositories; determination and interpretation of sorption data applied to radionuclide migration in underground repositories; solubility of radionuclide compounds presented in the BWIP site characterization report; and release rate from engineered system

  17. Testing of candidate waste-package backfill and canister materials for basalt

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project (BWIP) is developing a multiple-barrier waste package to contain high-level nuclear waste as part of an overall system (e.g., waste package, repository sealing system, and host rock) designed to isolate the waste in a repository located in basalt beneath the Hanford Site, Richland, Washington. The three basic components of the waste package are the waste form, the canister, and the backfill. An extensive testing program is under way to determine the chemical, physical, and mechanical properties of potential canister and backfill materials. The data derived from this testing program will be used to recommend those materials that most adequately perform the functions assigned to the canister and backfill

  18. High-level waste-basalt interactions. Annual progress report, February 1, 1977--September 30, 1977

    International Nuclear Information System (INIS)

    Commercial radioactive waste can be placed under ground in a basalt repository to contain significant amounts of radioactive decay heat for the first hundred or so years, which constitutes the ''thermal period'' of waste isolation, if the feasibility is determined that a basalt geology is a suitable medium for storage of radioactive wastes. Several physical-chemical changes analogous to natural geochemical processes can occur in and around this repository during the thermal period. The waste canister can act as a heat source and cause changes in the mineralogy and properties of the surrounding basalts. Geochemically, this is ''contact metamorphism.'' This phenomenon needs to be investigated because it could affect the behavior of the basalt with regard to migration of long-lived radionuclides away from the immediate repository. It is well known that even the relatively low-grade hydrothermal conditions possible in the repository (temperatures up to 400 degrees Centigrade; pressures up to 300 bars) can cause extensive modifications in rocks and minerals. At the end of the thermal period, the residue of the original waste plus the waste-basalt interaction products would constitute the actual waste form (or ''source term'') subject to the low-temperature leaching and migration processes under investigation in other laboratories. During the last eight months of fiscal year 1977, a program was initiated at The Pennsylvania State University which had as its objective the determination of the nature and implication of any chemical or mineralogical changes in, or interactions between, each candidate radioactive waste form and representative Columbia River Basalt under the various relevant repository conditions during the thermal period. Results of these investigations are given

  19. Hydrothermal interaction of a ceramic waste form with basalt

    International Nuclear Information System (INIS)

    The behavior of crystalline supercalcine-ceramic in the presence of basalt was investigated under mild hydrothermal conditions at 100, 200, and 3000C with a pressure of 300 bars. Both the solid phases and solution concentrations of the interaction products of basalt and supercalcine-ceramic were characterized. At 1000C, no alteration products could be detected in experiments involving supercalcine-ceramic and basalt. The solution analyses for elements specific to the supercalcine-ceramic did not indicate any significant differences between the treatments with and without basalt, suggesting little or no interaction between basalt and supercalcine-ceramic at this temperature. At 3000C, several solid alteration/interaction products were identified. These products included two phases, pollucite and scheelite, originally incorporated into the ceramic formulation but which reformed with different bulk chemical compositions. In addition, isolated crystals of unidentified K (+-Ba) aluminosilicate phases were observed. Solution analyses of these runs did not indicate any significant differences between the treatments of supercalcine-ceramic with and without basalt, except that the Sr concentration decreased in the presence of basalt. Similar behavior was noted earlier, when basalt and SrZrO3 experiments were conducted. Alteration products and solution concentrations at 2000C lie intermediate between the 1000 and 3000C results

  20. Nuclear waste package materials testing report: basaltic and tuffaceous environments

    International Nuclear Information System (INIS)

    The disposal of high-level nuclear wastes in underground repositories in the continental United States requires the development of a waste package that will contain radionuclides for a time period commensurate with performance criteria, which may be up to 1000 years. This report addresses materials testing in support of a waste package for a basalt (Hanford, Washington) or a tuff (Nevada Test Site) repository. The materials investigated in this testing effort were: sodium and calcium bentonites and mixtures with sand or basalt as a backfill; iron and titanium-based alloys as structural barriers; and borosilicate waste glass PNL 76-68 as a waste form. The testing also incorporated site-specific rock media and ground waters: Reference Umtanum Entablature-1 basalt and reference basalt ground water, Bullfrog tuff and NTS J-13 well water. The results of the testing are discussed in four major categories: Backfill Materials: emphasizing water migration, radionuclide migration, physical property and long-term stability studies. Structural Barriers: emphasizing uniform corrosion, irradiation-corrosion, and environmental-mechanical testing. Waste Form Release Characteristics: emphasizing ground water, sample surface area/solution volume ratio, and gamma radiolysis effects. Component Compatibility: emphasizing solution/rock, glass/rock, glass/structural barrier, and glass/backfill interaction tests. This area also includes sensitivity testing to determine primary parameters to be studied, and the results of systems tests where more than two waste package components were combined during a single test

  1. Basaltic glass: alteration mechanisms and analogy with nuclear waste glasses

    International Nuclear Information System (INIS)

    A synthetic basaltic glass was dissolved experimentally at 90 deg. C under static conditions in initially pure water. The basaltic glass dissolution rates measured near and far from equilibrium were compared with those of SON 68 nuclear waste glass. Experimental and literature data notably suggested that the alteration mechanisms for the two glasses are initially similar. Under steady-state concentration conditions, the alteration rate decreased of four orders of magnitude below the initial rate (r0). The same alteration rate decrease was observed for basaltic and nuclear glass. These findings tend to corroborate the analogy of the two glasses alteration kinetics. The effect of dissolved silica in solution, observed through dynamic leach tests with silicon-rich solutions, cannot account for the significant drop in the basaltic glass kinetics. Hence, a protective effect of the glass alteration film was assumed and experimentally investigated. Moreover, modeling with LIXIVER argue for a significant effect of diffusion in the alteration gel

  2. Nuclear waste repository in basalt: a design description

    International Nuclear Information System (INIS)

    The conceptual design of a nuclear waste repository in basalt is described. Nuclear waste packages are placed in holes drilled into the floor of tunnels at a depth of 3700 ft. About 100 miles of tunnels are required to receive 35,000 packages. Five shafts bring waste packages, ventilation air, excavated rock, personnel, material, and services to and from the subsurface. The most important surface facility is the waste handling building, located over the waste handling shaft, where waste is received and packaged for storage. Two independent ventilation systems are provided to avoid potential contamination of spaces that do not contain nuclear waste. Because of the high temperatures at depth, an elaborate air chilling system is provided. Because the waste packages deliver a considerable amount of heat energy to the rock mass, particular attention is paid to heat transfer and thermal stress studies. 3 references, 31 figures, 3 tables

  3. Progress in the development of waste package performance requirements for a repository located in basalt

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project waste package reference conceptual design consists of three components: the waste form, the canister, and the backfill. The waste package system is an engineered barrier in series with two barriers that are in parallel, i.e., the geologic site barrier and the repository seal system barrier (shaft seal, tunnel backfill, and borehole seals). Preliminary analyses of radionuclide transport and release through the waste package system and site geology are presented herein. The effect of a range of postulated groundwater travel times on radionuclide release to the accessible environment is shown. The required values for two waste package performance parameters are shown as a function of groundwater travel time and potential radionuclide release to the accessible environment. 3 references, 4 figures

  4. Reference waste form, basalts, and ground water systems for waste interaction studies

    Energy Technology Data Exchange (ETDEWEB)

    Deju, R.A.; Ledgerwood, R.K.; Long, P.E.

    1978-09-01

    This report summarizes the type of waste form, basalt, and ground water compositions to be used in theoretical and experimental models of the geochemical environment to be simulated in studying a typical basalt repository. Waste forms to be used in the experiments include, and are limited to, glass, supercalcine, and spent unreprocessed fuel. Reference basalts selected for study include the Pomona member and the Umtanum Unit, Shwana Member, of the Columbia River Basalt Group. In addition, a sample of the Basalt International Geochemical Standard (BCR-1) will be used for cross-comparison purposes. The representative water to be used is of a sodium bicarbonate composition as determined from results of analyses of deep ground waters underlying the Hanford Site. 12 figures, 13 tables.

  5. Hanford site as it relates to an alternative site for the Waste Isolation Pilot Plant: an environmental description

    Energy Technology Data Exchange (ETDEWEB)

    Fecht, K.R. (ed.)

    1978-12-01

    The use of basalt at Hanford as an alternative for the Waste Isolation Pilot Plant (WIPP) would require that the present Basalt Waste Isolation Program (BWIP) at Hanford be expanded to incorporate the planned WIPP functions, namely the permanent storage of transuranic (TRU) wastes. This report discusses: program costs, demography, ecology, climatology, physiography, hydrology, geology, seismology, and historical and archeological sites. (DLC)

  6. Hanford site as it relates to an alternative site for the Waste Isolation Pilot Plant: an environmental description

    International Nuclear Information System (INIS)

    The use of basalt at Hanford as an alternative for the Waste Isolation Pilot Plant (WIPP) would require that the present Basalt Waste Isolation Program (BWIP) at Hanford be expanded to incorporate the planned WIPP functions, namely the permanent storage of transuranic (TRU) wastes. This report discusses: program costs, demography, ecology, climatology, physiography, hydrology, geology, seismology, and historical and archeological sites

  7. Hydrothermal waste package interactions with methane-containing basalt groundwater

    International Nuclear Information System (INIS)

    Hydrothermal waste package interaction tests with methane-containing synthetic basalt groundwater have shown that in the absence of gamma radiolysis, methane has little influence on the glass dissolution rate. Gamma radiolysis tests at fluxes of 5.5 x 105 and 4.4 x 104 R/hr showed that methane-saturated groundwater was more reducing than identical experiments where Ar was substituted for CH4. Dissolved methane, therefore, may be beneficial to the waste package in limiting the solubility of redox sensitive radionuclides such a 99Tc. Hydrocarbon polymers known to form under the irradiation conditions of these tests were not produced. The presence of the waste package constituents apparently inhibited the formation of the polymers, however, the mechanism which prevented their formation was not determined

  8. Summary of INEL research on the iron-enriched basalt waste form

    International Nuclear Information System (INIS)

    This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B203, Na, and SiO2 (glass frit). IEB requires processing temperatures of 1400 to 1600 degrees C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance

  9. Proposed methodology for completion of scenario analysis for the Basalt Waste Isolation Project. [Assessment of post-closure performance for a proposed repository for high-level nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Roberds, W.J.; Plum, R.J.; Visca, P.J.

    1984-11-01

    This report presents the methodology to complete an assessment of postclosure performance, considering all credible scenarios, including the nominal case, for a proposed repository for high-level nuclear waste at the Hanford Site, Washington State. The methodology consists of defensible techniques for identifying and screening scenarios, and for then assessing the risks associated with each. The results of the scenario analysis are used to comprehensively determine system performance and/or risk for evaluation of compliance with postclosure performance criteria (10 CFR 60 and 40 CFR 191). In addition to describing the proposed methodology, this report reviews available methodologies for scenario analysis, discusses pertinent performance assessment and uncertainty concepts, advises how to implement the methodology (including the organizational requirements and a description of tasks) and recommends how to use the methodology in guiding future site characterization, analysis, and engineered subsystem design work. 36 refs., 24 figs., 1 tab.

  10. Effect of aged waste package and basalt on radioelement release

    International Nuclear Information System (INIS)

    Results of experiments are described that combine backfill, radioactive waste, and repository host rock in a single flowing groundwater stream in a manner analogous to a hydraulic breach of a waste repository. The experimental design is used to identify the chemical interactions that would occur if repository components were breached by flowing water. The results indicate that of three parameters studied, the alteration of the repository components as might occur upon aging had the most substantial influence on the migration of radioactive elements dissolved from the solid radioactive waste. The other two parameters, the metal alloy used in the apparatus and an ionizing radiation field imposed on the experimental apparatus, had little or no measurable effect on radioactive element transport by flowing water. Inasmuch as the alteration of the repository materials represent aging in an actual repository, it is concluded that changes with age may detrimentally affect the ability of a repository to isolate plutonium and neptunium, and possibly other radioactive elements in nuclear waste. 37 references, 2 figures, 2 tables

  11. Geo-engineering review and proposed program outline for the structural design of a radioactive waste repository in Columbia Plateau basalts

    International Nuclear Information System (INIS)

    The radioactive waste produced by our nuclear industry must be placed in a safe repository. Deep underground storage in a geologic medium is a method proposed to do this. It has been proposed that basalt in the Pasco Basin of the Columbia Plateau would be an excellent underground storage medium for nuclear waste. Thermal and mechanical properties of basalt have been reviewed. The results of this review show that basalt has many characteristics favorable to long-term storage, including strength and thermal stability indicating the ability to isolate the waste from the biosphere in a geologically stable environment. The available computer codes which may be used to simulate the thermo-mechanical behavior of the rock mass surrounding the repository were reviewed and evaluated. There are several codes currently available or under development that can analyze geo-engineering problems and model the repository in order to predict rock mass behavior. Data gathering and demonstration projects were proposed. These include an extensive drilling program, laboratory analysis of core samples, in situ thermo-mechanical studies performed in an excavation in basalt near the surface, and further studies performed in an underground facility in a deep basalt horizon. Possible repository layouts and mining considerations were discussed. Utilization of data from the above programs, plus programs to improve construction techniques and mining cost determinations, will allow development of a final repository that meets long-term radioactive waste isolation requirements

  12. Characteristics of candidate geologies for nuclear waste isolation: a review

    International Nuclear Information System (INIS)

    Basalt, granite, salt, shale, and tuff formations have been proposed as sites for geologic disposal of high-level nuclear waste. The choice of site will affect the design of the waste package and the accompanying engineered barriers; thus, it is important to know the general properties of each type of repository rock in order to tailor an effective waste isolation system. In this document, the stratigraphy, chemical and mineral composition, hydrology, and physical properties of each rock type are summarized. Most of the data are site-specific and, in some cases, preliminary. More detailed analyses from other sources are expected to be available at a later date. 88 references

  13. Autogenous Tumbling Media Assessment to Clean Weathered Surfaces of Waste-Rock Particles from a Basalt Quarry

    Directory of Open Access Journals (Sweden)

    Baran Tufan

    2015-06-01

    Full Text Available In this study, the optimum feed composition in autogenous tumbling of basalt waste-rock particles to clean their weathered surface was determined. The weathered surfaces of basalt are generally cut out consequent to extraction of basalt columns in quarry operations. The inefficiently cut out portions of basalt cause formation of huge quarry waste dumps causing visual pollution on roadsides. Mixtures of different particle size fractions of basalt waste-rock particles were experimented to achieve the optimum feed material composition. The minimum loss of commercially available basalt particles and maximum clear surface was intended. The results were compared with respect to weight loss (% and reflectance values of used and generated samples.

  14. Seismic studies at a potential deep nuclear waste repository site within the Columbia River basalt group, Pasco, Basin

    International Nuclear Information System (INIS)

    A dense seismic network, including surface and borehole instruments, is being installed to characterize the seismicity of a proposed mined repository in Columbia River basalt on the Hanford Site. There are 11 seismic stations currently being operated by the Basalt Waste Isolation Project (BWIP), including four 1-Hz vertical surface stations, six 2-Hz 3-component surface stations, and one 4.5-Hz 3-component borehole instrument operated at a depth of 1100 m. The signal from these stations is frequency modulation telemetered to a central location, and is recorded at 200 samples/sec on an event-triggered digital recording system. Eight to 10 additional shallow (200 to 300 m) borehole seismometers may be added, pending a review of the repository network requirements prior to construction, and nine additional surface instruments are operated in support of other nuclear projects. The repository network presently has a station spacing of 5 to 10 km, compared to 25 km provided by the University of Washington (UW) regional network. Regional monitoring has observed the occurrence of shallow earthquake swarm activity in the basalts. The objective of the site-specific monitoring is to investigate the location of low-level (magnitude greater than or equal to 0) events, to search for zones of stress release, to measure the seismic moments and stress drops of the sources, and to evaluate the impacts of such microearthquakes on repository performance

  15. Development and characterization of basalt-glass ceramics for the immobilization of transuranic wastes

    International Nuclear Information System (INIS)

    Basalt-based waste forms were developed for the immobilization of transuranic (TRU) contaminated wastes. The specific waste studied is a 3:1 blend of process sludge and incinerator ash. Various amounts of TRU blended waste were melted with Pomona basalt powder. The vitreous products were subjected to a variety of heat treatment conditions to form glass ceramics. The total crystallinity of the glass ceramic, ranging from 20 to 45 wt %, was moderately dependent on composition and heat treatment conditions. Three parent glasses and four glass ceramics with varied composition and heat treatment were produced for detailed phase characterization and leaching. Both parent glasses and glass ceramics were mainly composed of a continuous, glassy matrix phase. This glass matrix entered into solution during leaching in both types of materials. The Fe-Ti rich dispersed glass phase was not significantly degraded by leaching. The glass ceramics, however, exhibited four to ten times less elemental releases during leaching than the parent glasses. The glass ceramic matrix probably contains higher Fe and Na and lower Ca and Mg relative to the parent glass matrix. The crystallization of augite in the glass ceramics is believed to contribute to the improved leach rates. Leach rates of the basalt glass ceramic are compared to those of other TRU nuclear waste forms containing 239Pu

  16. Property and process correlations for iron-enriched basalt waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

    1993-02-01

    Correlations of thermodynamic properties and process parameters of high-temperature slag for a range of compositions of iron-enriched basalt are presented. The quantification of the properties of this complex mixture can assist in the design and monitoring of high-temperature melting systems for the treatment of radioactive and hazardous wastes at the Idaho National Engineering Laboratory. The buried and stored wastes at the INEL Radioactive Waste Management Complex have a similar composition to iron-enriched basalt after oxidation of organics. The properties correlated are the viscosity, electrical conductivity, refractory corrosion, and recrystallization temperature. The correlations are expressed as a function of input waste-soil mixture composition, alkali concentration, and slag temperature. An application to determine the effect of alkali flux on slag temperature, leach rate, and volume reduction is presented. Though the correlations are for mixtures of soil and waste with average transuranic-contaminated waste compositions, it appears that good approximations for other waste streams and glass-ceramic waste forms can be obtained because of similarities in composition.

  17. Simulated high-level waste-basalt interaction experiments. First interim progress report

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, G.J.; Scheetz, B.E.; Komarneni, S.; Barnes, M.; Smith, C.A.; Lewis, J.F.; Smith, D.K.

    1978-03-24

    Reconnaissance experiments have shown that waste/basalt interactions are of real importance in understanding all aspects of total containment of radionuclides in a basalt repository. It has been shown that the reprocessed waste forms, calcine and glass, are relatively more reactive than the more crystalline waste forms, spent unreprocessed fuel (SURF) and supercalcine. These experiments have established the direction of future research. The remainder of the program will be concerned with longer-duration and more-detailed experiments whose emphasis will be on understanding the mechanisms of reaction. Long-duration and in-depth experiments are being initiated to establish kinetic relationships and get a better feel as to whether or not we are approaching equilibrium in our shorter-duration reconnaissance experiments. In some cases, especially at higher temperatures, it appears that we are approaching a steady-state wherein products are no longer changing. This, however, might be a metastable state. Experiments with cesium compounds thought to be present in SURF (Cs/sub 2/MoO/sub 4/), a simple cesium source (CsOH), labradorite, and ground water have shown that pollucite forms and, as a result, fixes 86 to 99% of the cesium (depending upon the amount of basalt present.

  18. Chemical characterization, nano-particle mineralogy and particle size distribution of basalt dust wastes.

    Science.gov (United States)

    Dalmora, Adilson C; Ramos, Claudete G; Oliveira, Marcos L S; Teixeira, Elba C; Kautzmann, Rubens M; Taffarel, Silvio R; de Brum, Irineu A S; Silva, Luis F O

    2016-01-01

    Understanding the geochemistry of basalt alteration is central to the study of agriculture systems. Various nano-minerals play an important role in the mobilization of contaminants and their subsequent uptake by plants. We present a new analytical experimental approach in combination with an integrated analytical protocol designed to study basalt alteration processes. Recently, throughout the world, ultra-fine and nano-particles derived from basalt dust wastes (BDW) during "stonemeal" soil fertilizer application have been of great concern for their possible adverse effects on human health and environmental pollution. Samples of BDW utilized were obtained from companies in the Nova Prata mining district in southern Brazil for chemical characterization and nano-mineralogy investigation, using an integrated application of advanced characterization techniques such as X-ray diffraction (XRD), High Resolution-Transmission Electron microscopy (HR-TEM)/Energy Dispersive Spectroscopy (EDS)/(selected-area diffraction pattern) SAED, Field Emission-Scanning Electron Microscopy (FE-SEM/EDS), and granulometric distribution analysis. The investigation has revealed that BDW materials are dominated by SiO2, Al2O3, and Fe2O3, with a complex micromineralogy including alkali feldspar, augite, barite, labradorite, hematite, heulandrite, gypsum, kaolinite, quartz, and smectite. In addition, we have identified a number of trace metals such as Cd, Cu, Cr, and Zn, that are preferentially concentrated into the finer, inhalable, dust fraction and, thus, could present a health hazard in the urban areas around the basalt mining zone. The implication of this observation is that use of these nanometric-sized particulates as soil fertilizer may present different health challenges to those of conventional fertilizers, inviting future work regarding the relative toxicities of these materials. Our investigation on the particle size distribution, nano-particle mineralogy and chemical composition in

  19. Waste water purification from petroleum oil using basalt fibers and UV radiation

    International Nuclear Information System (INIS)

    Presence of petroleum oil in liquid radioactive wastes at NPPs and in solutions after decontamination of mechanisms, machines and autos caused serious problems in operation of purification equipment. Efficiency of water-phase purification from organic substances in dependence on the filtration rate through the basalt fibers and the filtration bed thickness is studied. It is shown that the petroleum oil content by filtration may be reduced up to 1-2 mg/l and by means of UF irradiation up to 0.5 mg/l

  20. Repository environmental parameters and models/methodologies relevant to assessing the performance of high-level waste packages in basalt, tuff, and salt

    International Nuclear Information System (INIS)

    This document provides specifications for models/methodologies that could be employed in determining postclosure repository environmental parameters relevant to the performance of high-level waste packages for the Basalt Waste Isolation Project (BWIP) at Richland, Washington, the tuff at Yucca Mountain by the Nevada Test Site, and the bedded salt in Deaf Smith County, Texas. Guidance is provided on the identify of the relevant repository environmental parameters; the models/methodologies employed to determine the parameters, and the input data base for the models/methodologies. Supporting studies included are an analysis of potential waste package failure modes leading to identification of the relevant repository environmental parameters, an evaluation of the credible range of the repository environmental parameters, and a summary of the review of existing models/methodologies currently employed in determining repository environmental parameters relevant to waste package performance. 327 refs., 26 figs., 19 tabs

  1. Site characterization report for the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues

  2. Geochemical controls on radionuclide releases from a nuclear waste repository in basalt: estimated solubilities for selected elements

    International Nuclear Information System (INIS)

    Two basalt flows within the Grande Ronde formation at the Hanford Site in Southeastern Washington are candidates for a high-level nuclear waste repository. In order to determine the anticipated rates of release and migration of radionuclides from the repository, solubility controls must be determined for key elements. Solubilities, the solids controlling solubility and aqueous speciation for a variety of actinides and fission products in groundwater, have been determined at 250C from available thermodynamic data over a range of Eh values. Groundwater compositions used include all available analyses from the Grande Ronde formation determined by the Basalt Waste Isolation Project. Solids predicted to control solubility for the selected radionuclides include hydroxides and hydrous oxides (palladium, antimony, samarium, europium, lead, americium), oxides (nickel, tin, thorium, neptunium, plutonium), elements (selenium, palladium) and silicates (zirconium, uranium). Dominant soluble species include hydroxy complexes (zirconium, palladium, tin, antimony, samarium, europium, thorium, uranium, neptunium) and carbonate species (nickel, samarium, europium, lead, uranium, neptunium, plutonium, americium). The effect on solubility of dissolved, reduced (S2-, HS-) sulfur species is large for nickel, palladium, antimony, and lead. However, available data suggest that essentially all sulfur in Grande Ronde groundwater is in the form of sulfate (SO42-). Selenium solubility appears to be a strong function of Eh and may reach very high levels where -0.45 > Eh > -0.05 V. This result suggests that future experimental work should include solubility determinations for selenium. In addition, other elements, notably technetium and radium, with large uncertainties in calculated solubility should also have solubilities determined experimentally

  3. Functions of an engineered barrier system for a nuclear waste repository in basalt

    International Nuclear Information System (INIS)

    Defined in this document are the functions of components selected for an engineered barrier system for a nuclear waste repository in basalt. The definitions provide a focal point for barrier material research and development by delineating the purpose and operative lifetime of each component of the engineered system. A five-component system (comprised of waste form, canister, buffer, overpack, and tailored backfill) is discussed in terms of effective operation throughout the course of repository history, recognizing that the emplacement environment changes with time. While components of the system are mutually supporting, redundancy is provided by subsystems of physical and chemical barriers which act in concert with the geology to provide a formidable barrier to transport of hazardous materials to the biosphere. The operating philosophy of the conceptual engineered barrier system is clarified by examples pertinent to storage in basalt, and a technical approach to barrier design and material selection is proposed. A method for system validation and qualification is also included which considers performance criteria proposed by external agencies in conjunction with site-specific models and risk assessment to define acceptable levels of system performance

  4. Application of cold crucible melting to NPP waste conditioning using basaltic rocks

    International Nuclear Information System (INIS)

    Cold crucible inductive melting (CCIM) is one of the most promising technologies for treatment of various inorganic and organic radioactive wastes. This technology was successfully applied for vitrification of NPP operational wastes produced at Russian RBMK and WWER reactors. These wastes with high concentration of sodium nitrate were vitrified with borosilicate glass formers and high leach resistant and mechanically strong glasses were produced. To reduce a cost of the process boron-containing additives may be substituted by local basaltic rocks. Such rocks contain major silicon, aluminium, iron oxides and minor sodium, potassium, calcium, manganese and other oxides and may be used as effective and inexpensive glass forming additives to NNP waste salts. Lab-scale tests using a cold crucible energized from 10 kW high frequency (5.28 MHz) generator were conducted. Glasses and glass-crystalline materials obtained had low leach rates of alkali elements, boron, and silicon being very similar to leach rates from HLW borosilicate glasses (PCT test). (author)

  5. Waste Isolation Pilot Plant simulated waste compositions and mechanical properties

    International Nuclear Information System (INIS)

    Analyses of the final state of collapse of various types of contact-handled waste drums are required to assess of the performance of the waste storage areas in the Waste Isolation Pilot Plant. To provide data for calculations, tests must use simulated, instead of actual waste. Data on the contents of the principal categories of contact-handled transuranic waste from the Idaho National Engineering Laboratory were used to define standard compositions of simulated waste. Categories of baseline waste will be created by mixing appropriate amounts of the simulants together. Selection of materials is discussed. Methods for estimating the consolidation characteristics of simulated waste are also described. Theoretical solid densities, theoretical solid compressibilities, and initial void volumes of various waste components are estimated, and a method for estimating consolidation curves in the absence of experimental data is described. 9 refs., 14 figs., 11 tabs

  6. Waste acceptance criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase

  7. Waste isolation facility description: bedded salt

    International Nuclear Information System (INIS)

    The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria

  8. Preliminary feasibility study on storage of radioactive wastes in Columbia River basalts. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    ,

    1976-11-01

    Volume II comprises four appendices: analytical data and sample locations for basalt flow type localities; Analytical data and sample locations for measured field sections in Yakima basalts; core hole lithology and analytical data; and geophysical logs. (LK)

  9. Numerical modelling of rock stresses within a basaltic nuclear waste repository. Phase I, problem definition

    International Nuclear Information System (INIS)

    Numerical modeling of the thermo-mechanical response of the basaltic rock mass surrounding a nuclear waste repository will be required during the design and licensing phases of the repository. The reliance on numerical modeling is greater in this project than for other underground construction projects because of the interaction of both thermal and groundwater problems with traditional rock mechanics and because of the unusually long time for which the repository must function satisfactorily. The types of thermo-mechanical problems that must be analyzed using numerical models are identified and discussed. No one single analysis or modeling technique would be able to provide both the detail required in some areas and the overall impact required in the regional analyses. Hence, the repository modeling problems are divided into three scale categories and two time scales. The three size subdivisions correspond loosely to canister-, room- and repository-scale problems, and short-term, including processes during construction and the retrievability period, and long-term problems are identified. Numerical techniques as well as boundary integral equation methods are reviewed and the applicability to problems associated with nuclear waste disposal discussed

  10. Nuclear waste isolation activities report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    Included are: a report from the Deputy Assistant Secretary, a summary of recent events, new literature, a list of upcoming waste management meetings, and background information on DOE`s radwaste management programs. (DLC)

  11. Nuclear waste isolation activities report

    International Nuclear Information System (INIS)

    Included are: a report from the Deputy Assistant Secretary, a summary of recent events, new literature, a list of upcoming waste management meetings, and background information on DOE's radwaste management programs

  12. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

    International Nuclear Information System (INIS)

    This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses

  13. Rationale for development of constitutive models of a basalt rock mass for design of a nuclear waste repository at the Hanford Site

    International Nuclear Information System (INIS)

    The Cohassett basalt flow underlying the Hanford Site in Eastern Washington is being investigated by the U.S. Department of Energy to assess the feasibility of constructing the nation's first nuclear waste repository in the flow. Development of constitutive laws of the basalt is necessary for modeling studies used to evaluate the repository design and to evaluate the ability of the repository to contain radioactive waste for several thousands of years. This paper evaluates four analytical approaches that have been used in previous analyses of the repository in basalt and presents a strategy for further development of constitutive models

  14. Waste Isolation Pilot Plant Safety Analysis Report

    International Nuclear Information System (INIS)

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions'' (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.'' This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment

  15. Waste Isolation Pilot Plant Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  16. Experimental alteration of basalt glass applied to the alteration of nuclear waste glass

    International Nuclear Information System (INIS)

    The main objective of the experiments was to produce in the laboratory an altered basalt glass similar to basalt glass altered in a natural environment. This objective has been accomplished with a very good correlation between the observed alteration of basalt glass in a natural environment with that in the laboratory. The formation of the amorphous hydration layer, smectite, analcime, calcium carbonate, and thomsonite all have been observed in natural glass samples that have undergone palagonitization. The SRL 165 glass reacts to a greater extent than the synthetic basalt glass under the same conditions. The alteration of SRL 165 glass produced a smectite clay, analcime, and gyrolite similar to that produced by the synthetic basalt glass

  17. Geological problems in radioactive waste isolation

    International Nuclear Information System (INIS)

    The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, ''Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately

  18. Geological problems in radioactive waste isolation

    Energy Technology Data Exchange (ETDEWEB)

    Witherspoon, P.A. (ed.)

    1991-01-01

    The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

  19. Waste acceptance criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies

  20. Mechanical compaction of Waste Isolation Pilot Plant simulated waste

    International Nuclear Information System (INIS)

    The investigation described in this report acquired experimental information about how materials simulating transuranic (TRU) waste compact under axial compressive stress, and used these data to define a model for use in the Waste Isolation Pilot Plant (WIPP) disposal room analyses. The first step was to determine compaction curves for various simultant materials characteristic of TRU waste. Stress-volume compaction curves for various combinations of these materials were than derived to represent the combustible, metallic, and sludge waste categories. Prediction of compaction response in this manner is considered essential for the WIPP program because of the difficulties inherent in working with real (radioactive) waste. Next, full-sized 55-gallon drums of simulated combustible, metallic, and sludge waste were axially compacted. These results provided data that can be directly applied to room consolidation and data for comparison with the predictions obtained in Part 1 of the investigation. Compaction curves, which represent the combustible, metallic, and sludge waste categories, were determined, and a curve for the averaged waste inventory of the entire repository was derived. 9 refs., 31 figs., 12 tabs

  1. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 23. Environmental effluent analyses

    International Nuclear Information System (INIS)

    This volume, Y/OWI/TM-36/23, ''Environmental Effluent Analysis,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Drat Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the releases to the environment of radioactive and non-radioactive materials that arise during facility construction and waste handling operations, as well as releases that could occur in the event of an operational accident. The results of the analyses are presented along with a detailed description of the analytical methodologies employed

  2. Waste isolation pilot plant disposal room model

    International Nuclear Information System (INIS)

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the open-quotes Disposal Room Model,close quotes describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized

  3. Waste isolation pilot plant disposal room model

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the {open_quotes}Disposal Room Model,{close_quotes} describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized.

  4. Waste Isolation Pilot Plant safety analysis report

    International Nuclear Information System (INIS)

    The United States Department of Energy (DOE) was authorized by Public Law 96-164 to provide a research and development facility for demonstrating the safe permanent disposal of transuranic (TRU) wastes from national defense activities and programs of the United States exempted from regulations by the US Nuclear Regulatory Commission (NRC). The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico near Carlsbad, was constructed to determine the efficacy of an underground repository for disposal of TRU wastes. In accordance with the 1981 and 1990 Records of Decision (ROD), the development of the WIPP was to proceed with a phased approach. Development of the WIPP began with a siting phase, during which several sites were evaluated and the present site selected based on extensive geotechnical research, supplemented by testing. The site and preliminary design validation phase (SPDV) followed the siting phase, during which two shafts were constructed, an underground testing area was excavated, and various geologic, hydrologic, and other geotechnical features were investigated. The construction phase followed the SPDV phase during which surface structures for receiving waste were built and underground excavations were completed for waste emplacement

  5. Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 2. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    This document is the Baseline Inventory Report for the transuranic (alpha-bearing) wastes stored at the Waste Isolation Pilot Plant (WIPP) in New Mexico. Waste stream profiles including origin, applicable EPA codes, typical isotopic composition, typical waste densities, and typical rates of waste generation for each facility are presented for wastes stored at the WIPP.

  6. Rock mechanics activities at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The application of rock mechanics at nuclear waste repositories is a true multidisciplinary effort. A description and historical summary of the Waste Isolation Pilot Plant (WIPP) is presented. Rock mechanics programs at the WIPP are outlined, and the current rock mechanics modeling philosophy of the Westinghouse Waste Isolation Division is discussed

  7. Waste Isolation Pilot Plant Strategic Plan

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant (WIPP) Strategic Plan is to provide decision makers, project participants, and the public with a high-level overview of the objectives, issues, and strategiesthat impact a decision on the suitability of WIPP as a permanent, safe disposal facility for transuranic (TRU) waste that has resulted from defense activities. This document is a component of an integrated planning process and is a key management tool that is coordinated and consistent with the Secretary's Disposal Decision Plan and the Environmental Restoration and Waste Management (EM) Five-Year Plan. This documentsupports other US Department of Energy (DOE) planning efforts, including the TRU Waste Program. The WIPP Strategic Plan addresses the WIPP Program Test Phase, Disposal Decision, Disposal Phase, and Decommissioning Phase (decontamination and decommissioning). It describes the actions and activities that the DOE will conduct to ensure that WIPP will comply with applicable, relevant, and appropriate requirements of the US Environmental Protection Agency (EPA), State of New Mexico, and other applicable federal and state regulations. It also includes the key assumptions under which the strategy was developed. A comprehensive discussion of the multitude of activities involved in the WIPP Program cannot be adequately presented in this document. The specific details of these activities are presented in other, more detailed WIPP planningdocuments

  8. Thermodynamic tables for nuclear waste isolation

    International Nuclear Information System (INIS)

    Tables of consistent thermodynamic property values for nuclear waste isolation are given. The tables include critically assessed values for Gibbs energy of formation, enthalpy of formation, entropy and heat capacity for minerals; solids; aqueous ions; ion pairs and complex ions of selected actinide and fission decay products at 25 degree C and zero ionic strength. These intrinsic data are used to calculate equilibrium constants and standard potentials which are compared with typical experimental measurements and other work. Recommendations for additional research are given. 13 figs., 23 tabs

  9. Waste Isolation Pilot Plant No-migration variance petition

    International Nuclear Information System (INIS)

    This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program

  10. Waste Isolation Pilot Plant, Land Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives.

  11. Waste Isolation Pilot Plant, Land Management Plan

    International Nuclear Information System (INIS)

    To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives

  12. Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan

    International Nuclear Information System (INIS)

    The following recommendations have been abstracted from the body of this report. The Office of Nuclear Waste Isolation's Socioeconomic Program Plan for the Establishment of Mined Geologic Repositories to Isolate Nuclear Waste should be modified to: (1) encourage active public participation in the decision-making processes leading to repository site selection; (2) clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process. In addition, the Office of Nuclear Waste Isolation should carefully review the overall role that these persons and groups, including local pressure groups organized in the face of potential repository development, will play in the siting process; (3) place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; (4) include additional approaches to solving socioeconomic problems. For example, a reluctance to acknowledge that solutions to socioeconomic problems need to be found jointly with interested parties is evident in the plan; (5) recognize that mitigation mechanisms other than compensation and incentives may be effective; (6) as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and (7) comply fully with the pertinent provisions of NWPA

  13. Numerical modeling of rock stresses within a basaltic nuclear waste repository. Final report

    International Nuclear Information System (INIS)

    The modeling undertaken during this project incorporated a wide range of problems that impact the design of the waste repository. Interaction of groundwater, heat and stress were considered on a regional scale, whereas on the room and canister scale thermo-mechanical analyses were undertaken. In the Phase II report, preliminary guidelines for waste densities were established based primarily on short-term stress criteria required to maintain stability during the retrievability period. Additional analyses are required to evaluate the effect of joints, borehole linings, room support and ventilation on these preliminary waste loading densities. The regional analyses did not indicate any adverse effect that could control the allowable waste loading densities. However, further refinements of geologic structure, hydrologic models, seismicity and possible induced seismicity are required before firm estimates of the loading densities can be made

  14. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 8. Repository preconceptual design studies: salt

    International Nuclear Information System (INIS)

    This volume, Volume 8 ''Repository Preconceptual Design Studies: Salt,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in salt. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/9, ''Drawings for Repository Preconceptual Design Studies: Salt.''

  15. Geology and petrology of the basalts of Crater Flat: applications to volcanic risk assessment for the Nevada Nuclear Waste Storage investigations

    International Nuclear Information System (INIS)

    Volcanic hazard studies of the south-central Great Basin, Nevada, are being conducted for the Nevada Nuclear Waste Storage Investigations. This report presents the results of field and petrologic studies of the basalts of Crater Flat, a sequence of Pliocene to Quaternary-age volcanic centers located near the southwestern part of the Nevada Test Site. Crater Flat is one of several basaltic fields constituting a north-northeast-trending volcanic belt of Late Cenozoic age extending from southern Death Valley, California, through the Nevada Test Site region to central Nevada. The basalts of Crater Flat are divided into three distinct volcanic cycles. The cycles are characterized by eruption of basalt magma of hawaiite composition that formed cinder cone clusters and associated lava flows. Total volume of erupted magma for respective cycles is given. The basalts of Crater Flat are sparsely to moderately porphyritic; the major phenocryst phase is olivine, with lesser amounts of plagioclase, clinopyroxene, and rare amphibole. The consistent recurrence of evolved hawaiite magmas in all three cycles points to crystal fractionation from more primitive magmas at depth. A possible major transition in mantle source regions through time may be indicated by a transition from normal to Rb-depleted, Sr-enriched hawaiites in the younger basaltic cycles. The recurrence of small volumes of hawaiite magma at Crater Flat supports assumptions required for probability modeling of future volcanic activity and provides a basis for estimating the effects of volcanic disruption of a repository site in the southwestern Nevada Test Site region. Preliminary data suggest that successive basalt cycles at Crater Flat may be of decreasing volume but recurring more frequently

  16. Waste Isolation Pilot Plant borehole data

    International Nuclear Information System (INIS)

    Data pertaining to all the surface boreholes used at the WIPP site for site characterization hydrological testing and resource evaluation exist in numerous source documents. This project was initiated to develop a comprehensive data base that would include the data on all WIPP related surface boreholes from the Atomic Energy Commission, Waste Isolation Pilot Plant Energy Research and Development Administration, Department of Energy, and Hydrologic Test Borehole Programs. The data compiled from each borehole includes: operator, permit number, location, total depth, type of well, driller, drilling record, casing record, plugging schedule, and stratigraphic summary. There are six groups of boreholes contained in this data base, they are as follows: Commercially Drilled Potash Boreholes, Energy Department Wells, Geologic Exploration Boreholes, Hydrologic Test Boreholes, Potash Boreholes, and Subsurface Exploration Boreholes. There were numerous references which contained borehole data. In some cases the data found in one document was inconsistent with data in another document. In order to ensure consistency and accuracy in the data base, the same references were used for as many of the boreholes as possible. For example, all elevations and locations were taken from Compilation and Comparison of Test-Hole Location Surveys in the Vicinity of the WIPP Site. SAND 88-1065, Table 3-5. There are some sections where a data field is left blank. In this case, the information was either not applicable or was unavailable

  17. Waste Isolation Pilot Plant Salt Decontamination Testing

    Energy Technology Data Exchange (ETDEWEB)

    Rick Demmer; Stephen Reese

    2014-09-01

    On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. At the request of WIPP’s operations contractor, Idaho National Laboratory (INL) personnel developed several methods of decontaminating WIPP salt, using surrogate contaminants and also americium (241Am). The effectiveness of the methods is evaluated qualitatively, and to the extent possible, quantitatively. One of the requirements of this effort was delivering initial results and recommendations within a few weeks. That requirement, in combination with the limited scope of the project, made in-depth analysis impractical in some instances. Of the methods tested (dry brushing, vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high, and it is very easy and rapid to deploy. The amount of wastewater produced (2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from the strippable coating and water washing coupons found no residual removable contamination. Thus, whatever is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System (PBS) proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.

  18. Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problems; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) explains the rationale and design criteria for the environmental monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document changes in the environmental monitoring program. Guidance for preparation of EMPs is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

  19. Waste Isolation Pilot Plant Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2008-03-12

    U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problems; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) explains the rationale and design criteria for the environmental monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document changes in the environmental monitoring program. Guidance for preparation of EMPs is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

  20. Degradation of transuranic-contaminated wastes under geological isolation conditions

    International Nuclear Information System (INIS)

    Results of extensive experimental studies on the degradation of existing defense transuranic-contaminated (TRU) wastes are presented. Environmental conditions for waste degradation are representative of deep geological isolation of TRU wastes in a bedded-salt repository, as anticipated for the proposed Waste Isolation Pilot Plant in southeastern New Mexico. TRU-contaminated waste matrices investigated include cellulosics, plastics, rubbers, mixed organic composite, bitumen, a developmental concrete-TRU ash matrix, mild steel, and inorganic process sludges. Degradation mechanisms studied were alpha radiolysis, microbial action, thermal decomposition and dewatering, and chemical corrosion. Experimental variables are waste composition, alpha-contamination level, temperature, pressure, time, water or brine content, aerobic or anaerobic conditions, etc. Results of waste degradation are presented in terms of gas generation rates, gas compositions, container corrosion rates, effectiveness of anti-corrosion coatings, microbial formation and degradation of chelating agents. Based on experimental results, the relative quantities of gas generated by individual mechanisms acting on the organic matrix wastes can be ranked as follows: (1) microbial action, (2) thermal decomposition (at 400C and higher), (3) alpha radiolysis, and (4) corrosion. Corrosion of metallic waste canisters and realistic bedded-salt repository conditions was determined not to have a significant effect on potential waste retrievability. The technical data provided in these studies are used in assessments to determine whether existing forms of TRU wastes are acceptable for safe geological isolation. (author)

  1. Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problem; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) has been written to contain the rationale and design criteria for the monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document any proposed changes in the environmental monitoring program. Guidance for preparation of Environmental Monitoring Plans is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance. The plan will be effective when it is approved by the appropriate Head of Field Organization or their designee. The plan discusses major environmental monitoring and hydrology activities at the WIPP and describes the programs established to ensure that WIPP operations do not

  2. A DEPTH OPTIMIZATION STUDY FOR GEOLOGIC ISOLATION OF RADIOACTIVE WASTES

    Energy Technology Data Exchange (ETDEWEB)

    Thadani, M.

    1980-02-01

    Current Federal plans for the isolation of high-level radioactive wastes and spent fuel include the possible placement of these wastes in deep geologic repositories. It is generally assumed that increasing the emplacement depth increases safety because the wastes are farther removed from the phenomena that might compromise the integrity of their isolation. Also, the path length for the migration of radionuclides to the biosphere increases with depth, thus delaying their arrival. However, increasing the depth of emplacement adds cost and operatiunal penalties. Therefore, a trade-off between the safety and the cost of waste isolation exists. A simple algorithm has been developed to relate the repository construction and operation costs, the costs associated with construction and operational hazards, and the costs resulting from radiological exposures to future generations to the depth of emplacement: The application of the algorithm is illustrated by SdDlP 1 e ca leul at ions u t il i zing se 1 ec ted parameters. The cost-optimum emplacement depths are estimated by summing the cost elements and determining the depth at which the sum would be the least. The relationship between the repository construction costs and the depth of the depository was derived from simplified rock mechanics and stability considerations applied to repository design concepts selected from the current literature and the available data base on mining and excavation costs. In developing the relationship between the repository costs and the depth of the depository, a worldwide cost information data base was used. The relationships developed are suitable for application to bedded sa1t, shale, and basalt geologies. The incremental impacts of hazards as a function of repository depth resulting from drilling, construction of repositories and hoisting systems, and operation of repositories were developed from the reported data on accidents involving shafts and mine construction activities and shaft

  3. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Volume I contains the following attachments for Module II: waste analysis plan; quality assurance program plan for the Waste Isolation Pilot Plant (WIPP) Experiment Waste Characterization Program(QAPP); WIPP Characterization Sampling and Analysis Guidance Manual (Plan)(SAP); and no migration Determination Requirement Summary (NMD)

  4. Initial hydrothermal waste package release experiments using spent fuel with waste package components

    International Nuclear Information System (INIS)

    The Waste/Barrier/Rock interactions program of the Basalt Waste Isolation Project (BWIP) is conducting hydrothermal experiments with fully radioactive waste forms and the other components comprising a designed waste package for a basalt repository. These additional materials include container material (steel) and packing material (crushed basalt and bentoonite). The initial 11 experiments with spent reactor fuel have been completed, showing that, after six months, the fuel begins to react only slightly with water at 2000C. Solid reaction products identified thus far consist of uranylsilicate in spent fuel-water experiments, an iron hydroxide in steel-spent fuel experiments, and a smectite clay in basalt-bearing experiments. Solution samples taken during the experiments show that concentrations of many radionuclides, including Cs, Sr, and the actinides, are lower with basalt present than without. With or without basalt, these key species occur in solution at concentrations well below those required to meet federal release criteria

  5. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 22. Nuclear considerations for repository design

    International Nuclear Information System (INIS)

    This volume, Y/OWI/TM-36/22, ''Nuclear Considerations for Repository Design,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. Included in this volume are baseline design considerations such as characteristics of canisters, drums, casks, overpacks, and shipping containers; maximum allowable and actual decay-heat levels; and canister radiation levels. Other topics include safeguard and protection considerations; occupational radiation exposure including ALARA programs; shielding of canisters, transporters and forklift trucks; monitoring considerations; mine water treatment; canister integrity; and criticality calculations

  6. Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Britt, Phillip F [ORNL

    2015-03-01

    Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions based on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.

  7. Waste Isolation Pilot Plant (WIPP) fact sheet

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    Pursuant to the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (RCRA), as amended (42 USC 6901, et seq.), and the New Mexico Hazardous Waste Act (Section 74-4-1 et seq., NMSA 1978), Permit is issued to the owner and operator of the US DOE, WIPP site (hereafter called the Permittee(s)) to operate a hazardous waste storage facility consisting of a container storage unit (Waste Handling Building) and two Subpart X miscellaneous below-ground storage units (Bin Scale Test Rooms 1 and 3), all are located at the above location. The Permittee must comply with all terms and conditions of this Permit. This Permit consists of the conditions contained herein, including the attachments. Applicable regulations cited are the New Mexico Hazardous Waste Management Regulations, as amended 1992 (HWMR-7), the regulations that are in effect on the date of permit issuance. This Permit shall become effective upon issuance by the Secretary of the New Mexico Environment Department and shall be in effect for a period of ten (10) years from issuance. This Permit is also based on the assumption that all information contained in the Permit application and the administrative record is accurate and that the activity will be conducted as specified in the application and the administrative record. The Permit application consists of Revision 3, as well as associated attachments and clarifying information submitted on January 25, 1993, and May 17, 1993.

  8. Materials considerations relative to multibarrier waste isolation

    International Nuclear Information System (INIS)

    The environmental conditions associated with the storage of radioactive wastes are reviewed, and the corrosion of potential waste containment materials under these conditions is evaluated. The desired service life of about 1000 years is beyond the time period for which existing corrosion data can be extrapolated with certainty; however, titanium alloys seem to offer the most promise. The mechanical requirements for canisters and overpacks are considered and several candidate materials are selected. Designs for a canister and an overpack have been developed, and these are used to estimate the costs for three possible materials of construction

  9. The Waste Isolation Pilot Plant no-migration variance petition

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) has been built to be a mined geologic repository for transuranic (TRU) waste generated by the defense programs of the U.S. government. This waste generally consists of rags, clothing, laboratory equipment, and other items that are contaminated with TRU elements in excess of 100 nCi/g. Construction of the WIPP facility is essentially complete, and the plant is undergoing final checkout and startup in anticipation of beginning a series of experimental evaluations aimed at gathering data and operating experience. One significant conclusion that will come out of these experiments is whether or not it is necessary to treat these wastes prior to disposal. One issue associated with the lack of treatment technology and capacity for these wastes is related to compliance with the Resource Conservation and Recovery Act (RCRA) and involve those radioactive wastes that are cocontaminated with hazardous wastes. These so-called radioactive mixed wastes are subject to dual regulation under the Atomic Energy Act and RCRA. In specifying the concept of no disposal of untreated hazardous waste, Congress included language in the statute that allows disposal if the operator can demonstrate that the water will not migrate from the disposal unit for as long as the wastes are hazardous. This demonstration is submitted to the administrator of the EPA in the form of a petition, referred to as a no-migration variance petition. The WIPP no-migration variance petition was submitted to the EPA in March of 1989

  10. Assessing compliance of the waste isolation pilot plant performance assessment

    International Nuclear Information System (INIS)

    On May 13, 1998 the US Environmental Protection Agency (EPA) determined (with conditions) that the Department of Energy (DOE) Waste Isolation Pilot Plant met EPA's radioactive waste disposal standards at 40 CFR 191 and 194. DOE demonstrated compliance with the radioactive waste disposal numerical containment requirements through the use of performance assessment simulating potential releases over a 10,000 year simulation. In addition to EPA's role in the development and implementation of regulations, EPA conducted an independent review of DOE's performance assessment, including conceptual models, computer codes, input parameters, scenario screening and documentation. EPA's review identified inadequacies that DOE addressed. EPA then directed DOE to conduct an additional set of calculations in the Performance Assessment Verification Test (PAVT). The PAVT predicted releases that were greater than the releases predicted in DOE's original calculations, but they did not violate EPA's containment requirements. This demonstrated that the Waste Isolation Pilot Plant is a robust system that can contain radionuclides as required

  11. Waste Isolation Pilot Plant Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse Electric Company Waste Isolation Division

    1999-09-29

    DOE Order 5400.1, General Environmental Protection Program Requirements (DOE, 1990a), requires each DOE facility to prepare an EMP. This document is prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment (DOE, 1990b); Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) 834, Radiation Protection of the Public and Environment (Draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1 (DOE, 1995), which is the driver for the Annual Site Environmental Report (ASER) and the guidance source for preparing many environmental program documents. The WIPP project is operated by Westinghouse Electric Company, Waste Isolation Division (WID), for the DOE. This plan defines the extent and scope of the WIPP's effluent and environmental monitoring programs during the facility's operational life and also discusses the WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE, 1991). This document references DOE orders and other federal and state regulations affecting environmental monitoring programs at the site. WIPP procedures

  12. Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    DOE Order 5400.1, General Environmental Protection Program Requirements (DOE, 1990a), requires each DOE facility to prepare an EMP. This document is prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment (DOE, 1990b); Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) 834, Radiation Protection of the Public and Environment (Draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1 (DOE, 1995), which is the driver for the Annual Site Environmental Report (ASER) and the guidance source for preparing many environmental program documents. The WIPP project is operated by Westinghouse Electric Company, Waste Isolation Division (WID), for the DOE. This plan defines the extent and scope of the WIPP's effluent and environmental monitoring programs during the facility's operational life and also discusses the WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE, 1991). This document references DOE orders and other federal and state regulations affecting environmental monitoring programs at the site. WIPP procedures, which implement

  13. Retrieval of canistered experimental waste at the waste isolation pilot plant

    International Nuclear Information System (INIS)

    To assess the suitability of bedded salt for nuclear waste disposal, an extensive experimental program will be implemented at the Waste Isolation Pilot Plant. In order to evaluate experimental results, it will be necessary to recover certain of these experiments for postmortem examination and analysis. This document describes the equipment and procedures used to effect recovery of one category of WIPP experiments

  14. Operations Program Plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

  15. In-situ stress measurement in a jointed basalt: the suitability of five overcoring techniques

    International Nuclear Information System (INIS)

    Overcoring tests were conducted at the Near-Surface Test Facility (NSTF) to assess the suitability of five techniques (US Bureau of Mines borehole deformation gauge (BDG), Commonwealth Scientific and Industrial Research Organization (CSIRO) hollow inclusion stress cell, epoxy inclusion, Lulea triaxial gauge (LuH gauge), and Council for Scientific and Industrial Research (CSIR) doorstopper) for in situ stress determination in a closely jointed basalt. This effort is in support of the Basalt Waste Isolation project, which is studying the feasibility of locating a nuclear waste repository in the basalts of the Hanford Site in southeastern Washington. This paper preents the results from the overcoring study that formed the basis for selection of two techniques to be used during the further exploration of the basalt formations at depth

  16. Final environmental impact statement. Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described

  17. Final environmental impact statement. Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

  18. Seismic Characterization of Basalt Topography at Two Candidate Sites for the INL Remote-Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Jeff Sondrup; Gail Heath; Trent Armstrong; Annette Shafer; Jesse Bennett; Clark Scott

    2011-04-01

    This report presents the seismic refraction results from the depth to bed rock surveys for two areas being considered for the Remote-Handled Low-Level Waste (RH-LLW) disposal facility at the Idaho National Laboratory. The first area (Site 5) surveyed is located southwest of the Advanced Test Reactor Complex and the second (Site 34) is located west of Lincoln Boulevard near the southwest corner of the Idaho Nuclear Technology and Engineering Center (INTEC). At Site 5, large area and smaller-scale detailed surveys were performed. At Site 34, a large area survey was performed. The purpose of the surveys was to define the topography of the interface between the surficial alluvium and underlying basalt. Seismic data were first collected and processed using seismic refraction tomographic inversion. Three-dimensional images for both sites were rendered from the data to image the depth and velocities of the subsurface layers. Based on the interpreted top of basalt data at Site 5, a more detailed survey was conducted to refine depth to basalt. This report briefly covers relevant issues in the collection, processing and inversion of the seismic refraction data and in the imaging process. Included are the parameters for inversion and result rendering and visualization such as the inclusion of physical features. Results from the processing effort presented in this report include fence diagrams of the earth model, for the large area surveys and iso-velocity surfaces and cross sections from the detailed survey.

  19. Elaboration of vitreous and vitrocrystalline basalt materials containing simulated radioactive ash wastes. Study of some physical properties and leaching behaviour

    International Nuclear Information System (INIS)

    This work is a preliminary study of a matrix for containment of incinerator ashes. Basalt presents a good capacity for ash incorporation (up to 50%), glasses obtained are homogeneous and the low viscosity at 13000C allows an industrial preparation. Vitrocrystalline products have a dendritic texture which can be controlled by cooling rate and are composed of magnesioferrite, pyroxene, plagioclase and vitreous fraction depending on the filling material ratio. Uranium and thorium, for actinide simulation in ashes, are localized in the glass. Glass leaching decrease with ash content and the alteration film presents a better retention of some elements, such as uranium and thorium. Vitrocrystalline materials are less leachable than glasses. Interesting possibilities are shown for use of basalt as filling material in underground storage, since basalt decrease glass deterioration

  20. Waste-isolation projects, FY 1978

    International Nuclear Information System (INIS)

    This report describes Lawrence Livermore Laboratory (LLL) activities during FY 1978 in support of the National Waste Terminal Storage Program. Current projects at LLL fall into three categories: (1) field testing, (2) laboratory rock mechanics measurements, and (3) laboratory studies of sorption and leaching. Field test activities conducted in the Climax granite at the Nevada Test Site included electrical heater tests, preparation for a spent-fuel-storage test, and planning for a series of rock mechanics tests. The heater tests determined the in situ thermal properties of Climax granite and its in situ permeability as a function of rock temperature. The two main laboratory rock mechanics projects involved (1) measurement of the permeability, electrical conductivity, and acoustic velocity of 15-cm-diam cores of granitic rocks over a range of confining pressure, pore (water) pressure, and deviatoric stress, and (2) measurement of rock thermal properties as a function of temperature and confining pressure in the presence of pore fluids to 7700K and 200 Mpa. The leaching studies made use of an LLL-designed, single-pass leaching apparatus with three solutions, two leach temperatures, and three flow rates. The material evaluated was Np--Pu-doped simulated waste glass from Battelle Pacific Northwest Laboratories. The sorption studies involved standard static measurements of the equilibrium distribution coefficient (K/sub d/) for various radionuclides on a variety of rocks, and flow-through-core studies of dynamic sorption

  1. Waste isolation safeguards and security system. Volume 2. Bibliography

    International Nuclear Information System (INIS)

    The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schedule and provides an extensive bibliography, in volumes two and three of applicable reference safeguards documents

  2. Waste isolation safeguards and security system. Volume 3. Bibliography supplement

    International Nuclear Information System (INIS)

    The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schecule and provides an extensive bibliography in volumes two and three of applicable reference safeguards documents

  3. Geological problems in radioactive waste isolation - second worldwide review

    Energy Technology Data Exchange (ETDEWEB)

    Witherspoon, P.A. [ed.

    1996-09-01

    The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19, 1989 in Washington, D.C. Reports from 15 countries were presented at the workshop and four countries provided reports after the workshop, so that material from 19 different countries was included in the first review. It was apparent from the widespread interest in this first review that the problem of providing a permanent and reliable method of isolating radioactive waste from the biosphere is a topic of great concern among the more advanced, as well as the developing, nations of the world. This is especially the case in connection with high-level waste (HLW) after its removal from nuclear power plants. The general concensus is that an adequate isolation can be accomplished by selecting an appropriate geologic setting and carefully designing the underground system with its engineered barriers. This document contains the Second Worldwide Review of Geological Problems in Radioactive Waste Isolation, dated September 1996.

  4. Geological problems in radioactive waste isolation - second worldwide review

    International Nuclear Information System (INIS)

    The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19, 1989 in Washington, D.C. Reports from 15 countries were presented at the workshop and four countries provided reports after the workshop, so that material from 19 different countries was included in the first review. It was apparent from the widespread interest in this first review that the problem of providing a permanent and reliable method of isolating radioactive waste from the biosphere is a topic of great concern among the more advanced, as well as the developing, nations of the world. This is especially the case in connection with high-level waste (HLW) after its removal from nuclear power plants. The general concensus is that an adequate isolation can be accomplished by selecting an appropriate geologic setting and carefully designing the underground system with its engineered barriers. This document contains the Second Worldwide Review of Geological Problems in Radioactive Waste Isolation, dated September 1996

  5. Waste Isolation Pilot Plant 2005 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2006-10-13

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to make WIPP environmental information available to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2004. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through defense activities and programs. TRU waste is defined, in the WIPP LWA, as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting TRU isotopes per gram of waste, with half-lives greater than 20 years except for high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools; sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. TRU waste is eligible for disposal at WIPP if it has been generated in whole or in part by one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management,defense nuclear materials security and safeguards and security

  6. Waste Isolation Pilot Plant Annual Site Environmental Report for 2005

    International Nuclear Information System (INIS)

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to make WIPP environmental information available to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2004. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through defense activities and programs. TRU waste is defined, in the WIPP LWA, as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting TRU isotopes per gram of waste, with half-lives greater than 20 years except for high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools; sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. TRU waste is eligible for disposal at WIPP if it has been generated in whole or in part by one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] 10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management,defense nuclear materials security and safeguards and security investigations, and defense

  7. Summarizing Ten Years Operating the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Ten years ago this month, the Waste Isolation Pilot Plant (WIPP) received the first shipment of Transuranic (TRU) waste for permanent isolation from the biosphere. Twenty years of planning, site characterization studies, licensing and permitting went into that first shipment. Now, after ten operating years, WIPP has demonstrated that deep geologic disposal of long-lived radioactive waste is not only feasible, it has also shown that it can be accomplished safely and efficiently. This paper presents the lessons learned from ten years of operations. It describes the issues of keeping the pipeline full, so that disposal operations progress smoothly. Balancing the various generator site's waste removal priorities (risk reduction) with characterization and transportation resources requires constant communication between WIPP and the Department of Energy (DOE) TRU waste complex. The paper describes the changes that had to be made to authorize Remote Handled (RH) TRU waste operations, and the difficulty in balancing CH and RH waste receipt rates to avoid losing disposal capacity. As a licensed and permitted facility, all WIPP operations are in a constant state of oversight. This oversight is spread across numerous organizations and effectively results in competition. The WIPP project is one of the most scrutinized operations in the DOE and substantial resources are needed to satisfy the information requirements resulting from the oversight. Finally, the paper looks to the next ten years of WIPP operations. With a freshly re-permitted and re-licensed regulatory regime, and with the easily characterized waste streams already emplaced, the goal will be to keep the pipeline filled. New and more difficult waste streams will make the road to WIPP disposal more challenging. (authors)

  8. Carlsbad Area Office Waste Isolation Division Transition Plan

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    In October 1993, the US Department of Energy (DOE) announced the Revised Test Strategy for the Waste Isolation Pilot Plant (WIPP). The new strategy involves conducting additional radioactive waste tests in laboratories instead of the underground at the WIPP. It will likely result in an acceleration of regulatory compliance activities needed for a disposal decision, which could result in permanent disposal of transuranic waste earlier than the previous test program and regulatory compliance strategy. The Revised Test Strategy changes the near-term program activities for the WIPP site. The revised strategy deletes radioactive waste tests at the WIPP, prior to completing all activities for initiating disposal operations, and consequently the need to maintain readiness to receive waste in the near-term. However, the new strategy enables the DOE to pursue an earlier disposal decision, supported by an accelerated regulatory compliance strategy. With the new strategy, the WIPP must prepare for disposal operations in early 1998. This Westinghouse Waste Isolation Division (WID) Transition Plan addresses the WID programmatic, budgetary, and personnel changes to conform to the Revised Test Strategy, and to support the accelerated compliance strategy and earlier disposal operations at the WIPP.

  9. Carlsbad Area Office Waste Isolation Division Transition Plan

    International Nuclear Information System (INIS)

    In October 1993, the US Department of Energy (DOE) announced the Revised Test Strategy for the Waste Isolation Pilot Plant (WIPP). The new strategy involves conducting additional radioactive waste tests in laboratories instead of the underground at the WIPP. It will likely result in an acceleration of regulatory compliance activities needed for a disposal decision, which could result in permanent disposal of transuranic waste earlier than the previous test program and regulatory compliance strategy. The Revised Test Strategy changes the near-term program activities for the WIPP site. The revised strategy deletes radioactive waste tests at the WIPP, prior to completing all activities for initiating disposal operations, and consequently the need to maintain readiness to receive waste in the near-term. However, the new strategy enables the DOE to pursue an earlier disposal decision, supported by an accelerated regulatory compliance strategy. With the new strategy, the WIPP must prepare for disposal operations in early 1998. This Westinghouse Waste Isolation Division (WID) Transition Plan addresses the WID programmatic, budgetary, and personnel changes to conform to the Revised Test Strategy, and to support the accelerated compliance strategy and earlier disposal operations at the WIPP

  10. Waste Isolation Pilot Plant 2003 Site Environmental Report

    International Nuclear Information System (INIS)

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] 10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by

  11. Waste Isolation Pilot Plant 2003 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2005-09-03

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by

  12. Radioactive and nonradioactive waste intended for disposal at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Transuranic (TRU) waste generated by the handling of plutonium in research on or production of US nuclear weapons will be disposed of in the Waste Isolation Pilot Plant (WIPP). This paper describes the physical and radiological properties of the TRU waste that will be deposited in the WIPP. This geologic repository will accommodate up to 175,564 m3 of TRU waste, corresponding to 168,485 m3 of contact-handled (CH-) TRU waste and 7,079 m3 of remote-handled (RH-) TRU waste. Approximately 35% of the TRU waste is currently packaged and stored (i.e., legacy) waste, with the remainder of the waste to be packaged or generated and packaged in activities before the year 2033, the closure time for the repository. These wastes were produced at 27 US Department of Energy (DOE) sites in the course of generating defense nuclear materials. The radionuclide and nonradionuclide inventories for the TRU wastes described in this paper were used in the 1996 WIPP Compliance Certification Application (CCA) performance assessment calculations by Sandia National Laboratories/New Mexico (SNL/NM)

  13. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

  14. Continued oversight of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The United States Environmental Protection Agency (EPA) developed environmental standards applicable to the disposal of defence-related transuranic wastes at the US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). By statute, EPA also serves as the regulator and implements these standards at WIPP, which has been in operation since 1999. The general environmental standards are set forth in the Agency's 40 Code of Federal Regulations (CFR), Part 191 Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (US NARA, 1985). These standards are implemented by site-specific compliance criteria at 40 CFR 194 (US NARA, 1996). The repository waste area is ∼650 meters below ground surface in a thick bedded salt formation that dips from west to east at ∼1 deg.. WIPP is located in the Chihuahuan Desert of south-eastern New Mexico, where the annual precipitation averages between 25 and 40 centimetres and there is high evapotranspiration. Much of the area around WIPP is federal land, managed by the Bureau of Land Management, and the area is sparsely populated. The transuranic waste disposed of at WIPP consists of materials such as radioactive sludges, soils and laboratory materials (e.g. chemical mixtures, contaminated glove boxes, paper and glass). Wastes are typically not treated unless necessary for shipping purposes (e.g. to limit hydrogen build-up). The waste is contaminated with plutonium, americium and other radionuclides, including some caesium and strontium. Transuranic waste is defined as waste with radionuclides heavier than uranium containing more than 3 700 Bq (100 nanocuries) of alpha-emitting transuranic isotopes per gram of waste; isotopes must have half-lives greater than 20 years. The WIPP Land Withdrawal Act limits the total disposal volume to ∼177 000 cubic meters (6.2 million cubic feet) and creates two categories of waste based on operational

  15. Waste Isolation Pilot Plant 1999 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Roy B.; Adams, Amy; Martin, Don; Morris, Randall C.; Reynolds, Timothy D.; Warren, Ronald W.

    2000-09-30

    The U.S. Department of Energy's (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

  16. The Waste Isolation Pilot Plant transportation system - dedicated to safety

    International Nuclear Information System (INIS)

    The purpose of this paper is to describe the development by the U.S. Department of Energy (DOE) of a first-of-a-kind transportation system. The total transport package includes a specially designed trailer, lightweight tractor, and type B container. In the development effort, the DOE has been exceptionally sensitive to public concerns and the need for safety in the transport of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) site. Measures taken in the development of the transport system exceed all existing requirements and, in the interest of public safety, incorporate all precautionary measures possible

  17. The Waste Isolation Pilot Plant status and related socioeconomic impacts

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) has been ''authorized as a defense activity of the Department of Energy...for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States...'' (PL 96-164). As reported in previous conferences, WIPP continues ahead of schedule and below budget with full facility construction well underway. To date, based on recent review, the socioeconomic impacts have been negligible and steps have been taken to ensure that they remain that way throughout operations

  18. The waste isolation pilot plant regulatory compliance program

    International Nuclear Information System (INIS)

    The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional mandate to open the WIPP in as short a time as possible, thereby initiating the process of addressing this nation's transuranic (TRU) waste problem. The DOE responded to the LWA by shifting the priority at the WIPP from scientific investigations to regulatory compliance and the completion of prerequisites for the initiation of operations. Regulatory compliance activities have taken four main focuses: (1) preparing regulatory submittals; (2) aggressive schedules; (3) regulator interface; and (4) public interactions

  19. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services (WRES)

    2004-10-25

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

  20. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

  1. Final environmental impact statement. Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text

  2. Final environmental impact statement. Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text.

  3. Geohydrological studies for nuclear waste isolation at the Hanford Reservation. Volume I. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Apps, J.; Doe, T.; Doty, B.

    1979-08-01

    A study of the hydrology of the Pasco Basin near Richland, Washington, was initiated during FY 1978 as part of a long-term study on the feasibility of nuclear waste disposal in the Columbia River Basalt underlying the Hanford Reservation. This report summarizes the hydrology field program, Pasco Basin modeling, and groundwater chemistry program. Hanford well logs are also reviewed. (DLC)

  4. Geohydrological studies for nuclear waste isolation at the Hanford Reservation. Volume I. Executive summary

    International Nuclear Information System (INIS)

    A study of the hydrology of the Pasco Basin near Richland, Washington, was initiated during FY 1978 as part of a long-term study on the feasibility of nuclear waste disposal in the Columbia River Basalt underlying the Hanford Reservation. This report summarizes the hydrology field program, Pasco Basin modeling, and groundwater chemistry program. Hanford well logs are also reviewed

  5. Regulatory basis for the Waste Isolation Pilot Plant performance assessment

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191, and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996, the DOE submitted its Compliance Certification Application (CCA) to the EPA to demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP's compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal

  6. Regulatory basis for the Waste Isolation Pilot Plant performance assessment

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191. and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996. the DOE submitted its Compliance Certification Application (CCA) to the EPA to demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP'S compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal

  7. The Westinghouse Waste Isolation Division Management and Supervisor Training Program

    International Nuclear Information System (INIS)

    The Westinghouse Waste Isolation Division (WID) is the management and operating contractor (MOC) for the Department of Energy's (DOE's) Waste Isolation Plant (WIPP). Managers and supervisors at DOE facilities such as the WIPP are required to complete extensive training. To meet this requirement, WID created a self-paced, self-study program known as Management and Supervisor Training (MAST). All WID managers and supervisors are required to earn certification through the MAST program. Selected employees are permitted to participate in MAST with prior approval from their manager and the Human Resources Manager. Initial MAST certification requires the completion of 31 modules. MAST participants check out modules and read them when convenient. When they are prepared, participants take module examinations. To receive credit for a given module, participants must score at least 80 percent on the examination. Lessons learned from the development, implementation, and administration are presented in this paper

  8. Basaltic glasses from Iceland and the deep sea: Natural analogues to borosilicate nuclear waste-form glass

    International Nuclear Information System (INIS)

    The report provides a detailed analysis of the alteration process and products for natural basaltic glasses. Information of specific applicability to the JSS project include: * The identification of typical alteration products which should be expected during the long-term corrosion process of low-silica glasses. The leached layers contain a relatively high proportion of crystalline phases, mostly in the form of smectite-type clays. Channels through the layer provide immediate access of solutions to the fresh glass/alteration layer interface. Thus, glasses are not 'protected' from further corrosion by the surface layer. * Corrosion proceeds with two rates - an initial rate in silica-undersaturated environments and a long-term rate in silica-saturated environments. This demonstrates that there is no unexpected change in corrosion rate over long periods of time. The long-term corrosion rate is consistent with that of borosilicate glasses. * Precipitation of silica-containing phases can result in increased alteration of the glass as manifested by greater alteration layer thicknesses. This emphasizes the importance of being able to predict which phases form during the reaction sequence. * For natural basaltic glasses the flow rate of water and surface area of exposed glass are critical parameters in minimizing glass alteration over long periods of time. The long-term stability of basalt glasses is enhanced when silica concentrations in solution are increased. In summary, there is considerable agreement between corrosion phenomena observed for borosilicate glasses in the laboratory and those observed for natural basalt glasses of great age. (With 121 refs.) (authors)

  9. Scientific, institutional, regulatory, political, and public acceptance of the waste isolation pilot plant transuranic waste repository

    International Nuclear Information System (INIS)

    The recent successful certification and opening of a first-of-a-kind, deep geological repository for safe disposal of long-lived, transuranic radioactive waste (TRUW) at the Waste Isolation Pilot Plant (WIPP) site, New Mexico, United States of America (USA), embody both long-standing local and wide-spread, gradually achieved, scientific, institutional, regulatory, political, and public acceptance. The related historical background and development are outlined and the main contributors to the successful siting, certification, and acceptance of the WIPP TRUW repository, which may also serve as a model to success for other radioactive waste disposal programs, are described. (author)

  10. Resource conversation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Volume II contains attachments for Module II and Module III. Attachments for Module II are: part A permit application; examples of acceptable documentation; Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program; inspection schedule and monitoring schedule; inspection log forms; personnel training course outlines; hazardous waste job position training requirements; contingency plan; closure plan; and procedures for establishing background for the underground units. One attachment, facility process information, is included for Module III. Remaining attachments for this module are in Volume III

  11. Waste isolation pilot plant (WIPP). EPA's regulatory approach

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) will contain transuranic (TRU) waste that has resulted from the United States' nuclear weapons programs. As independent regulator of the WIPP, the United States Environmental Protection Agency (USEPA) has the responsibilities of promulgating public health and environmental standards, determining if the WIPP meets the standards, certifying compliance of the WIPP, and periodically, re-evaluating the WIPP to assure continued compliance for meeting these standards. EPA has been successful in finalizing the Radioactive Waste Disposal Standards, proposing the Compliance Criteria, and implementing a process for achieving acceptance through the public participation process in the WIPP rulemaking. EPA has incorporated four guiding principles that are implemented in the regulatory process: the principles of protection, good science, consultation, and commitment. EPA will continue to regulate the WIPP efficiently and effectively to always protect the public health and the environment. (author)

  12. Bentonite as a waste isolation pilot plant shaft sealing material

    Energy Technology Data Exchange (ETDEWEB)

    Daemen, J.; Ran, Chongwei [Univ. of Nevada, Reno, NV (United States)

    1996-12-01

    Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites.

  13. Preliminary seal design evaluation for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    This report presents a preliminary evaluation of design concepts for the eventual sealing of the shafts, drifts, and boreholes at the Waste Isolation Pilot Plant Facility. The purpose of the seal systems is to limit the flow of water into, through, and out of the repository. The principal design strategy involves the consolidation of crushed or granular salt in response to the closure of the excavations in salt. Other candidate seal materials are bentonite, cementitious mixtures, and possibly asphalt. Results from in situ experiments and modeling studies, as well as laboratory materials testing and related industrial experience, are used to develop seal designs for shafts, waste storage panel entryways, non-waste containing drifts, and boreholes. Key elements of the ongoing experimental program are identified. 112 refs., 25 figs., 1 tab

  14. Bentonite as a waste isolation pilot plant shaft sealing material

    International Nuclear Information System (INIS)

    Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites

  15. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

    International Nuclear Information System (INIS)

    This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

  16. Waste Isolation Pilot Plant Safety Analysis Report. Volume 1

    International Nuclear Information System (INIS)

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection: Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating control and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  17. High level radioactive waste isolation by incorporation in silicate rock

    International Nuclear Information System (INIS)

    A number of technical possibilities for isolating high level radioactive materials have been theoretically investigated at various times and places. Isolating such wastes deep underground to insure long-term removal from the biosphere is one such possibility which has been investigated. The present concept involves as a first step creating the necessary void space at considerable depth, say 2 to 5 km, in a very low permeability silicate medium such as shale. Waste in dry, calcined or vitrified form is then lowered into the void space, and the access hole or shaft sealed. Energy released by the radioactive decay raises the temperature to a point where the surrounding rock begins to melt. The waste is then dissolved in it. The extent of this melt region grows until the heat generated is balanced by conduction away from the molten zone. Resolidification then begins, and ends when the radioactive decay has progressed to the point that the temperature falls below the melting point of the rock-waste solution. Calculations are presented showing the growth and resolidification process. The use of a nuclear explosion presents one alternative way of creating the void space

  18. Waste Isolation Pilot Plant Safety Analysis Report. Volume 4

    International Nuclear Information System (INIS)

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  19. Waste Isolation Pilot Plant Safety Analysis Report. Volume 5

    International Nuclear Information System (INIS)

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  20. Waste Isolation Pilot Plant Safety Analysis Report. Volume 2

    International Nuclear Information System (INIS)

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  1. Waste Isolation Pilot Plant Safety Analysis Report. Volume 3

    International Nuclear Information System (INIS)

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  2. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions

    2000-12-01

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period.

  3. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period

  4. Annotated bibliography of the geology of the Columbia Plateau (Columbia River Basalt) and adjacent areas of Oregon

    International Nuclear Information System (INIS)

    This bibliography containing approximately 2000 entries was prepared by the Oregon Department of Geology and Mineral Industries under Subcontract SA-913 with Rockwell Hanford Operations' Basalt Waste Isolation Program. The objective of the Basalt Waste Isolation Program is to determine the feasibility of storing nuclear waste within the Columbia River Basalt Group. Under the geologic portion of this program, the stratigraphic, structural, tectonic, seismic, and hydrologic aspects of the Columbia Plateau are being examined. Other aspects of the Basalt Waste Isolation Program are concerned with systems integration, engineered barriers, engineering testing, and construction of a near-surface test facility. The area covered in this bibliography comprises that area north of 43030' latitude and east of the Willamette Meridian, which is located just west of Portland. The bibliographic entries are presented in two forms. The first is an alphabetized listing of all articles dealing with the geology of the Columbia Plateau (Columbia River Basalt) and adjacent areas of Oregon. The second form consists of an alphabetized listing of the entries subdivided under fourteen categories

  5. Annotated bibliography of the geology of the Columbia Plateau (Columbia River Basalt) and adjacent areas of Oregon

    Energy Technology Data Exchange (ETDEWEB)

    Bela, J.

    1979-01-01

    This bibliography containing approximately 2000 entries was prepared by the Oregon Department of Geology and Mineral Industries under Subcontract SA-913 with Rockwell Hanford Operations' Basalt Waste Isolation Program. The objective of the Basalt Waste Isolation Program is to determine the feasibility of storing nuclear waste within the Columbia River Basalt Group. Under the geologic portion of this program, the stratigraphic, structural, tectonic, seismic, and hydrologic aspects of the Columbia Plateau are being examined. Other aspects of the Basalt Waste Isolation Program are concerned with systems integration, engineered barriers, engineering testing, and construction of a near-surface test facility. The area covered in this bibliography comprises that area north of 43/sup 0/30' latitude and east of the Willamette Meridian, which is located just west of Portland. The bibliographic entries are presented in two forms. The first is an alphabetized listing of all articles dealing with the geology of the Columbia Plateau (Columbia River Basalt) and adjacent areas of Oregon. The second form consists of an alphabetized listing of the entries subdivided under fourteen categories. (RWR)

  6. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first

  7. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Enviromnetal Services

    2009-09-21

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first

  8. Waste Isolation Pilot Plant 2001 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions, Inc.

    2002-09-20

    The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

  9. Waste Isolation Pilot Plant 2001 Site Environmental Report

    International Nuclear Information System (INIS)

    The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment

  10. Waste Isolation Pilot Plant CY 2000 Site Environmental Report

    International Nuclear Information System (INIS)

    The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no evidence was found of any adverse

  11. Waste Isolation Pilot Plant CY 2000 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

    2001-12-31

    The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no

  12. Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600-m-thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope--amounting to about a quarter million years, the time during which its activity will decline to background level--represent only 0.11% of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible

  13. Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600 m thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope - amounting to about a quarter million years, the time during which its activity will decline to background level represent only 0.11 percent of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible

  14. Assessment of effectiveness of geologic isolation systems. A conceptual simulation model for release scenario analysis of a hypothetical site in Columbia Plateau Basalts

    International Nuclear Information System (INIS)

    This report is a status report for an evolving methodology for release scenario development for underground nuclear waste repositories. As such, it is intended for use as a reference point and a preliminary description of an evolving geoscience methodology. When completed this methodology will be used as a tool in developing disruptive release scenarios for analyzing the long-term safety of geological nuclear waste repositories. While a basalt environment is used as an example, this report is not intended to reflect an actual site safety assessment for a repository in a media. It is rather intended to present a methodology system framework and to provide discussions of the geological phenomena and parameters that must be addressed in order to develop a methodology for potential release scenarios. It is also important to note that the phenomena, their interrelationships, and their relative importance along with the overall current structure of the model will change as new geological information is gathered through additional peer review, geotechnical input, site specific field work, and related research efforts

  15. Radiosensitivity of microorganisms isolated from radioactive waste repository

    International Nuclear Information System (INIS)

    Bacteria are much more diverse in comparison with plants and animals. Among the huge diversity of bacteria there are microorganisms capable to grow at or adapt to extreme conditions. Some bacteria grow at temperature above 100 deg. C, other thrive in high salinity such as 20-30% NaCl, still others can live at pH lower than 2 or pH higher than 10 or exhibit high radioresistance. Due to accelerated disarmament and nuclear energy activities, large quantities of radioactive waste and nuclear fuel are being placed in storage areas. The awareness the microbial activity could potentially effect the performance of a system for geological disposal of radioactive waste gained acceptance in the early to middle 1980s, and as a result many countries considering developing programmes to study and quantify microbial effects in terms of their own particular disposal concept. A new research programme was launched in 1995, sponsored by the NATO Scientific Affairs Division, for studying microbiologically influenced corrosion (MIC) in radioactive waste repositories and spent fuel storage area. Our programme concerns several major items that may have an influence on the mobility of radionuclides in direct and indirect ways thereby being important for the safety analysis. They are uptake and transport of radionuclides by microorganisms, diversity and distribution of subterranean bacteria in typical repository environments, environmental limitation and bacterial activity, effect of bacterial activity on the mobility of radionuclides, microbial gas production and consumption, bacterial recombination of hydrogen and oxygen from radiolysis, and microbially induced corrosion of waste canister. The Permian Boda Claystone Formation in the Mecsek Hill area is being considered for high level waste disposal. Groundwater, technical water, rock and surface samples were collected aseptically from different depths. The quantitative and qualitative analysis of aerobic and anaerobe isolates were

  16. Transporting transuranic waste to the Waste Isolation Pilot Plant: Risk and cost perspectives

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is an authorized US Department of Energy (DOE) research and development facility constructed near the city of Carlsbad in southeastern New Mexico. The facility is intended to demonstrate the safe disposal of transuranic (TRU) radioactive waste resulting from US defense activities. Under the WIPP Land Withdrawal Act of 1992 (LWA), federal lands surrounding the WIPP facility were withdrawn from all public use and the title of those lands was transferred to the Secretary of Energy. The DOE's TRU waste is stored, and in some cases is still being generated, at 10 large-quantity and 13 small-quantity sites across the US. After applicable certification requirements have been met, the TRU waste at these sites will be sent to the WIPP to initiate the disposal phase of the facility, which according to current planning is projected to last for approximately 35 years

  17. The waste isolation pilot plant project: a changing paradigm

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) repository that has been developed to demonstrate the safe and permanent isolation of transuranic radioactive wastes in a deep geologic site. It is located in 650 m below the surface in a bedded salt formation, and is designed to hold approximately 175,500 cubic meters of waste. Compliance with the regulations has become the principal focus for the Project. The scientific baseline is an important and integral part of the CCA, as it provides the foundation for conducting total system performance assessment calculations for comparison with applicable standards. The activities required to support the scientific baseline are being pursued in parallel to minimize the time required to collect, analyze, interpret and fully incorporate the results into the CCA. The DOE has shifted its approach to demonstrating compliance with the applicable regulations from a paradigm of a series of broad investigations to a new paradigm of highly focused activities conducted in parallel. The success of this approach will be assessed by the EPA when the application is critically reviewed

  18. Chemical and isotopic characterization of water-rock interactions in shales induced by the intrusion of a basaltic dike: A natural analogue for radioactive waste disposal

    International Nuclear Information System (INIS)

    Disposal of nuclear waste in deep geological formations is expected to induce thermal fluxes for hundreds of years with maximum temperature reaching about 100-150 deg. C in the nearfield argillaceous environment. The long-term behavior of clays subjected to such thermal gradients needs to be perfectly understood in safety assessment considerations. In this respect, a Toarcian argillaceous unit thermally disturbed by the intrusion of a 1.1-m wide basaltic dike at the Perthus pass (Herault, France), was studied in detail as a natural analogue. The thermal imprint induced by the dike was evaluated by a mineralogical, chemical and K-Ar study of the <2 μm clay fraction of shale samples collected at increasing distance from the basalt. The data suggest that the mineral composition of the shales was not significantly disturbed when the temperature was below 100-150 deg. C. Closer to the dike at 150-300 deg. C, changes such as progressive dissolution of chlorite and kaolinite, increased content of the mixed layers illite-smectite with more illite layers, complete decalcification and subsequent increased content of quartz, were found. At the eastern contact with the dike, the mineral and chemical compositions of both the shales and the basalt suggest water-rock interactions subsequent to the intrusion with precipitation of palagonite and renewed but discrete deposition of carbonate. A pencil cleavage developed in the shales during the dike emplacement probably favored water circulation along the contact. Strontium isotopic data suggest that the fluids of probable meteoric origin, reacted with Bathonian and Bajocian limestones before entering the underlying Toarcian shales. By analogy with deep geological radioactive waste repositories, the results report discrete mineralogical variations of the clays when subjected to temperatures of 100-150 deg. C that are expected in deep storage conditions. Beyond 150 deg. C, significant mineralogical changes may alter the physical and

  19. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Washinton TRU Solutions LLC

    2002-09-30

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2000, to March 31, 2002. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Field Office's (CBFO) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. In the prior BECR, the CBFO and the management and operating contractor (MOC)committed to discuss resolution of a Letter of Violation that had been issued by the New Mexico Environment Department (NMED) in August 1999, which was during the previous BECR reporting period. This Letter of Violation alleged noncompliance with hazardous waste aisle spacing, labeling, a nd tank requirements. At the time of publication of the prior BECR, resolution of the Letter of Violation was pending. On July 7, 2000, the NMED issued a letter noting that the aisle spacing and labeling concerns had been adequately addressed and that they were rescinding the violation alleging that the Exhaust Shaft Catch Basin failed to comply with the requirements for a hazardous waste tank. During the current reporting period, WIPP received a Notice of Violation and a compliance order alleging the violation of the New Mexico Hazardous Waste Regulations and the WIPP Hazardous Waste Facility Permit (HWFP).

  20. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2000, to March 31, 2002. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Field Office's (CBFO) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. In the prior BECR, the CBFO and the management and operating contractor (MOC)committed to discuss resolution of a Letter of Violation that had been issued by the New Mexico Environment Department (NMED) in August 1999, which was during the previous BECR reporting period. This Letter of Violation alleged noncompliance with hazardous waste aisle spacing, labeling, a nd tank requirements. At the time of publication of the prior BECR, resolution of the Letter of Violation was pending. On July 7, 2000, the NMED issued a letter noting that the aisle spacing and labeling concerns had been adequately addressed and that they were rescinding the violation alleging that the Exhaust Shaft Catch Basin failed to comply with the requirements for a hazardous waste tank. During the current reporting period, WIPP received a Notice of Violation and a compliance order alleging the violation of the New Mexico Hazardous Waste Regulations and the WIPP Hazardous Waste Facility Permit (HWFP)

  1. Compliance status report for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) is responsible for the disposition of transuranic (TRU) waste generated through national defense-related activities. Approximately 53,700 m2 of these wastes have been generated and are currently stored at government defense installations across the country. The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been sited and constructed to meet the criteria established by the scientific and regulatory community for the safe, long-term disposal of TRU and TRU-mixed wastes. This Compliance Status Report (CSR) provides an assessment of the progress of the WIPP Program toward compliance with long-term disposal regulations, set forth in Title 40 CFR 191 (EPA, 1993a), Subparts B and C, and Title 40 CFR section 268.6 (EPA, 1993b), in order to focus on-going and future experimental and engineering activities. The CSR attempts to identify issues associated with the performance of the WIPP as a long-term repository and to focus on the resolution of these issues. This report will serve as a tool to focus project resources on the areas necessary to ensure complete, accurate, and timely submittal of the compliance application. This document is not intended to constitute a statement of compliance or a demonstration of compliance

  2. A historical review of Waste Isolation Pilot Plant backfill development

    International Nuclear Information System (INIS)

    Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. Its introduction was motivated by the need to scavenging CO2 [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits

  3. A historical review of Waste Isolation Pilot Plant backfill development

    Energy Technology Data Exchange (ETDEWEB)

    KRUMHANSL,JAMES L.; MOLECKE,MARTIN A.; PAPENGUTH,HANS W.; BRUSH,LAURENCE H.

    2000-06-05

    Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. Its introduction was motivated by the need to scavenging CO{sub 2} [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits.

  4. Compliance status report for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-31

    The US Department of Energy (DOE) is responsible for the disposition of transuranic (TRU) waste generated through national defense-related activities. Approximately 53,700 m{sup 2} of these wastes have been generated and are currently stored at government defense installations across the country. The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been sited and constructed to meet the criteria established by the scientific and regulatory community for the safe, long-term disposal of TRU and TRU-mixed wastes. This Compliance Status Report (CSR) provides an assessment of the progress of the WIPP Program toward compliance with long-term disposal regulations, set forth in Title 40 CFR 191 (EPA, 1993a), Subparts B and C, and Title 40 CFR {section}268.6 (EPA, 1993b), in order to focus on-going and future experimental and engineering activities. The CSR attempts to identify issues associated with the performance of the WIPP as a long-term repository and to focus on the resolution of these issues. This report will serve as a tool to focus project resources on the areas necessary to ensure complete, accurate, and timely submittal of the compliance application. This document is not intended to constitute a statement of compliance or a demonstration of compliance.

  5. Data qualification for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) site near Carlsbad, New Mexico, has been the subject of scientific and engineering investigations for more than twenty years. Data from these investigations are now being used as part of the process to certify compliance of the WIPP with the governing regulations. Some of these data were collected prior to the development and implementation of the quality assurance (QA) standards that are now being applied in the WIPP compliance certification process, and are considered ''existing data'' within the current QA program. This paper discusses the process for qualification of existing data (QED) defined for the WIPP project, the implementation of that process, and some of the results. This process incorporates many lessons learned, and should be useful to others in the radioactive waste management system who are dealing with ''existing data.''

  6. Waste isolation safeguards and security system. Volume 1. Scoping study

    International Nuclear Information System (INIS)

    The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schedule and provides an extensive bibliography of applicable reference safeguards documents. Volume one contains the following: glossary, system description; threat definition; safeguards regulations review - current and future; WIS safeguards criteria; assessment of criteria applicability and development requirements; and program plan

  7. THERMODYNAMIC TABLES FOR NUCLEAR WASTE ISOLATION, V.1: AQUEOUSSOLUTIONS DATABASE

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, S.L.; Hale, F.V.; Silvester, L.F.

    1988-05-01

    Tables of consistent thermodynamic property values for nuclear waste isolation are given. The tables include critically assessed values for Gibbs energy of formation. enthalpy of formation, entropy and heat capacity for minerals; solids; aqueous ions; ion pairs and complex ions of selected actinide and fission decay products at 25{sup o}C and zero ionic strength. These intrinsic data are used to calculate equilibrium constants and standard potentials which are compared with typical experimental measurements and other work. Recommendations for additional research are given.

  8. Waste Isolation Pilot Plant Annual Site Environmental Report for 2012

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

  9. An assessment of the suitability of five overcoring techniques for stress determination in a jointed basalt

    International Nuclear Information System (INIS)

    Overcoring tests were conducted at the Near-Surface Test Facility (NSTF) using the US Bureau of Mines borehole deformation gauge, the C.S.I.R.O. hollow inclusion stress cell, the cast epoxy inclusion, the Lulea triaxial strain cell, and the C.S.I.R. ''doorstopper'' gauge to assess the suitability of each technique for in situ stress determination in a closely jointed basalt. This effort is in support of the Basalt Waste Isolation Project which is studying the feasibility of locating a nuclear waste repository in basalt. Testing at the NSTF provided information for the evaluation of overcoring techniques so that one or more can be selected to obtain in situ stress data at the reference repository horizon. Even though some problems were experienced, the borehole deformation gauge and doorstopper proved the most successful. 30 refs., 53 figs. 16 tabs

  10. Waste Isolation Pilot Plant No-migration variance petition. Addendum: Volume 7, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program.

  11. Application of ICRP recommendations to radioactive waste isolation

    International Nuclear Information System (INIS)

    Some radioactive waste categories require isolation from the biosphere for extended periods of time. Various mechanisms can be expected in the future leakage of radionuclides; some are the result of 'normal', expected processes, while others would be the result of random disruptive events. In the second case, the exposures can only be evaluated on a probabilistic basis. Nevertheless, the three basic principles for protection usually recommended by ICRP still apply: individual risk limitation, optimization of protection, and justification of practice. In the individual-related assessment, the requirement should be that the overall probability of death from exposure to waste products (considering both the probability of dose and the probability of death, given the dose) should not exceed the probability of death at the dose 'upper bound' that national authorities would designate for the practice. In the source-related assessment for optimization of protection, the detriment should be assessed over relevant time periods and be the basis for marginal cost-benefit analysis of the various potential improvements in the combined isolation provided by the engineering and geological features. (author)

  12. Geological problems in radioactive waste isolation - A world wide review

    Energy Technology Data Exchange (ETDEWEB)

    Witherspoon, P.A. [Lawrence Berkeley Lab., CA (United States)

    1991-06-01

    The problem of isolating radioactive wastes from the biosphere presents specialists in the earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high-level waste (HLW), which must be isolated in the underground and away from the biosphere for thousands of years. The most widely accepted method of doing this is to seal the radioactive materials in metal canisters that are enclosed by a protective sheath and placed underground in a repository that has been carefully constructed in an appropriate rock formation. Much new technology is being developed to solve the problems that have been raised, and there is a continuing need to publish the results of new developments for the benefit of all concerned. Table 1 presents a summary of the various formations under investigation according to the reports submitted for this world wide review. It can be seen that in those countries that are searching for repository sites, granitic and metamorphic rocks are the prevalent rock type under investigation. Six countries have developed underground research facilities that are currently in use. All of these investigations are in saturated systems below the water table, except the United States project, which is in the unsaturated zone of a fractured tuff.

  13. Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

    International Nuclear Information System (INIS)

    The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED)

  14. Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2003-09-17

    The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED).

  15. Geological challenges in radioactive waste isolation: Third worldwide review

    Energy Technology Data Exchange (ETDEWEB)

    Witherspoon Editor, P.A.; Bodvarsson Editor, G.S.

    2001-12-01

    The broad range of activities on radioactive waste isolation that are summarized in Table 1.1 provides a comprehensive picture of the operations that must be carried out in working with this problem. A comparison of these activities with those published in the two previous reviews shows the important progress that is being made in developing and applying the various technologies that have evolved over the past 20 years. There are two basic challenges in perfecting a system of radioactive waste isolation: choosing an appropriate geologic barrier and designing an effective engineered barrier. One of the most important developments that is evident in a large number of the reports in this review is the recognition that a URL provides an excellent facility for investigating and characterizing a rock mass. Moreover, a URL, once developed, provides a convenient facility for two or more countries to conduct joint investigations. This review describes a number of cooperative projects that have been organized in Europe to take advantage of this kind of a facility in conducting research underground. Another critical development is the design of the waste canister (and its accessory equipment) for the engineered barrier. This design problem has been given considerable attention in a number of countries for several years, and some impressive results are described and illustrated in this review. The role of the public as a stakeholder in radioactive waste isolation has not always been fully appreciated. Solutions to the technical problems in characterizing a specific site have generally been obtained without difficulty, but procedures in the past in some countries did not always keep the public and local officials informed of the results. It will be noted in the following chapters that this procedure has caused some problems, especially when approval for a major component in a project was needed. It has been learned that a better way to handle this problem is to keep all

  16. Geological challenges in radioactive waste isolation: Third worldwide review

    International Nuclear Information System (INIS)

    The broad range of activities on radioactive waste isolation that are summarized in Table 1.1 provides a comprehensive picture of the operations that must be carried out in working with this problem. A comparison of these activities with those published in the two previous reviews shows the important progress that is being made in developing and applying the various technologies that have evolved over the past 20 years. There are two basic challenges in perfecting a system of radioactive waste isolation: choosing an appropriate geologic barrier and designing an effective engineered barrier. One of the most important developments that is evident in a large number of the reports in this review is the recognition that a URL provides an excellent facility for investigating and characterizing a rock mass. Moreover, a URL, once developed, provides a convenient facility for two or more countries to conduct joint investigations. This review describes a number of cooperative projects that have been organized in Europe to take advantage of this kind of a facility in conducting research underground. Another critical development is the design of the waste canister (and its accessory equipment) for the engineered barrier. This design problem has been given considerable attention in a number of countries for several years, and some impressive results are described and illustrated in this review. The role of the public as a stakeholder in radioactive waste isolation has not always been fully appreciated. Solutions to the technical problems in characterizing a specific site have generally been obtained without difficulty, but procedures in the past in some countries did not always keep the public and local officials informed of the results. It will be noted in the following chapters that this procedure has caused some problems, especially when approval for a major component in a project was needed. It has been learned that a better way to handle this problem is to keep all

  17. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

  18. Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan

    International Nuclear Information System (INIS)

    The ONWI Socioeconomic Program Plan spells out DOE's approach to analyzing the socioeconomic impacts from siting, constructing, and operating radioactive waste repositories and discusses mitigation strategies. The peer review indicated the following modifications should be made to the Plan: encourage active public participation in the decision-making processes leading to repository site selection; clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process; place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; recognize that mitigation mechanisms other than compensation and incentives may be effective; as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and comply fully with the pertinent provisions of NWPA

  19. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2006-10-12

    This Biennial Environmental Compliance Report (BECR) documents compliance with environmental regulations at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste. This BECR covers the reporting period from April 1, 2004, to March 31, 2006. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents United States (U.S.) Department of Energy (DOE) compliance with regulations and permits issued pursuant to the following: (1) Title 40 Code of Federal Regulations (CFR) Part 191, Subpart A, "Environmental Standards for Management and Storage"; (2) Clean Air Act (CAA) (42 United States Code [U.S.C.] §7401, et seq.); (3) Solid Waste Disposal Act (SWDA) (42 U.S.C. §§6901-6992, et seq.); (4) Safe Drinking Water Act (SDWA) (42 U.S.C. §§300f, et seq.); (5) Toxic Substances Control Act (TSCA) (15 U.S.C. §§2601, et seq.); (6) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (42 U.S.C. §§9601, et seq.); and all other federal and state of New Mexico laws pertaining to public health and safety or the environment.

  20. Summary of scientific investigations for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The scientific issues concerning disposal of radioactive wastes in salt formations have received 40 years of attention since the National Academy of Sciences (NAS) first addressed this issue in the mid-50s. For the last 21 years, Sandia National Laboratories (SNL) have directed site specific studies for the Waste Isolation Pilot Plant (WIPP). This paper will focus primarily on the WIPP scientific studies now in their concluding stages, the major scientific controversies regarding the site, and some of the surprises encountered during the course of these scientific investigations. The WIPP project's present understanding of the scientific processes involved continues to support the site as a satisfactory, safe location for the disposal of defense-related transuranic waste and one which will be shown to be in compliance with Environmental Protection Agency (EPA) standards. Compliance will be evaluated by incorporating data from these experiments into Performance Assessment (PA) models developed to describe the physical and chemical processes that could occur at the WIPP during the next 10,000 years under a variety of scenarios. The resulting compliance document is scheduled to be presented to the EPA in October 1996 and all relevant information from scientific studies will be included in this application and the supporting analyses. Studies supporting this compliance application conclude the major period of scientific investigation for the WIPP. Further studies will be of a ''confirmatory'' and monitoring nature

  1. Experimental program plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included

  2. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    This Biennial Environmental Compliance Report (BECR) documents compliance with environmental regulations at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste. This BECR covers the reporting period from April 1, 2004, to March 31, 2006. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents United States (U.S.) Department of Energy (DOE) compliance with regulations and permits issued pursuant to the following: (1) Title 40 Code of Federal Regulations (CFR) Part 191, Subpart A, 'Environmental Standards for Management and Storage'; (2) Clean Air Act (CAA) (42 United States Code [U.S.C.] 7401, et seq.); (3) Solid Waste Disposal Act (SWDA) (42 U.S.C. 6901-6992, et seq.); (4) Safe Drinking Water Act (SDWA) (42 U.S.C. 300f, et seq.); (5) Toxic Substances Control Act (TSCA) (15 U.S.C. 2601, et seq.); (6) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (42 U.S.C. 9601, et seq.); and all other federal and state of New Mexico laws pertaining to public health and safety or the environment.

  3. The waste isolation pilot plant transuranic waste repository: A case study in radioactive waste disposal safety and risk

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) deep geological defense-generated transuranic radioactive waste (TRUW) repository in the United States was certified on the 13 of May 1998 and opened on the 26 of March 1999. Two sets of safety/performance assessment calculations supporting the certification of the WIPP TRUW repository show that the maximum annual individual committed effective dose will be 32 times lower than the regulatory limit and that the cumulative amount of radionuclide releases will be at least 10 times, more likely at least 20 times, lower than the regulatory limits. Yet, perceptions remain among the public that the WIPP TRUW repository imposes an unacceptable risk

  4. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

  5. Hydrologic bibliography of the Columbia River basalts in Washington with selected annotations

    International Nuclear Information System (INIS)

    The objective of this compilation is to present a comprehensive listing of the published, unpublished, and open file references pertaining to the surface and subsurface hydrology of the Columbia River basalts within the State of Washington and is presented in support of Rockwell's hydrologic data compilation effort for the Basalt Waste Isolation Program. A comprehensive, annotated bibliography of the Pasco Basin (including the Hanford Site) hydrology has been prepared for Rockwell as part of the Pasco Basin hydrology studies. In order to avoid unnecessary duplication, no effort was made to include a complete list of bibliographic references on Hanford in this volume

  6. Proceedings of the Task 2 workshop Waste Isolation Safety Assessment Program

    International Nuclear Information System (INIS)

    The reports from the workshop on waste form release rate analysis are presented. The workshop started with overview presentations on the Office of Nuclear Waste Isolation (ONWI), the Waste Isolation Safety Assessment Program (WISAP), WISAP Task 2 (Waste Form Release Rate Analysis), and WISAP Task 4 (Sorption/Desorption Analysis). Technical presentations followed in these areas: leaching studies on spent fuels, leaching studies on high-level waste glass, waste form surface science experiments, radiation effects, and leach modeling. Separate abstracts were prepared for each

  7. Results from simulated remote-handled transuranic waste experiments at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Multi-year, simulated remote-handled transuranic waste (RH TRU, nonradioactive) experiments are being conducted underground in the Waste Isolation Pilot-Plant (WIPP) facility. These experiments involve the near-reference (thermal and geometrical) testing of eight full size RH TRU test containers emplaced into horizontal, unlined rock salt boreholes. Half of the test emplacements are partially filled with bentonite/silica-sand backfill material. All test containers were electrically heated at about 115 W/each for three years, then raised to about 300 W/each for the remaining time. Each test borehole was instrumented with a selection of remote-reading thermocouples, pressure gages, borehole vertical-closure gages, and vertical and horizontal borehole-diameter closure gages. Each test emplacements was also periodically opened for visual inspections of brine intrusions and any interactions with waste package materials, materials sampling, manual closure measurements, and observations of borehole changes. Effects of heat on borehole closure rates and near-field materials (metals, backfill, rock salt, and intruding brine) interactions were closely monitored as a function of time. This paper summarizes results for the first five years of in situ test operation with supporting instrumentation and laboratory data and interpretations. Some details of RH TRU waste package materials, designs, and assorted underground test observations are also discussed. Based on the results, the tested RH TRU waste packages, materials, and emplacement geometry in unlined salt boreholes appear to be quite adequate for initial WIPP repository-phase operations

  8. Risk assessment for waste emplacement at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Administered by the Carlsbad Area Office, the Waste Isolation Pilot Plant (WIPP) is designed to permanently dispose of transuranic waste left from US nuclear weapons research and production. Project facilities, located 26 miles east of Carlsbad, New Mexico, include disposal rooms mined 2,150 feet beneath the earth's surface in a stable, ancient salt formation. The US Department of Energy has established and analyzed the safety basis for handling and emplacement of contact-handled transuranic waste for disposal at the WIPP. The safety basis consists of management, design, construction, operation, and engineering characteristics necessary to protect the public, workers, and environment from the safety and health hazards posed by waste handling and emplacement operations. An assessment of hazards and the associated risk to safety was included in the effort. The hazard assessment technique used at the WIPP is a creative systematic interaction of a multi-disciplinary team that could be applied to other waste management activities. The qualitative assessment approach, which ranks hazards by likelihood and significance of consequence, would be useful for a wide range of risk analysis efforts. Hazards were systematically identified and assessed to evaluate the potential internal, external, and natural phenomena events that can cause the identified hazards to develop into accidents. The hazard assessment employed at the WIPP identified deviations from the intended design and operation of the waste handling system, analyzed potential accident consequences to the public and workers, estimated likelihood of occurrence, and evaluated associated preventative and mitigative features. It was concluded from the assessment that proposed WIPP waste emplacement operations and design are sufficient to ensure safety of the public, workers, and environment

  9. Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot

    International Nuclear Information System (INIS)

    The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ''near-reference'' with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed

  10. Sociocultural analysis for the proposed Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    In order to assess the potential or perceived sociocultural impact due to the construction and operation of the proposed Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico, a discussion-type survey was conducted in August and September of 1979. During those two months four researchers conducted probing-type discussions with nearly 200 Carlsbad area residents. The results of those discussions were analyzed for inclusion in the WIPP Final Environmental Impact Statement. The impacts on sociocultural aspects perceived by the residents included both positive and negative impacts. The most frequently mentioned positive impacts were new jobs, increased activity in business sectors and the housing industry, and new residents to the area. Negative impacts included perceived inflation or price increases, strained services and community infrastructure, attraction of transient construction workers, safety and health risks, and unequal distribution of benefits and costs. 2 tables

  11. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions

    2002-09-24

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

  12. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    The DOE has mandated in DOE Order 5400.1 that its operations will be conducted in an environmentally safe manner. The Waste Isolation Pilot Plant (WIPP) will comply with DOE Order 5400.1 and will conduct its operations in a manner that ensures the safety of the environment and the public. This document outlines how the WIPP will protect and preserve groundwater within and surrounding the WIPP facility. Groundwater protection is just one aspect of the WIPP environmental protection effort. The WIPP groundwater surveillance program is designed to determine statistically if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will be determined and appropriate corrective action initiated

  13. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP

  14. Waste Isolation Pilot Plant Annual Site Environmental Report for 2010

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  15. Waste Isolation Pilot Plant Land Withdrawal Act of 1988

    International Nuclear Information System (INIS)

    The Committee on Energy and Natural Resources reports on the Bill S. 1272 and recommends passage of the bill as amended by the Committee. S. 1272 as amended withdraws 10,240 acres of land in Eddy county, New Mexico for the exclusive use of the Department of Energy (DOE) for construction, operation, decommissioning and post-decommissioning control of the Waste Isolation Pilot Plant (WIPP). The lands, currently managed by the Department of the Interior, would be permanently withdrawn and transferred to the control of DOE. The bill sets forth specific instructions to the Secretary of Energy to preserve the ecology of these lands and mandates compliance with standards of the Environmental Protection Agency (EPA) for storage and disposal of transuranium radioactive waste as set forth in 40 C.F.R. Part 191. In addition to the section-by-section analysis of the bill, a cost estimate from the Congressional Budget Office and copies of communications received by the Committee from DOE and the Department of the Interior setting forth executive recommendations relating to the bill are included

  16. Waste Isolation Pilot Plant: Draft Supplement Environmental Impact Statement

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) has prepared this supplement to the 1980 Final Environmental Impact Statement (FEIS) for the Waste Isolation Pilot Plant (WIPP) in order to assess the environmental impacts that may occur from the continued development of the WIPP as a minced geologic repository for transuranic (TRU) waste. Since the publication of the FEIS in October 1980, new data collected at the WIPP have led to changes in the understanding of the hydrogeologic characteristics of the area and their potential implications for the long-term performance of the WIPP. In addition, there have been changes in the FEIS Proposed Action and new regulatory requirements. This supplement to the FEIS (SEIS) evaluates the environmental consequences of the Proposed Action as modified since 1980 in light of new data and assumptions. The new information pertains mainly to the geologic and hydrologic systems at the WIPP site and their effect on the long-term performance of the WIPP. The SEIS includes new data indicating that: the permeability of the Salado Formation, the geologic formation in which the WIPP underground facilities are located, is lower than previously believed; the moisture content of the Salado Formation and the consequent brine inflow is higher than previously believed; a higher transmissivity zone is present in the Rustler Formation in the southeastern portion of the WIPP site; and ''salt creep'' (convergence) in the repository occurs faster than previously believed. 50 figs., 92 tabs

  17. Groundwater monitoring at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    This paper discusses the Groundwater Monitoring Program (GPM) being conducted at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The Regulatory and Environmental Programs (REP) section of the Environment, Safety and Health department (ES ampersand H) is responsible for conducting environmental monitoring at the WIPP. Groundwater monitoring is one of the ongoing environmental activities currently taking place. The REP section includes water quality sampling and water level monitoring. The WIPP Project is a research and develop facility designed to demonstrate the safe disposal of defense-generated waste in a geologic repository. Water quality sampling for physical, chemical, and radiological parameters has been an ongoing activity at the WIPP site for the past six years, and will continue through the life of the project. The water quality of a well is sampled while the well is continuously pumped. Serial samples of the pumped water are collected and tested for pH, Eh, temperature, specific gravity, specific conductivity, alkalinity, chlorides, divalent cations, ferrous iron, and total iron. Stabilization of serial sampling parameters determined if a representative sample is being obtained, Representative samples are sent to contract laboratories and analyzed for general chemistry, major cations and anions, and radionuclides. 13 refs., 4 figs., 1 tab

  18. Waste Isolation Pilot Plant Annual Site Environmental Report for 2010

    Energy Technology Data Exchange (ETDEWEB)

    None

    2011-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  19. The Waste Isolation Pilot Plant (WIPP) integrated project management system

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission of demonstrating the safe disposal of transuranic (TRU) radioactive wastes. This unique project was authorized by Congress in 1979 in response to the national need for long-term, safe methods for disposing of radioactive by-products from our national defense programs. The WIPP was originally established in December of 1979, by Public Law 96-164, DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980. Since the inception of the WIPP Project, work has continued to prepare the facility to receive TRU wastes. Studies continue to be conducted to demonstrate the safety of the WIPP facility in accordance with federal and state laws, state agreements, environmental regulations, and DOE Orders. The objectives of implementing an integrated project management system are to assure compliance with all regulatory and federal regulations, identify areas of concern, provide justification for funding, provide a management tool for control of program workscope, and establish a project baseline from which accountability and performance will be assessed. Program management and project controls are essential for the success of the WIPP Project. The WIPP has developed an integrated project management system to establish the process for the control of the program which has an expected total dollar value of $2B over the ten-year period from 1990-2000. The implementation of this project management system was motivated by the regulatory requirements of the project, the highly public environment in which the project takes place, limited funding and resources, and the dynamic nature of the project. Specific areas to be addressed in this paper include strategic planning, project organization, planning and scheduling, fiscal planning, and project monitoring and reporting

  20. Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    RECHARD,ROBERT P.; SANCHEZ,LAWRENCE C.; STOCKMAN,CHRISTINE T.; TRELLUE,HOLLY R.

    2000-04-01

    Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low.

  1. Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low

  2. Potential for long-term isolation by the Waste Isolation Pilot Plant disposal system

    Energy Technology Data Exchange (ETDEWEB)

    Bertram-Howery, S.G. (Sandia National Labs., Albuquerque, NM (USA)); Swift, P.N. (Tech. Reps., Inc., Albuquerque, NM (USA))

    1990-06-01

    The US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) must comply with EPA regulation 40 CFR Part 191, Subpart B, which sets environmental standards for radioactive waste disposal. The regulation, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (hereafter referred to as the Standard), was vacated in 1987 by a Federal Court of Appeals and is underground revision. By agreement with the Sate of New Mexico, the WIPP project is evaluating compliance with the Standard as promulgated, in 1985 until a new regulation is available. This report summarizes the early-1990 status of Sandia National Laboratories' (SNL) understanding of the Project's ability to achieve compliance. The report reviews the qualitative and quantitative requirements for compliance, and identifies unknowns complicating performance assessment. It discusses in relatively nontechnical terms the approaches to resolving those unknowns, and concludes that SNL has reasonable confidence that compliance is achievable with the Standard as first promulgated. 46 refs., 7 figs.

  3. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New Mexico Administrative Code), 'Adoption of 40 CFR [Code of Federal Regulations] Part 264,'specifically 40 CFR 264.90 through 264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] 6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  4. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2005-07-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  5. Hydrogeology problems in high level radioactive waste isolation

    International Nuclear Information System (INIS)

    The problem of isolating high level radioactive waste in underground repositories presents the hydrogeologist with some of the most difficult problems that have been encountered in the field of earth sciences. This paper presents a brief review of the different rock types that are currently being investigated for their potential use in waste repositories. Granitic rocks have been studied more than any other rock type in many parts of the world, but the presence of discontinuities such as joints and fractures in this type of rock creates a formidable problem. There are two fundamental components to this problem: the factors that control the flow of fluids through a single fracture, and the factors that control the overall permeability of a fractured rock mass. Much work has been carried out in developing an understanding of fluid flow in a single fracture. The well known cubic law can only be used to describe this flow when the aperature is relatively large. As a fracture closes under stress, a complicated flow geometry develops, and the flux decreases much more rapidly than would be predicted by the cubic law. The flow is restricted to tortuous channels that apparently cannot be closed even at high stress levels. In evaluating the overall permeability of a fractured rock mass, the basic problem is that of determining the continuity of the fractures. Standard methods of fracture mapping to locate the system of discontinuities can be improved using seismic and radar tomography. A new procedure of determining the connectivity and permeability of a fractured rock mass is described that is based on an inverse technique involving a process of simulated annealing

  6. Isolation and characterisation of circoviruses from pigs with wasting syndromes in Spain, Denmark and Northern Ireland

    DEFF Research Database (Denmark)

    Allan, G.M.; Mc Neilly, F.; Meehan, B.M.; Kennedy, S.; Mackie, D.P.; Ellis, J.A.; Clark, E.G.; Espuna, E.; Saubi, N.; Riera, P.; Bøtner, Anette; Charreyre, C.E.

    1999-01-01

    A porcine circovirus (PCV) was isolated from tissues of pigs with wasting syndromes from Spain, Denmark and N. Ireland. The antigenic profiles of these viruses were determined by indirect immunofluorescence assays using polyclonal antisera and monoclonal antibodies (mAbs) prepared against...... previously isolated PCVs. A rapid and convenient PCR-based test was developed and used for the genotyping of these PCV isolates. These PCV isolates were found to be antigenically and genomically similar to previously reported isolates of PCV from pigs with wasting disease (PCV2), but distinct from the...

  7. Design and installation of deep multilevel piezometer nests in Columbia River basalts at the Hanford Site, Washington

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project (BWIP) was established in 1976 as part of the National Waste Terminal Storage Program, now the Office of Civilian Radioactive Waste Management. The BWIP objective is to assess the suitability of basalt as a repository medium for the long-term storage of commercial high-level radioactive waste. As part of the hydrogeologic characterization activities, BWIP designed and installed multilevel piezometer nests at three borehole cluster sites within and adjacent to the 18-square-mile reference repository location. These borehole cluster sites will provide multilevel piezometric baseline data across the reference repository location prior to, during, and after drilling a large-diameter exploratory shaft. They will also be used to monitor future hydraulic stress tests on a large scale. Three series of piezometer nests (A-, C-, and D-series) were installed at three borehole cluster sites in nine hydrogeologic units from a depth of about 500 to 3700 feet within the Columbia River Basalt Group. These multilevel monitoring zones are isolated from each other and the next overlying hydrogeologic unit by high-density cement seals. The A-series piezometer nests monitor two shallow sedimentary units. The C-series piezometer nests monitor basalt flow tops in the six deepest zones. The D-series piezometer monitors an intermediate sedimentary unit. Each piezometer tube was developed by air-lift pumping to complete the installtion prior to installing downhole pressure transducers. 23 refs., 10 figs., 1 tab

  8. Hazard and consequence analysis for waste emplacement at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Carlsbad Area Office established and analyzed the safety bases for the design and operations as documented in the WIPP Safety Analysis Report (SAR). Additional independent efforts are currently underway to assess the hazards associated with the long-term (10,000 year) isolation period as required by 40 CFR 191. The structure of the WIPP SAR is unique due to the hazards involved, and the agreement between the State of New Mexico and the DOE regarding SAR content and format. However, the hazards and accident analysis philosophy as contained in DOE-STD-3009-94 was followed as closely as possible, while adhering to state agreements. Hazards associated with WIPP waste receipt, emplacement, and disposal operations were systematically identified using a modified Hazard and Operability Study (HAZOP) technique. The WIPP HAZOP assessed the potential internal, external, and natural phenomena events that can cause the identified hazards to develop into accidents. The hazard assessment identified deviations from the intended design and operation of the waste handling system, analyzed potential accident consequences to the public and workers, estimated likelihood of occurrence, and evaluated associated preventative and mitigative features. It was concluded from the assessment that the proposed WIPP waste emplacement operations and design are sufficient to ensure safety of the public, workers, and environment, over the 35 year disposal phase

  9. Investigations of deteriorated concrete from the liner of the Waste Isolation Pilot Plant Waste Shaft

    International Nuclear Information System (INIS)

    During inspections of the Waste Isolation Pilot Plant Waste Shaft in May 1990, patchy areas of apparently degraded concrete were observed on the inner surface of the shaft liner between approximately 810 feet and 900 feet below the surface. The apparent cause of this degradation is chemical reaction of the concrete with magnesium-bearing brine in the annulus between the concrete liner and the host rock. The greater thickness of the degraded layer below the joint may be related to the different chemical compositions that were determined by analyses of the paste portions of concrete samples from above and below the joint. The analytical results support a complex mechanistic explanation of concrete degradation observed behind the liner and in the joint: chemical weakening of the concrete paste; cracking by precipitation of solids in pores; and increased permeability due to calcium chloroaluminate formation. Additional sampling, analyses, and regular monitoring are worth considering to bound the vertical extent of Waste Shaft liner degradation, detect concrete liner degradation in other shafts, and measure any ongoing degradation that may be occurring

  10. The Waste Isolation Pilot Plant transuranic waste repository: A sleeping beauty

    International Nuclear Information System (INIS)

    On May 13, 1998, crowning a 24-year United States Department of Energy effort, the US Environmental Protection Agency certified that the deep geological repository for safe disposal of long-lived, transuranic radioactive waste proposed by the DOE at the Waste Isolation Pilot Plant site in New Mexico complied with all applicable environmental radiation protection standards and compliance criteria. Pursuant to the applicable law, the WIPP Land Withdrawal Act of 1992, as amended in 1997, at the decision of the secretary of energy, the WIPP repository could open 30 calendar days after receiving the EPA certification. The secretary of energy announced May 13, 1998, that he intended to open the WIPP TRUW repository by June 14, 1998. However, at the end of 1998, the opening of the WIPP TRUW repository remains hostage to time-consuming, hazardous-waste-permitting procedures by the state of New Mexico Environment Department and two legal actions. Based on the EPA-verified high safety and the demonstrated risk reduction to both current and future generations offered by the WIPP TRUW repository, it is concluded that the WIPP TRUW repository is a sleeping beauty that will awake, perhaps in stages, and begin its important mission in 1999

  11. AIR DISPERSION MODELING AT THE WASTE ISOLATION PILOT PLANT

    Energy Technology Data Exchange (ETDEWEB)

    Rucker, D.F.

    2000-08-01

    One concern at the Waste Isolation Pilot Plant (WIPP) is the amount of alpha-emitting radionuclides or hazardous chemicals that can become airborne at the facility and reach the Exclusive Use Area boundary as the result of a release from the Waste Handling Building (WHB) or from the underground during waste emplacement operations. The WIPP Safety Analysis Report (SAR), WIPP RCRA Permit, and WIPP Emergency Preparedness Hazards Assessments include air dispersion calculations to address this issue. Meteorological conditions at the WIPP facility will dictate direction, speed, and dilution of a contaminant plume of respirable material due to chronic releases or during an accident. Due to the paucity of meteorological information at the WIPP site prior to September 1996, the Department of Energy (DOE) reports had to rely largely on unqualified climatic data from the site and neighboring Carlsbad, which is situated approximately 40 km (26 miles) to the west of the site. This report examines the validity of the DOE air dispersion calculations using new meteorological data measured and collected at the WIPP site since September 1996. The air dispersion calculations in this report include both chronic and acute releases. Chronic release calculations were conducted with the EPA-approved code, CAP88PC and the calculations showed that in order for a violation of 40 CFR61 (NESHAPS) to occur, approximately 15 mCi/yr of 239Pu would have to be released from the exhaust stack or from the WHB. This is an extremely high value. Hence, it is unlikely that NESHAPS would be violated. A site-specific air dispersion coefficient was evaluated for comparison with that used in acute dose calculations. The calculations presented in Section 3.2 and 3.3 show that one could expect a slightly less dispersive plume (larger air dispersion coefficient) given greater confidence in the meteorological data, i.e. 95% worst case meteorological conditions. Calculations show that dispersion will decrease

  12. Isolation of Precursor Cells from Waste Solid Fat Tissue

    Science.gov (United States)

    Byerly, Diane; Sognier, Marguerite A.

    2009-01-01

    A process for isolating tissue-specific progenitor cells exploits solid fat tissue obtained as waste from such elective surgical procedures as abdominoplasties (tummy tucks) and breast reductions. Until now, a painful and risky process of aspiration of bone marrow has been used to obtain a limited number of tissue- specific progenitor cells. The present process yields more tissue-specific progenitor cells and involves much less pain and risk for the patient. This process includes separation of fat from skin, mincing of the fat into small pieces, and forcing a fat saline mixture through a sieve. The mixture is then digested with collagenase type I in an incubator. After centrifugation tissue-specific progenitor cells are recovered and placed in a tissue-culture medium in flasks or Petri dishes. The tissue-specific progenitor cells can be used for such purposes as (1) generating three-dimensional tissue equivalent models for studying bone loss and muscle atrophy (among other deficiencies) and, ultimately, (2) generating replacements for tissues lost by the fat donor because of injury or disease.

  13. Performance assessment requirements for the identification and tracking of transuranic waste intended for disposal at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Snider, C.A. [Department of Energy, Carlsbad, NM (United States); Weston, W.W. [Westinghouse Electric Corp., Carlsbad, NM (United States)

    1997-11-01

    To demonstrate compliance with environmental radiation protection standards for management and disposal of transuranic (TRU) radioactive wastes, a performance assessment (PA) of the Waste Isolation Pilot Plant (WIPP) was made of waste-waste and waste-repository interactions and impacts on disposal system performance. An estimate of waste components and accumulated quantities was derived from a roll-up of the generator/storage sites` TRU waste inventories. Waste components of significance, and some of negligible effect, were fixed input parameters in the model. The results identified several waste components that require identification and tracking of quantities to ensure that repository limits are not exceeded. The rationale used to establish waste component limits based on input estimates is discussed. The distinction between repository limits and waste container limits is explained. Controls used to ensure that no limits are exceeded are identified. For waste components with no explicit repository based limits, other applicable limits are contained in the WIPP Waste Acceptance Criteria (WAC). The 10 radionuclides targeted for identification and tracking on either a waste container or a waste stream basis include Am-241, Pu-238, Pu-239, Pu-240, Pu-242, U-233, U-234, U-238, Sr-90, and Cs-137. The accumulative activities of these radionuclides are to be inventoried at the time of emplacement in the WIPP. Changes in inventory curie content as a function of radionuclide decay and ingrowth over time will be calculated and tracked. Due to the large margin of compliance demonstrated by PA with the 10,000 year release limits specified, the quality assurance objective for radioassay of the 10 radionuclides need to be no more restrictive than those already identified for addressing the requirements imposed by transportation and WIPP disposal operations in Section 9 of the TRU Waste Characterization Quality Assurance Program Plan. 6 refs.

  14. Control of oxidation potential for basalt repository simulation tests

    International Nuclear Information System (INIS)

    Borosilicate waste glass durability in simulated repository environments can be assessed by use of static tests in leach vessels fabricated of the representative geomedia. Control of the oxidation potential during the test simulates a basalt repository environment. Under very anoxic conditions (i.e. at negative Eh values), the interactions between basalt and SRP waste glass in silica-saturated basaltic groundwaters are the same as those of basalt and groundwater when no waste glass is present. The lack of significant leaching of ions from the waste glass and the lack of any significant changes in either the leached surfaces of glass or basalt under anoxic conditions suggests that the components of this system are at equilibrium when oxygen is absent. 11 refs., 4 figs

  15. Probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    In its most recent report on the annual probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP), the annual failure rate is calculated to be 1.3E(-7)(1/yr), rounded off from 1.32E(-7). A calculation by the Environmental Evaluation Group (EEG) produces a result that is about 4% higher, namely 1.37E(-7)(1/yr). The difference is due to a minor error in the US Department of Energy (DOE) calculations in the Westinghouse 1996 report. WIPP's hoist safety relies on a braking system consisting of a number of components including two crucial valves. The failure rate of the system needs to be recalculated periodically to accommodate new information on component failure, changes in maintenance and inspection schedules, occasional incidents such as a hoist traveling out-of-control, either up or down, and changes in the design of the brake system. This report examines DOE's last two reports on the redesigned waste hoist system. In its calculations, the DOE has accepted one EEG recommendation and is using more current information about the component failures rates, the Nonelectronic Parts Reliability Data (NPRD). However, the DOE calculations fail to include the data uncertainties which are described in detail in the NPRD reports. The US Nuclear Regulatory Commission recommended that a system evaluation include mean estimates of component failure rates and take into account the potential uncertainties that exist so that an estimate can be made on the confidence level to be ascribed to the quantitative results. EEG has made this suggestion previously and the DOE has indicated why it does not accept the NRC recommendation. Hence, this EEG report illustrates the importance of including data uncertainty using a simple statistical example

  16. ISOLATION AND SELECTION OF ALKALINE PROTEOLYTIC BACTERIA FROM LEATHER PR OCESSING WASTE AND ENZYME CHARACTERIZATION

    OpenAIRE

    MARITA ANGGARANi; Nisa R. Mubarik; BUDIASIH WAHYUNTARI

    2004-01-01

    The aims of this experiment were to isolate alkaline protease producing bacteria from leather processing waste, and to study the biochemical properties of the enzyme produced by the selected bacteria. Nine bacterial isolates incubated at 37"C, revealed proteolytic activity on skim milk containing media. Four isolates were grown at pH 9 and another four isolates at pH 10 and only one isolate at pH 11. However, in further subculture, there were only three isolates that showed proteolytic acti...

  17. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    International Nuclear Information System (INIS)

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis

  18. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    Energy Technology Data Exchange (ETDEWEB)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)

  19. Draft Genome Sequences of Two Ureolytic Bacteria Isolated from Concrete Block Waste.

    Science.gov (United States)

    Park, Hongjae; Park, Byeonghyeok; Kim, Hyun Jung; Park, Woojun; Choi, In-Geol

    2016-01-01

    We sequenced genomes of two ureolytic bacteria, Bacillus sp. JH7 and Sporosarcina sp. HYO08, which were isolated from concrete waste and have a potential for biocementation applications. PMID:27491992

  20. WIPP conceptual design report. Addendum C. Cost worksheets for Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1977-04-01

    The cost worksheets for the Waste Isolation Pilot Plant (WIPP) are presented. A summary cost estimate, cost estimate for surface facilities, and cost estimate for shafts and underground facilities are included. (DC)

  1. Seismic reflection data report: Waste Isolation Pilot Plant (WIPP) site, Southeastern New Mexico

    International Nuclear Information System (INIS)

    Volume II contains uninterpreted processed lines and shotpoint maps from three seismic reflection surveys conducted from 1976 through 1978 by Sandia Laboratories to support investigations for the Waste Isolation Pilot Plant. Data interpretations will be the subject of subsequent reports

  2. Draft Genome Sequences of Two Ureolytic Bacteria Isolated from Concrete Block Waste

    Science.gov (United States)

    Park, Hongjae; Park, Byeonghyeok; Kim, Hyun Jung

    2016-01-01

    We sequenced genomes of two ureolytic bacteria, Bacillus sp. JH7 and Sporosarcina sp. HYO08, which were isolated from concrete waste and have a potential for biocementation applications. PMID:27491992

  3. WIPP conceptual design report. Addendum C. Cost worksheets for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    The cost worksheets for the Waste Isolation Pilot Plant (WIPP) are presented. A summary cost estimate, cost estimate for surface facilities, and cost estimate for shafts and underground facilities are included

  4. Mechanisms governing the direct removal of wastes from the Waste Isolation Pilot Plant repository caused by exploratory drilling

    International Nuclear Information System (INIS)

    Two processes are identified that can influence the quantity of wastes brought to the ground surface when a waste disposal room of the Waste Isolation Pilot Plant is inadvertently penetrated by an exploratory borehole. The first mechanism is due to the erosion of the borehole wall adjacent to the waste caused by the flowing drilling fluid (mud); a quantitative computational model based upon the flow characteristics of the drilling fluid (laminar or turbulent) and other drilling parameters is developed and example results shown. The second mechanism concerns the motion of the waste and borehole spall caused by the flow of waste-generated gas to the borehole. Some of the available literature concerning this process is discussed, and a number of elastic and elastic-plastic finite-difference and finite-element calculations are described that confirm the potential importance of this process in directly removing wastes from the repository to the ground surface. Based upon the amount of analysis performed to date, it is concluded that it is not unreasonable to expect that volumes of waste several times greater than that resulting from direct cutting of a gauge borehole could eventually reach the ground surface. No definitive quantitative model for waste removal as a result of the second mechanism is presented; it is concluded that decomposed waste constitutive data must be developed and additional experiments performed to assess further the full significance of this latter mechanism

  5. Mechanisms governing the direct removal of wastes from the Waste Isolation Pilot Plant repository caused by exploratory drilling

    Energy Technology Data Exchange (ETDEWEB)

    Berglund, J.W. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

    1992-12-01

    Two processes are identified that can influence the quantity of wastes brought to the ground surface when a waste disposal room of the Waste Isolation Pilot Plant is inadvertently penetrated by an exploratory borehole. The first mechanism is due to the erosion of the borehole wall adjacent to the waste caused by the flowing drilling fluid (mud); a quantitative computational model based upon the flow characteristics of the drilling fluid (laminar or turbulent) and other drilling parameters is developed and example results shown. The second mechanism concerns the motion of the waste and borehole spall caused by the flow of waste-generated gas to the borehole. Some of the available literature concerning this process is discussed, and a number of elastic and elastic-plastic finite-difference and finite-element calculations are described that confirm the potential importance of this process in directly removing wastes from the repository to the ground surface. Based upon the amount of analysis performed to date, it is concluded that it is not unreasonable to expect that volumes of waste several times greater than that resulting from direct cutting of a gauge borehole could eventually reach the ground surface. No definitive quantitative model for waste removal as a result of the second mechanism is presented; it is concluded that decomposed waste constitutive data must be developed and additional experiments performed to assess further the full significance of this latter mechanism.

  6. Proposed outline of safety analysis report for facilities for geologic isolation of radioactive wastes

    International Nuclear Information System (INIS)

    This report is concerned with formulating the appropriate and necessary contents for a Safety Analysis Report (SAR) for safe, long-term radioactive waste isolation in federal repositories. The material is presented as a guide rather than as an outline of a SAR. Site characteristics, design criteria, facility design, operational systems and components, radiation protection and operational safety, long-term waste isolation, conduct of operations, technical specifications, and quality assurance are covered. Recommendations are given for further research studies

  7. Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 1. Revision 1

    International Nuclear Information System (INIS)

    This document provides baseline inventories of transuranic wastes for the WIPP facility. Information on waste forms, forecasting of future inventories, and waste stream originators is also provided. A diskette is provided which contains the inventory database

  8. WIPP conceptual design report. Addendum A. Design calculations for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    The design calculations for the Waste Isolation Pilot Plant (WIPP) are presented. The following categories are discussed: general nuclear calculations; radwaste calculations; structural calculations; mechanical calculations; civil calculations; electrical calculations; TRU waste surface facility time and motion analysis; shaft sinking procedures; hoist time and motion studies; mining system analysis; mine ventilation calculations; mine structural analysis; and miscellaneous underground calculations

  9. Chem I Supplement. Chemistry Related to Isolation of High-Level Nuclear Waste.

    Science.gov (United States)

    Hoffman, Darleane C.; Choppin, Gregory R.

    1986-01-01

    Discusses some of the problems associated with the safe disposal of high-level nuclear wastes. Describes several waste disposal plans developed by various nations. Outlines the multiple-barrier concept of isolation in deep geological questions associated with the implementation of such a method. (TW)

  10. Long-term climate variability at the Waste Isolation Pilot Plant, Southeastern New Mexico, USA

    International Nuclear Information System (INIS)

    The United States Department of Energy is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico for the disposal of transuranic wastes generated by defense programs. Because changes in climate during the next 10,000 years (10 ka) may affect performance of the repository, an understanding of long-term climate variability is essential for evaluating regulatory compliance

  11. WIPP conceptual design report. Addendum A. Design calculations for Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1977-04-01

    The design calculations for the Waste Isolation Pilot Plant (WIPP) are presented. The following categories are discussed: general nuclear calculations; radwaste calculations; structural calculations; mechanical calculations; civil calculations; electrical calculations; TRU waste surface facility time and motion analysis; shaft sinking procedures; hoist time and motion studies; mining system analysis; mine ventilation calculations; mine structural analysis; and miscellaneous underground calculations.

  12. Laboratory and bin-scale tests of gas generation for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The design-basis, defense-related, transuranic (TRU) waste to be emplaced in the Waste Isolation Pilot Plant (WIPP) could, if sufficient H2O and nutrients were present, produce as much as 1,500 moles of gas per drum of waste. Anoxic corrosion of Fe and Fe-base alloys and microbial degradation of cellulosics are the processes of greatest concern, but radiolysis of brine could also be important. 19 refs., 1 fig., 1 tab

  13. BIOREMEDIATION OF INDUSTRIAL AND MUNICIPAL WASTE WATER USING BACTERIAL ISOLATES

    OpenAIRE

    P.Priya darshini*, J.Sharpudin

    2016-01-01

    Bioremediation is a treatment that uses naturally occurring organisms to break down hazardous substances into less toxic or non toxic substances. The microbes are effective in control of pollution due to waste water. The industrial and municipal waste water is analyzed for different Physico-Chemical parameters such as pH, Temperature, TDS, BOD, COD, Total Alkalinity, Chlorides. The collected waste water samples were serially diluted and pour plated on Nutrient Agar medium and incubated at 37˚...

  14. Zeolite stability constraints on radioactive waste isolation in zeolite-bearing volcanic rocks

    International Nuclear Information System (INIS)

    Silicic tuffs of the southern Great Basin and basalts of the Columbia River Plateau are under investigation as potential host rocks for high- and intermediate-level radioactive wastes. Non-welded and partially welded tuffs may contain major amounts (> 50%) of the zeolite minerals: clinoptilolite, mordenite, and analcime. Densely welded tuffs and some basalt flows may contain clinoptilolite as fracture filling which limits permeability of these rocks. The cation exchange properties of these zeolite minerals allow them to pose a natural barrier to the migration of cationic species of various radionuclides in aqueous solutions. However, these minerals are unstable at elevated temperatures and at low water vapor pressures, and they may break down either by reversible dehydration or by irreversible mineralogical reactions. All of the breakdown reactions occurring with increased temperature involve a net volume reduction and evolution of fluids. Thus, they may provide both a pathway (shrinkage fractures) and a driving force (fluid pressure) for release of radionuclides to the biosphere. These reactions may be avoided by keeping zeolite-bearing horizons saturated with water and below about 850C. This may restrict allowable gross thermal loadings in radioactive waste repositories in zeolite-bearing volcanic rocks. 3 figures

  15. Regulation of radioactive mixed waste at the Waste Isolation Pilot Plant (WIPP) under the Resource Conservation and Recovery Act (RCRA)

    International Nuclear Information System (INIS)

    This paper discusses Resource Conservation and Recovery Act (RCRA) (1) compliance issues pertinent to the placement of radioactive mixed waste in the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The discussion focuses on the mixed waste issue, the WIPP as an interim status facility, effects of RCRA land disposal prohibitions on the WIPP, regulation of geologic repositories as Subpart X miscellaneous units, and various inconsistencies between U.S. Department of Energy (DOE) requirements for the WIPP and the RCRA regulations. An approach to permitting the WIPP as a RCRA compliance facility is also addressed

  16. Hydrothermal evolution of repository groundwaters in basalt

    International Nuclear Information System (INIS)

    Groundwaters in the near field of a radioactive waste repository in basalt will change their chemical composition in response to reactions with the basalt. These reactions will be promoted by the heat generated by the decaying waste. It is important to predict both the rate and the extent of these reactions, and the secondary minerals produced, because the alteration process controls the chemical environment affecting the corrosion of the canister, the solubility and complexation of migrating radionuclides, the reactivity of the alteration products to radionuclides sorption, and the porosity and permeability of the host rock. A comprehensive review of the literature leads to the preliminary finding that hydrothermally altering basalts in geothermal regions such as Iceland lead to a secondary mineralogy and groundwater composition similar to that expected to surround a repository. Furthermore, laboratory experiments replicating the alteration conditions approximate those observed in the field and expected in a repository. Preliminary estimates were made of the rate of hydration and devitrification of basaltic glass and the zero-order dissolution rate of basaltic materials. The rates were compared with those for rhyolitic glasses and silicate minerals. Preliminary calculations made of mixed process alteration kinetics, involving pore diffusion and surface reaction suggest that at temperatures greater than 1500C, alteration proceeds so rapidly as to become pervasive in normally fractured basalt exposed to higher temperatures in the field. 70 references

  17. Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation

    International Nuclear Information System (INIS)

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and high-level wastes that will eventually be disposed of in a geologic repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. This paper discusses how detailed characterizations ar required for all of these materials. These characterizations include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. In addition, the present inventories and projected quantities of the various wastes are needed. This information has been assembled in a Characteristics Data Base which provides data in four formats: hardcopy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files

  18. Position paper on gas generation in the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Gas generation by transuranic (TRU) waste is a significant issue because gas will, if produced in significant quantities, affect the performance of the Waste Isolation Pilot Plant (WIPP) with respect to Environmental Protection Agency (EPA) regulations for the long-term isolation of radioactive and chemically hazardous waste. If significant gas production occurs, it will also affect, and will be affected by, other processes and parameters in WIPP disposal rooms. The processes that will produce gas in WIPP disposal rooms are corrosion, microbial activity and radiolysis. This position paper describes these processes and the models, assumptions and data used to predict gas generation in WIPP disposal rooms

  19. A Dynamic Waste Isolation Pilot Plant Performance Assessment Tool - 12490

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) Performance Assessment (PA) methodology comprises a toolbox used to demonstrate regulatory compliance of the repository after facility closure. The PA framework rests upon an extensive suite of computational codes. In some cases, significant alteration of code inputs is a tedious and difficult task. Due to the nature of the application for which they are used, PA codes used in support of WIPP regulatory compliance demonstration must satisfy stringent quality assurance requirements. Consequently, many of the coding practices used during original code development are still implemented today. A more efficient workflow configuration has the potential to alleviate difficulties associated with extensive code input modifications. Here, this potential is assessed via an implementation of a more flexible scientific workflow system for a subset of the codes used in WIPP PA. The scientific workflow approach taken here for a dynamic PA system enables users from disparate backgrounds to dramatically shorten the time between hypothesis and analysis by decreasing the amount of a priori knowledge, from a range of disciplines, needed to execute the code. Having smaller iteration times allows for more ideas to be tested and explored, which leads to safer and more optimized systems. Note that these high-level, dynamic tools are intended only for initial scoping studies on the personal computer of a researcher. Full, regulatory compliance calculations may occur only within a qualified computing environment. However, the WIPP PA tools here may guide future research and indicate regions of the analysis space that are worth further study. This next generation of PA software provides the ability to perform scoping investigations of repository performance quickly and easily, and has an accessible and useful interface to a variety of users, such as fuel cycle systems designers, domain experts such as repository modelers, and policy makers. The purview

  20. Isolation and molecular characterisation of malathion-degrading bacterial strains from waste water in Egypt

    OpenAIRE

    Zeinat K. Mohamed; Mohamed A. Ahmed; Nashwa A. Fetyan; SHERIF M. ELNAGDY

    2010-01-01

    Efficiencies of local bacterial isolates in malathion degradation were investigated. Five bacterial isolates obtained from agricultural waste water were selected due to their ability to grow in minimal salt media, supplied with 250 ppm malathion as sole source of carbon and phosphorus. The purified bacterial isolates (MOS-1, MOS-2, MOS-3, MOS-4 and MOS-5) were characterised and identified using a combination of cellular profile (SDS-PAGE), genetic make up profile (RAPD-PCR), and morphological...

  1. From science to compliance: Geomechanics studies of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Mechanical and hydrological properties of salt provide excellent bases for geological isolation of hazardous materials. Regulatory certification of the Waste Isolation Pilot Plant (WIPP) testifies to the nearly ideal characteristics of bedded salt deposits in southeast New Mexico. The WIPP history includes decades of testing and scientific investigations, which have resulted in a comprehensive understanding of salt's mechanical deformational and hydrological properties over an applicable range of stresses and temperatures. Comprehensive evaluation of salt's favorable characteristics helped demonstrate regulatory compliance and ensure isolation of radioactive waste placed in a salt geological setting

  2. Waste management '81: ANS topical meeting, the state of waste isolation in the US and elsewhere, advocacy programs and public communications, proceedings of the symposium of waste management, 1981

    International Nuclear Information System (INIS)

    The two volumes contain 90 papers presented at the meeting, 63 of which are indexed separately. The papers are grouped under general topics that include programmatic and regulatory issues, international approaches to waste management, alternate waste forms, transportation of radioactive wastes, waste isolation, low-level waste, volume reduction and solidification, mill tailings and decommissioning of nuclear facilities, and others

  3. Waste Management '81: ANS topical meeting, the state of waste isolation in the US and elsewhere, advocacy programs and public communications, proceedings of the symposium on waste management, 1981

    International Nuclear Information System (INIS)

    The two volumes contain 90 papers presented at the meeting, 61 of which are indexed separately. The papers are grouped under general topics that include programmatic and regulatory issues, international approaches to waste management, alternate waste forms, transportation of radioactive wastes, waste isolation, low-level waste, volume reduction and solidification, mill tailings and decommissioning of nuclear facilities, and others

  4. The potential of phosphate solubilizing bacteria isolated from sugarcane wastes for solubilizing phosphate

    Directory of Open Access Journals (Sweden)

    Atekan

    2014-07-01

    Full Text Available Most of P in agricultural soils is in unavailable forms for plant growth. Phosphate solubilizing bacteria can increase soil P availability. This study was aimed to isolate phosphate solubilizing bacteria from sugarcane waste compost and to test ability of the isolated bacterial to dissolve phosphate. The bacteria were isolated from three types of sugarcane waste, i.e. filter cake compost, bagasse compost, and a mixture of filter cake + bagasse + trash biomass compost. The potential colony was further purified by the Pikovskaya method on selective media. Eight isolates of phosphate solubilizing bacteria were obtained from all wasted studied. Amongst them, T-K5 and T-K6 isolates were superior in dissolving P from Ca3(PO42 in the media studied. The two isolates were able to solubilize P with solubilizing index of 1.75 and 1.67 for T-K5 and T-K6, respectively. Quantitatively, T-K6 isolate showed the highest P solubilization (0.74 mg / L, followed by T-K5 isolate (0.56 mg / L, while the lowest P solubilization (0.41 mg / L was observed for T-K4 isolate. The increase of soluble P was not always followed by the decrease in pH.

  5. Neutron shielding analysis for remote handled transuranic waste containers in facility casks at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Neutron shielding characteristics of the Waste Isolation Pilot Plant facility cask have been quantified for a variety of combinations of neutron sources and waste matrices which would potentially be handled in waste containers. The neutron attenuation and neutron environment of the waste container and the facility cask have been analyzed to ensure that the design requirement of neutron dose rate will be met under the combinations of the source and waste matrix conditions. The analyses considered the ranges of neutron source spectrum and waste matrices which combine to produce the minimum neutron shielding worth of the facility cask. One-dimensional analyses were performed with discrete ordinate transport theory methods using multigroup neutron cross section data. The results discussed in this report demonstrate the effect of source spectrum and waste container matrix on predicted neutron dose rates adjacent to the unshielded waste container and the surface of the facility cask. An evaluation of the uncertainties in predicted neutron dose rates is provided which results in an assessment of the maximum measured neutron dose rate external to the facility cask. A description of the analytical models developed, the analysis methodology, the neutron source spectra, and the detailed results are described in this report. 10 refs., 50 figs., 39 tabs

  6. TRU partnership -- Benefits to the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Transuranic (TRU) waste has been generated over the last 40 years as the result of the United States Government's nuclear defense research and production activities. Historically, the TRU waste has been managed on a site-specific basis. With increased regulatory authority being given to the states under the Resource and Conservation Recovery Act (RCRA) and the Federal FAcilities Compliance Agreements (FFCA), the management of TRU waste across the system varies considerably. This variable approach does not support the Department of Energy's vision of safe, efficient, and cost-effective TRU waste management. One effective tool for facilitating better communications, coordination, and cooperation among the generator/storage sites is the formation of topic-specific interface working groups that are made up of cognizant personnel from the affected sites. The benefits that the WIPP receives from one of these interface working groups, the TRU Projects Interiste Working Group, are discussed in this paper

  7. Nuclear Waste Materials Characterization Center. Semiannual progress report, April 1985-September 1985

    Energy Technology Data Exchange (ETDEWEB)

    Mendel, J.E. (comp.)

    1985-12-01

    Work continued on converting MCC Quality Assurance practices to comply with the national QA standard for nuclear facilities, ANSI/ASME NQA-1. Support was provided to the following: Office of Geologic Repositories; Salt Repository Project; Basalt Waste Isolation Project; Office of Defense Waste and Byproducts Management; Hanford Programs; Transportation Technology Center; and West Valley Demonstration Project. (LM)

  8. Westinghouse Hanford Company Plan for certifying newly generated contact-handled transuranic waste for emplacement in the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Westinghouse Hanford Company (Westinghouse Hanford) currently manages an interim storage site for Westinghouse Hanford and non-Westinghouse Hanford-generated transuranic (TRU) waste and operates TRU waste generating facilities within the Hanford Site in Washington State. Approval has been received from the Waste Acceptance Criteria Certification Committee (WACCC) and Westinghouse Hanford TRU waste generating facilities to certify newly generated contact-handled TRU (CH-TRU) solid waste to meet the Waste Acceptance Criteria (WAC). This document describes the overall plan for certifying newly generated CH-TRU solid waste to meet the WAC requirements for storage at the Waste Isolation Pilot Plant (WIPP) site. Attached to this document are facility-specific certification plans for the Westinghouse Hanford TRU waste generators that have received WACCC approval. The certification plans describe operations that generate CH-TRU solid waste and the specific procedures by which these wastes will be certified and segregated from uncertified wastes at the generating facilities. 1 fig

  9. Shipping Remote Handled Transuranic Waste to the Waste Isolation Pilot Plant - An Operational Experience

    International Nuclear Information System (INIS)

    On January 18, 2007, the first ever shipment of Remote Handled Transuranic (RH TRU) waste left the gate at the Idaho National Laboratory (INL), headed toward the Waste Isolation Pilot Plant (WIPP) for disposal, thus concluding one of the most stressful, yet rewarding, periods the authors have ever experienced. The race began in earnest on October 16, 2006, with signature of the New Mexico Environment Department Secretary's Final Order, ruling that the '..draft permit as changed is hereby approved in its entirety.' This established the effective date of the approved permit as November 16, 2006. The permit modification was a consolidation of several Class 3 modification requests, one of which included incorporation of RH TRU requirements and another of which incorporated the requirements of Section 311 of Public Law 108-137. The obvious goal was to complete the first shipment by November 17. While many had anticipated its approval, the time had finally come to actually implement, and time seemed to be the main item lacking. At that point, even the most aggressive schedule that could be seriously documented showed a first ship date in March 2007. Even though planning for this eventuality had started in May 2005 with the arrival of the current Idaho Cleanup Project (ICP) contractor (and even before that), there were many facility and system modifications to complete, startup authorizations to fulfill, and many regulatory audits and approvals to obtain before the first drum could be loaded. Through the dedicated efforts of the ICP workers, the partnership with Department of Energy (DOE) - Idaho, the coordinated integration with the Central Characterization Project (CCP), the flexibility and understanding of the regulatory community, and the added encouragement of DOE - Carlsbad Field Office and at Headquarters, the first RH TRU canister was loaded on December 22, 2006. Following final regulatory approval on January 17, 2007, the historic event finally occurred the

  10. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 3: Appendix BIR Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-31

    The Waste Isolation Pilot Plant (WIPP) Transuranic Waste Baseline Inventory Report (WTWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties, from across the US Department of Energy (DOE) transuranic (TRU) waste system, into a series of ``waste profiles`` that can be used as the basis for waste form discussions with regulatory agencies. The majority of this document reports TRU waste inventories of DOE defense sites. An appendix is included which provides estimates of commercial TRU waste from the West Valley Demonstration Project. The WIPP baseline inventory is estimated using waste streams identified by the DOE TRU waste generator/storage sites, supplemented by information from the Mixed Waste Inventory Report (MWIR) and the 1994 Integrated Data Base (IDB). The sites provided and/or authorized all information in the Waste Stream Profiles except the EPA (hazardous waste) codes for the mixed inventories. These codes were taken from the MWIR (if a WTWBIR mixed waste stream was not in MWIR, the sites were consulted). The IDB was used to generate the WIPP radionuclide inventory. Each waste stream is defined in a waste stream profile and has been assigned a waste matrix code (WMC) by the DOE TRU waste generator/storage site. Waste stream profiles with WMCs that have similar physical and chemical properties can be combined into a waste matrix code group (WMCG), which is then documented in a site-specific waste profile for each TRU waste generator/storage site that contains waste streams in that particular WMCG.

  11. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 3: Appendix BIR Volume 1

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) Transuranic Waste Baseline Inventory Report (WTWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties, from across the US Department of Energy (DOE) transuranic (TRU) waste system, into a series of ''waste profiles'' that can be used as the basis for waste form discussions with regulatory agencies. The majority of this document reports TRU waste inventories of DOE defense sites. An appendix is included which provides estimates of commercial TRU waste from the West Valley Demonstration Project. The WIPP baseline inventory is estimated using waste streams identified by the DOE TRU waste generator/storage sites, supplemented by information from the Mixed Waste Inventory Report (MWIR) and the 1994 Integrated Data Base (IDB). The sites provided and/or authorized all information in the Waste Stream Profiles except the EPA (hazardous waste) codes for the mixed inventories. These codes were taken from the MWIR (if a WTWBIR mixed waste stream was not in MWIR, the sites were consulted). The IDB was used to generate the WIPP radionuclide inventory. Each waste stream is defined in a waste stream profile and has been assigned a waste matrix code (WMC) by the DOE TRU waste generator/storage site. Waste stream profiles with WMCs that have similar physical and chemical properties can be combined into a waste matrix code group (WMCG), which is then documented in a site-specific waste profile for each TRU waste generator/storage site that contains waste streams in that particular WMCG

  12. Waste Isolation Pilot Plant Title I operator dose calculations. Final report, LATA report No. 90

    International Nuclear Information System (INIS)

    The radiation exposure dose was estimated for the Waste Isolation Pilot Plant (WIPP) operating personnel who do the unloading and transporting of the transuranic contact-handled waste. Estimates of the radiation source terms for typical TRU contact-handled waste were based on known composition and properties of the waste. The operations sequence for waste movement and storage in the repository was based upon the WIPP Title I data package. Previous calculations had been based on Conceptual Design Report data. A time and motion sequence was developed for personnel performing the waste handling operations both above and below ground. Radiation exposure calculations were then performed in several fixed geometries and folded with the time and motion studies for individual workers in order to determine worker exposure on an annual basis

  13. Radionuclide reactions with groundwater and basalts from Columbia River basalt formations

    International Nuclear Information System (INIS)

    Chemical reactions of radionuclides with geologic materials found in Columbia River basalt formations were studied. The objective was to determine the ability of these formations to retard radionuclide migration from a radioactive waste repository located in deep basalt. Reactions that can influence migration are precipitation, ion-exchange, complexation, and oxidation-reduction. These reactions were studied by measuring the effects of groundwater composition and redox potential (Eh) on radionuclide sorption on fresh basalt surfaces, a naturally altered basalt, and a sample of secondary minerals associated with a Columbia River basalt flow. In addition, radionuclide sorption isotherms were measured for these materials and reaction kinetics were determined. The radionuclides studied were 137Cs, 85Sr, 75Se, /sup 95m/Tc, 237Np, 241Am, 226Ra and 237Pu. The Freundlich equation accurately describes the isotherms when precipitation of radionuclides does not occur. In general, sorption increased in the order: basalt < altered basalt < secondary minerals. This increase in sorption corresponds to increasing surface area and cation exchange capacity. The Eh of the system had a large effect on technetium, plutonium, and neptunium sorption. Technetium(VII), Pu(VI), and Np(V) are reduced to Tc(IV), Pu(IV), and Np(IV), respectively, under Eh conditions expected in deep basalt formations. The kinetics of radionuclide sorption and basalt-groundwater reactions were observed over a period of 18 weeks. Most sorption reactions stabilized after about four weeks. Groundwater composition changed the least in contact with altered basalt. Contact with secondary minerals greatly increased Ca, K, and Mg concentrations in the groundwater

  14. Reliability and safety program plan outline for the operational phase of a waste isolation facility

    Energy Technology Data Exchange (ETDEWEB)

    Ammer, H.G.; Wood, D.E.

    1977-03-28

    A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division.

  15. HUMIC ACID-LIKE MATTER ISOLATED FROM GREEN URBAN WASTES. PART I: STRUCTURE AND SURFACTANT PROPERTIES

    Directory of Open Access Journals (Sweden)

    Enzo Montoneri

    2008-02-01

    Full Text Available A humic acid-like substance (cHAL2 isolated from urban green wastes before composting was compared to a humic acid-like substance (cHAL isolated from a mix of urban organic humid waste fraction and green residues composted for 15 days. cHAL2 was found to contain more aliphatic and O-alkyl C atoms relative to aromatic, phenol, and carboxyl C atoms, and to yield higher critical micellar concentration (cmc = 0.97 g L-1 and surface tension at the cmc (cmc = 37.8 mN/min water than cHAL (cmc = 0.40 g L-1; cmc = 36.1 mN/m. The results point out that biomass wastes may be an interesting source of biosurfactants with diversified properties that depend on the nature of waste and on its process of treatment.

  16. Waste Isolation Pilot Plant Site Environmental Report for calendar year 1989

    International Nuclear Information System (INIS)

    This is the 1989 Site Environmental Report (SER) for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP is a government owned and contractor-operated facility. The WIPP project is operated by Westinghouse Electric Corporation for the US Department of Energy (DOE). The mission of the WIPP is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) waste generated by the defense activities of the US Government. This report provides a comprehensive description of environmental activities at the WIPP during calendar year 1989. The WIPP facility will not receive waste until all concerns affecting opening the WIPP are addressed to the satisfaction of the Secretary of Energy. Therefore, this report describes the status of the preoperational activities of the Radiological Environmental Surveillance (RES) program, which are outlined in the Radiological Baseline Program for the Waste Isolation Pilot Plant (WTSD-TME-057). 72 refs., 13 figs., 20 tabs

  17. Waste Isolation Pilot Plant Site Environmental Report for calendar year 1989

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    This is the 1989 Site Environmental Report (SER) for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP is a government owned and contractor-operated facility. The WIPP project is operated by Westinghouse Electric Corporation for the US Department of Energy (DOE). The mission of the WIPP is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) waste generated by the defense activities of the US Government. This report provides a comprehensive description of environmental activities at the WIPP during calendar year 1989. The WIPP facility will not receive waste until all concerns affecting opening the WIPP are addressed to the satisfaction of the Secretary of Energy. Therefore, this report describes the status of the preoperational activities of the Radiological Environmental Surveillance (RES) program, which are outlined in the Radiological Baseline Program for the Waste Isolation Pilot Plant (WTSD-TME-057). 72 refs., 13 figs., 20 tabs.

  18. Reliability and safety program plan outline for the operational phase of a waste isolation facility

    International Nuclear Information System (INIS)

    A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division

  19. Waste isolation in geologic formations in the USA

    International Nuclear Information System (INIS)

    The ERDA program for the establishment of terminal storage facilities for commercial radioactive wastes in deep geologic formations was recently reorganized as the National Waste Terminal Storage (NWTS) program. General plans for implementing this expanded program call for geologic investigations and feasibility confirmation studies at multiple geographic locations, leading to pilot plant construction and operation with possible future conversion into a Federal Repository. The pilot plant operations will be experimental facilities having limited capacity to store actual waste in a readily retrievable configuration. The first two pilot plants are planned to start operations simultaneously in the mid-1980's. Geologic investigations are now in progress or planned in study areas of the interior basins of the Gulf Coast Salt Dome Province, in the Salina Salt basin and in the Paradox Basin in an effort to identify acceptable locations for these initial facilities. Subsequent pilot plants will be located in other formations. Preliminary geologic evaluations have been initiated in the Paleozoic shales and limestones, Triassic shale basins along the east coast, Mesozoic shales of the Gulf Coast and northern high plains and certain crystalline igneous rocks. Most of the required engineering testing of disposal in salt formations has been completed in previous programs. However, the establishment of pilot plants in the other rock types will require a sequence of in situ testing designed to develop the information necessary to both demonstrate the feasibility of waste disposal in that particular formation and provide the data for facility designs

  20. Office of Waste Isolation progress report, December 1977

    International Nuclear Information System (INIS)

    This document reports progress on the OWI's portion of the National Waste Terminal Storage (NWTS) program. It comprises project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. They are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs

  1. Office of Waste Isolation progress report, January 1978

    International Nuclear Information System (INIS)

    This document, prepared to report progress on the National Waste Terminal Storage (NWTS) program, consists of project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. The project reports are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs

  2. Waste Isolation Pilot Plant no-migration variance petition

    International Nuclear Information System (INIS)

    Section 3004 of RCRA allows EPA to grant a variance from the land disposal restrictions when a demonstration can be made that, to a reasonable degree of certainty, there will be no migration of hazardous constituents from the disposal unit for as long as the waste remains hazardous. Specific requirements for making this demonstration are found in 40 CFR 268.6, and EPA has published a draft guidance document to assist petitioners in preparing a variance request. Throughout the course of preparing this petition, technical staff from DOE, EPA, and their contractors have met frequently to discuss and attempt to resolve issues specific to radioactive mixed waste and the WIPP facility. The DOE believes it meets or exceeds all requirements set forth for making a successful ''no-migration'' demonstration. The petition presents information under five general headings: (1) waste information; (2) site characterization; (3) facility information; (4) assessment of environmental impacts, including the results of waste mobility modeling; and (5) analysis of uncertainties. Additional background and supporting documentation is contained in the 15 appendices to the petition, as well as in an extensive addendum published in October 1989

  3. Resource Conservation and Recovery Act Part B permit application [for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    This volume contains Appendix D2, engineering design basis reports. Contents include: Design considerations for the waste hoist of the Waste Isolation Pilot Plant (WIPP); A site-specific study of wind and tornado probabilities at the WIPP Site in southeast New Mexico; Seismic evaluation report of underground facilities; and calculations for analysis of wind loads and tornado loads for WHB, seismic calculations, calculations for VOC-10 monitoring system, and for shaft at station A

  4. Isolation and Screening of Water Microbes for Decolourisation of Textile Dye Waste

    OpenAIRE

    J. K. Singh,; Ranjan, R.; Pranay P. Pankaj*

    2016-01-01

    Azo dyes are widely used in textile industry. Unused dyes, consisting mainly non biodegradable released along with waste water streams without any proper pre-treatment which cause nuisance for environment and accumulate in flora as well as fauna. These also exhibit allergic, carcinogenic and mutagenic properties for human beings. Isolation and screening of azo dye degrading bacteria are economic in biodegradation and detoxification. In the present study, 200 waste water samples were collected...

  5. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 3: Comment response document

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy''s (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE''s Environmental Management Program. This volume provides responses to public comments on the Draft SEIS-II. Comments are related to: Alternatives; TRU waste; DOE credibility; Editorial; Endorsement/opposition; Environmental justice; Facility accidents; Generator site operations; Health and safety; Legal and policy issues; NEPA process; WIPP facilities; WIPP waste isolation performance; Purpose and need; WIPP operations; Site characterization; Site selection; Socioeconomics; and Transportation

  6. Hydrogeology of radioactive waste isolation: the challenge of a rational assessment

    International Nuclear Information System (INIS)

    Plans to isolate radioactive waste raise more questions than can be answered within the lifetime of today's researchers. The existence of a multitude of unanswered questions, however, is not a unique phenomenon related to waste isolation, but is a general characteristic of all science. Although most questions related to the isolation of radioactive waste are interesting scientifically, answers to only a small but critical fraction of the questions are vital to the practical aspects of the problem. Almost all hydrogeologic evaluations of repository sites convey an excessively negative view with respect to geologic processes. Repositories do not necessarily become more hazardous with time. Many slow, normal geologic processes will seal and cover repository sites, making radionuclide migration less likely in the future than at present. Furthermore, several more rapid geologic processes, which are viewed with great apprehension, will not always have negative effects. Faulting could block ground-water circulation near the repository and consequently slow the outward migration of radionuclides; volcanism could cover repository sites, with only a slight chance of a volcanic vent contracting the radioactive waste; and in most of the northern part of the Midwest, future glacial activity would probably plaster the ground surface with layers of till, thus helping to isolate and protect any potential deep repository. Safety of waste repositories will depend on multiple barriers to migration of radionuclides. Further research focused on each barrier, however, is required before repository safety is assured

  7. Radioactive waste isolation in salt: special advisory report on the status of the Office of Nuclear Waste Isolation's plans for repository performance assessment

    International Nuclear Information System (INIS)

    Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables

  8. 9+ years of disposal experience at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    With almost a decade of operating experience, the Waste Isolation Pilot Plant (WIPP) has established an enviable record by clearly demonstrating that a deep geologic repository for unconditioned radioactive waste in rock salt can be operated safely and in compliance with very complex regulations. WIPP has disposed of contact-handled transuranic (TRU) waste since 1999 and remote-handled TRU waste since 2007. Emplacement methods range from directly stacking unshielded 0.21-4.5 m3 containers inside disposal rooms to remotely inserting highly radioactive 0.89 m3 canisters into horizontally drilled holes (shield plugs placed in front of canisters protect workers inside active disposal rooms). More than 100 000 waste containers have been emplaced, and one-third of WIPP's authorized repository capacity of 175,000 m3 has already been consumed. Principal surface operations are conducted in the waste handling building, which is divided into CH and RH waste handling areas. Four vertical shafts extend from the surface to the disposal horizon, 655 m below the surface in a 1000 m thick sequence of Permian bedded salt. The waste disposal area of about 0.5 km2 is divided into ten panels, each consisting of seven rooms. Vertical closure (creep) rates in disposal rooms range up to 10 cm per year. While one panel is being filled with waste, the next one is being mined. Mined salt is raised to the surface in the salt shaft, and waste is lowered down the waste shaft. Both of these shafts also serve as principal access for personnel and materials. Underground ventilation is divided into separate flow paths, allowing simultaneous mining and disposal. A filter building near the exhaust shaft provides the capability to filter the exhaust air (in reduced ventilation mode) through HEPA filters before release to the atmosphere. WIPP operations have not exposed employees or the public to radiation doses beyond natural background variability. They consistently meet or exceed regulatory

  9. Workshop on fundamental geochemistry needs for nuclear waste isolation

    International Nuclear Information System (INIS)

    In their deliberations, workshop participants did not attempt to incorporate the constraints that the 1982 National Nuclear Waste Management Policy Act placed upon the site-specific investigations. In particular, there was no attempt to (1) identify the research areas that apply most strongly to a particular potential repository site, (2) identify the chronological time when the necessary data or knowledge could be available, or (3) include a sensitivity analysis to prioritize and limit data needs. The workshop participants felt these are the purview of the site-specific investigations; the purpose of the workshop was to discuss the generic geochemistry research needs for a nuclear waste repository among as broad spectrum of individual scientists as possible and to develop a consensus of what geochemical information is important and why

  10. Workshop on fundamental geochemistry needs for nuclear waste isolation

    Energy Technology Data Exchange (ETDEWEB)

    Heiken, J.H. (ed.)

    1985-09-01

    In their deliberations, workshop participants did not attempt to incorporate the constraints that the 1982 National Nuclear Waste Management Policy Act placed upon the site-specific investigations. In particular, there was no attempt to (1) identify the research areas that apply most strongly to a particular potential repository site, (2) identify the chronological time when the necessary data or knowledge could be available, or (3) include a sensitivity analysis to prioritize and limit data needs. The workshop participants felt these are the purview of the site-specific investigations; the purpose of the workshop was to discuss the generic geochemistry research needs for a nuclear waste repository among as broad spectrum of individual scientists as possible and to develop a consensus of what geochemical information is important and why.

  11. Biaxial casting method and apparatus for isolating radioactive waste

    International Nuclear Information System (INIS)

    Hazardous radioactive waste is compacted and cast into safely handled monolithic castings having a radiation barrier wall completely enclosing the radioactive waste by centrifugal casting processes in which the barrier wall may be either a pre-formed shell transported to the jobsite or it may be formed by biaxial centrifugal casting and curing of the barrier wall in a mold. When a pre-formed shell is used, means are provided for thickening the radiation barrier if necessary by biaxial casting of additional barrier material inside of the shell. Castable radioactive material is cast inside the barrier wall before removal of the casting mold from the finished cast monolith. The cast monolith is supported for rotation as the mold is removed therefrom so that additional impact resisting and radiation barrier material can also easily be applied to the exterior surface monolith if radiation leakage exceeds tolerance levels. (author) figs

  12. Can we talk? Communications management for the Waste Isolation Pilot Plant, a complex nuclear waste management project

    International Nuclear Information System (INIS)

    Sandia Nuclear Waste Management Program is pursuing for DOE an option for permanently disposing radioactive waste in deep geologic repositories. Included in the Program are the Waste Isolation Pilot Plant (WIPP) Project for US defense program mixed waste the Yucca Mountain Project (YMP) for spent power reactor fuel and vitrified high-level waste, projects for other waste types, and development efforts in environmental decision support technologies. WIPP and YMP are in the public arena, of a controversial nature, and provide significant management challenges. Both projects have large project teams, multiple organization participants, large budgets, long durations, are very complex, have a high degree of programmatic risk, and operate in an extremely regulated environment requiring legal defensibility. For environmental projects like these to succeed, SNL's Program is utilizing nearly all areas in PMI's Project Management Body of Knowledge (PMBOK) to manage along multiple project dimensions such as the physical sciences (e.g., geophysics and geochemistry; performance assessment; decision analysis) management sciences (controlling the triple constraint of performance, cost and schedule), and social sciences (belief systems; public participation; institutional politics). This discussion focuses primarily on communication challenges active on WIPP. How is the WIPP team meeting the challenges of managing communications?'' and ''How are you approaching similar challenges?'' will be questions for a dialog with the audience

  13. Waste Isolation Pilot Plant design validation: Final report, Appendices

    International Nuclear Information System (INIS)

    This volume is comprised of the following appendices: DOE stipulated agreement with State of New Mexico (partial); geologic correlations; mathematical simulation of underground in situ behavior; C and SH shaft geologic logs and maps; waste shaft geologic logs and maps; exhaust shaft geologic log; test rooms geologic maps and sections; drift cross sections; facility level geologic core hole logs; geomechanical instrumentation data plots; and analytical data plots

  14. Waste Isolation Pilot Plant No-Migration Variance Petition

    International Nuclear Information System (INIS)

    The purpose of the WIPP No-Migration Variance Petition is to demonstrate, according to the requirements of RCRA section 3004(d) and 40 CFR section 268.6, that to a reasonable degree of certainty, there will be no migration of hazardous constituents from the facility for as long as the wastes remain hazardous. The DOE submitted the petition to the EPA in March 1989. Upon completion of its initial review, the EPA provided to DOE a Notice of Deficiencies (NOD). DOE responded to the EPA's NOD and met with the EPA's reviewers of the petition several times during 1989. In August 1989, EPA requested that DOE submit significant additional information addressing a variety of topics including: waste characterization, ground water hydrology, geology and dissolution features, monitoring programs, the gas generation test program, and other aspects of the project. This additional information was provided to EPA in January 1990 when DOE submitted Revision 1 of the Addendum to the petition. For clarity and ease of review, this document includes all of these submittals, and the information has been updated where appropriate. This document is divided into the following sections: Introduction, 1.0: Facility Description, 2.0: Waste Description, 3.0; Site Characterization, 4.0; Environmental Impact Analysis, 5.0; Prediction and Assessment of Infrequent Events, 6.0; and References, 7.0

  15. Westinghouse Hanford Company plan for certifying newly generated contact-handled transuranic waste for emplacement in the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Westinghouse Hanford Company (Westinghouse Hanford) currently manages an interim storage site for Westinghouse Hanford and non-Westinghouse Hanford-generated transuranic (TRU) waste and operates TRU waste generating facilities within the Hanford Site in Washington State. Approval has been received from the Waste Acceptance Criteria Certification Committee (WACCC) and Westinghouse Hanford TRU waste generating facilities to certify newly generated contact-handled TRU (CH-TRU) solid waste to meet the Waste Acceptance Criteria (WAC). This document describes the plan for certifying newly generated CH-TRU solid waste to meet the WAC requirements for storage at the Waste Isolation Pilot Plant (WIPP) site. Attached to this document are facility-specific certification plans for the Westinghouse Hanford TRU waste generators that have received WACCC approval. The certification plans describe operations that generate CH-TRU solid waste and the specific procedures by which these wastes will be certified and segregated from uncertified wastes at the generating facilities. All newly generated CH-TRU solid waste is being transferred to the Transuranic Storage and Assay Facility (TRUSAF) and/or a controlled storage facility. These facilities will store the waste until the certified TRU waste can be sent to the WIPP site and the non-certified TRU waste can be sent to the Waste Receiving and Processing Facility. All non-certifiable TRU waste will be segregated and clearly identified

  16. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Summary

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy''s (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE''s Environmental Management Program

  17. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-31

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals.

  18. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals

  19. Performance assessment of geological isolation systems for radioactive waste. Summary

    International Nuclear Information System (INIS)

    The report summarizes the studies undertaken in the framework of the project PAGIS of the CEC Research Programme on radioactive waste. It concerns the analysis of the safety performances on the deep disposal of vitrified high level waste in four geological options: clay, granite, salt and the sub-seabed. The report describes the selection of sites and scenarios with the corresponding data base. It outlines the methodology adopted for determining the safety level which can be achieved with an underground disposal system for HLW. Two complementary approaches have been implemented: 1) a set of deterministic calculations for evaluating the dose rates as a function of time and for analysing local sensitivity on single parameters or components of the disposal system, 2) stochastic calculations for both uncertainty and global sensitivity analyses. For each option, the report presents the most significant results, obtained from the calculations at specific sites-from both the approaches. Apart the dose rates and their expectation values, the predominant radionuclides and pathways to man are identified as well as the most sensitive parameters and phenomena. The final chapter concludes stating the feasibility of safe disposal of HLW in underground repositories. This document is one of a set of 5 reports covering a relevant project of the European Community on a nuclear safety subject having very wide interest. The five volumes are: the summary (EUR 11775-EN), the clay (EUR 11776-EN), the granite (EUR 11777-FR), the salt (EUR 11778-EN) and the sub-seabed (EUR 11779-EN)

  20. Isolation and characterisation of circoviruses from pigs with wasting syndromes in Spain, Denmark and Northern Ireland

    DEFF Research Database (Denmark)

    Allan, G.M.; Mc Neilly, F.; Meehan, B.M.;

    1999-01-01

    A porcine circovirus (PCV) was isolated from tissues of pigs with wasting syndromes from Spain, Denmark and N. Ireland. The antigenic profiles of these viruses were determined by indirect immunofluorescence assays using polyclonal antisera and monoclonal antibodies (mAbs) prepared against...

  1. Geochemical assessment of nuclear waste isolation. Report of activities during fiscal year 1982

    Energy Technology Data Exchange (ETDEWEB)

    1983-07-01

    The status of the following investigations is reported: canister/overpack-backfill chemical interactions and mechanisms; backfill and near-field host rock chemical interactions mechanisms; far-field host rock geochemical interactions; verification and improvement of predictive algorithms for radionuclide migration; and geologic systems as analogues for long-term radioactive waste isolation.

  2. Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report

    Energy Technology Data Exchange (ETDEWEB)

    Beauheim, R.L. [Sandia National Labs., Albuquerque, NM (United States); Roberts, R.M.; Dale, T.F.; Fort, M.D.; Stensrud, W.A. [INTERA, Inc., Austin, TX (United States)

    1993-12-01

    Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations.

  3. Industrial Safety. MAS-123. Waste Isolation Division (WID). Management and Supervisor Training (MAST) Program.

    Science.gov (United States)

    Westinghouse Electric Corp., Carlsbad, NM.

    This learning module, which is part of a management and supervisor training program for managers and supervisors employed at the Department of Energy's Waste Isolation Division, is designed to prepare trainees to promote and monitor the industrial safety program at their plant. The following topics are covered in the module's individual sections:…

  4. Waste isolation facility description for the spent fuel cycle, bedded salt

    Energy Technology Data Exchange (ETDEWEB)

    1977-05-01

    Details are given on surface facilities, shafts and hoists, mine facilities, ventilation systems, land improvements, and utilities. Accidents, confinement, and safety criteria are covered. Appendices are provided on mine layout and development, mine operations, shaft construction information, and analysis concerning canister rupture inside the proposed waste isolation facility. (LK)

  5. Seismic reflection data report: Waste Isolation Pilot Plant (WIPP) site, Southeastern New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Hern, J.L.; Powers, D.W.; Barrows, L.J.

    1978-12-01

    Volume II contains uninterpreted processed lines and shotpoint maps from three seismic reflection surveys conducted from 1976 through 1978 by Sandia Laboratories to support investigations for the Waste Isolation Pilot Plant. Data interpretations will be the subject of subsequent reports. (LK)

  6. Geochemical assessment of nuclear waste isolation. Report of activities during fiscal year 1982

    International Nuclear Information System (INIS)

    The status of the following investigations is reported: canister/overpack-backfill chemical interactions and mechanisms; backfill and near-field host rock chemical interactions mechanisms; far-field host rock geochemical interactions; verification and improvement of predictive algorithms for radionuclide migration; and geologic systems as analogues for long-term radioactive waste isolation

  7. Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report

    International Nuclear Information System (INIS)

    Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations

  8. Hydraulic Isolation of Waste Disposal Areas at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    The Melton Valley watershed at Oak Ridge National Laboratory (ORNL) is the location of several large waste disposal areas that received waste from more than 50 years of operation, production, and research activities at ORNL and the U.S. Atomic Energy Commission's Southern Regional Burial Ground for wastes from more than 50 other facilities. The major burial grounds in the valley are Solid Waste Storage Areas (SWSAs) 4, 5, and 6, where wastes were buried in more than 850 unlined trenches and more than 1500 unlined auger holes. The area includes 3 seepage pits and 3 gravel-filled trenches used by ORNL for the disposal of liquid low level wastes. The burial grounds contained several hundred thousand cubic yards of waste, and the combined inventory of the burial grounds and liquid disposal sites was well over 1 million curies. The Record of Decision for Interim Actions for the Melton Valley Watershed at ORNL selected hydraulic isolation of major waste sources as the primary mechanism for remediation of the watershed. Isolation was to be accomplished mainly through the construction of multi-layer caps over the burial grounds, seepage pits, and trenches. Groundwater diversion and collection systems were installed along the up-gradient and down-gradient edges, respectively, of selected caps to enhance the performance of the isolation system. The waste areas were covered with both Resource Conservation and Recovery Act (RCRA)-type and isolation multi-layer caps. A total of 13 multi-layer caps covering 58.7 hectares (ha) (plan view) were constructed in Melton Valley between 2003 and 2006. The project encountered considerable challenges, not the least of which was its scale, involving simultaneous construction activities at widely scattered sites across the 430-ha watershed. Detailed planning and coordination enabled year-round fieldwork, an essential requirement necessary to retain a skilled, experienced workforce and meet the contract milestone for completion. Other

  9. Environmental management assessment of the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This document contains the results of the Environmental Management Assessment of the Waste Isolation Pilot Plant (WIPP). This Assessment was conducted by EH-24 from July 19 through July 30, 1993 to advise the Secretary of Energy of the adequacy of management systems established at WIPP to ensure the protection of the environment and compliance with Federal, state, and DOE environmental requirements. The mission of WIPP is to demonstrate the safe disposal of transuranic (TRU) waste. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the management and operating contractors. This assessment revealed that WIPP`s environmental safety and health programs are satisfactory, and that all levels of the Waste Isolation Division (WID) management and staff consistently exhibit a high level of commitment to achieve environmental excellence.

  10. Environmental management assessment of the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    This document contains the results of the Environmental Management Assessment of the Waste Isolation Pilot Plant (WIPP). This Assessment was conducted by EH-24 from July 19 through July 30, 1993 to advise the Secretary of Energy of the adequacy of management systems established at WIPP to ensure the protection of the environment and compliance with Federal, state, and DOE environmental requirements. The mission of WIPP is to demonstrate the safe disposal of transuranic (TRU) waste. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the management and operating contractors. This assessment revealed that WIPP's environmental safety and health programs are satisfactory, and that all levels of the Waste Isolation Division (WID) management and staff consistently exhibit a high level of commitment to achieve environmental excellence

  11. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  12. Evaluation of salt beds in New Mexico as a geologic repository for nuclear waste. [Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Weart, W.D.

    1978-10-01

    The Department of Energy is proposing to demonstrate the acceptability of geologic disposal of radioactive waste by locating a Waste Isolation Pilot Plant (WIPP) in the salt beds 26 miles east of Carlsbad, New Mexico. The WIPP will serve as a permanent repository for defense generated transuranic contaminated waste and will also be used as a facility in which experiments and demonstrations with all radioactive waste types can be conducted. Rock salt has been the leading candidate for geologic disposal of nuclear waste since the National Academy of Science recommended in 1957 that salt for repositories receive further evaluation. Subsequent studies have failed to reveal any phenoomena which would disqualify salt beds as a repository medium. The present area being proposed for the WIPP is the second such location in the Delaware Basin for which new site data have been devloped; the first site proved geologically unacceptable. Ecologic and socioeconomic aspects have been investigated and extensive geophysical, geologic and hydrologic studies have been conducted to allow an evaluation of site acceptability. This paper will deal principally with the geotechnical aspects of site characterization. These studies are now sufficiently complete that the site can be recommended for further development of the WIPP. 10 figures.

  13. Pressure grouting of fractured basalt flows

    International Nuclear Information System (INIS)

    This report describes a field trial of pressure grouting in basalt and presents the results of subsequent coring and permeability measurements. The trial shows that hydraulic conductivity of fractured basalt bedrock can be significantly reduced by pressure injection of cementitious materials. The effectiveness of the pressure grout procedure was evaluated by measuring the change in the hydraulic conductivity of the bedrock. The extent of grout penetration was determined by analyzing postgrout injection drilling chips for the presence of a tracer in the grout and also by examining cores of the treated basalt. Downhole radar mapping indicated major lava flow patterns and follow water movement during a surface infiltration test. A site called Box Canyon, which is northwest of the Idaho National Engineering Laboratory (INEL), was chosen for the study because its surface outcrop geology is similar to the underlying bedrock fracture system at the INEL's Radioactive Waste Management Complex (RWMC)

  14. Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 1, Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    This volume includes the following chapters: Waste Isolation Pilot Plant RCRA A permit application; facility description; waste analysis plan; groundwater monitoring; procedures to prevent hazards; RCRA contingency plan; personnel training; corrective action for solid waste management units; and other Federal laws.

  15. Aeromagnetic Expression of Buried Basaltic Volcanoes Near Yucca Mountain, Nevada

    Science.gov (United States)

    O'Leary, D. W.; Mankinen, E.A.; Blakely, R.J.; Langenheim, V.E.; Ponce, D.A.

    2002-01-01

    A high-resolution aeromagnetic survey has defined a number of small dipolar anomalies indicating the presence of magnetic bodies buried beneath the surface of Crater Flat and the Amargosa Desert. Results of potential-field modeling indicate that isolated, small-volume, highly magnetic bodies embedded within the alluvial deposits of both areas produce the anomalies. Their physical characteristics and the fact that they tend to be aligned along major structural trends provide strong support for the hypothesis that the anomalies reflect buried basaltic volcanic centers. Other, similar anomalies are identified as possible targets for further investigation. High-resolution gravity and ground-magnetic surveys, perhaps along with drilling sources of selected anomalies and radiometric age determinations, can provide valuable constraints in estimating potential volcanic hazard to the potential nuclear waste repository at Yucca Mountain.

  16. Groundwater stream experiment for the waste isolation pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Seitz, M.G.; Bowers, D.; Fortney, D.R.

    1981-08-01

    This project was conducted to evaluate the practicality of using laboratory groundwater stream experiments to model a hydraulic breach of a nuclear waste repository located deep in a bedded salt environment. A test plan is included in this report that gives details of the apparatus, rocks, solutions, and analyses to be used in a groundwater stream experiment. Preliminary experiments revealed the essential impermeability of halite; only a small concentration of water (about 75 ppM) moved in halite by diffusion, with a coefficient of 2.0 x 10/sup -7/ cm/sup 2//s. From work completed in this program, groundwater stream experiments appear to be a practical method of establishing the chemical interactions that would occur in a breached repository in bedded salt.

  17. Container materials for isolation of radioactive waste in salt

    International Nuclear Information System (INIS)

    The workshop reviewed the extensive data on the corrosion resistance of low-carbon steel in simulated salt repository environments, determined whether these data were sufficient to recommend low-carbon steel for fabrication of the container, and assessed the suitability of other materials under consideration in the SRP. The panelists determined the need for testing and research programs, recommended experimental approaches, and recommended materials based on existing technology. On the first day of the workshop, presentations were made on waste package requirements; the expected corrosion environment; degradation processes, including a review of data from corrosion tests on carbon steel; and rationales for container design and materials, modeling studies, and planned future work. The second day was devoted to a panel caucus, presentation of workshop findings, and open discussion. 76 refs., 2 figs., 3 tabs

  18. How does one communicate ''isolation of wastes from people and environments?''

    International Nuclear Information System (INIS)

    Federal and state laws, rules, and regulations governing/controlling management of radioactive, hazardous, and mixed radioactive-hazardous wastes are replete with discussions about storage and disposal. Whereas the meanings of these words are clear and simple, politicians, regulators, engineers, and scientists have so twisted the meanings that differences between them are slurred. This paper focuses on the misuse of these words and contends that what federal and state governments, scientific and engineering communities, and other parties want is isolation of wastes from people and environments. The paper illustrates how ancient peoples successfully isolated their trinkets from people and environments for millennia, using mostly stone-age tools. It argues that modern man should be capable of isolating his exotic trinkets from the same for multiple millennia, using modern metallurgical techniques, ceramic chemistry, and computer wizardry, augmented by a more precise vocabulary and revised educational strategy. 31 refs

  19. GEOTECHNICAL ASSESSMENT AND INSTRUMENTATION NEEDS FOR NUCLEAR WASTE ISOLATION IN CRYSTALLINE AND ARGILLACEOUS ROCKS SYMPOSIUM

    Energy Technology Data Exchange (ETDEWEB)

    Authors, Various

    1978-12-19

    Today there exists in the United States a large volume of nuclear wastes that result from both military and commercial activities. The United States has to date placed major emphasis on disposal in only one rock type--salt--whereas other nations have considered other rock types, such as granite in England and Sweden and clays in Belgium. No comprehensive evaluation of isolation in rocks other than salt has been made in the United States, and it is most appropriate that other rock types be evaluated both for constructing disposal sites in areas devoid of salt and also for having alternative waste management plans in case substantial problems are encountered in using salt as a disposal medium. To evaluate the state-of-the-art, research needs, and research priorities related to waste disposal in largely-impermeable rocks, scientists and engineers working on geologic aspects of nuclear waste disposal were brought together. The Geotechnical Assessment and Instrumentation Needs (GAIN) Symposium for Nuclear Waste Isolation in Crystalline and Argillaceous Rocks was held July 16-20, 1978 in Berkeley. This report and recommendations are the proceedings from that symposium. The location, design, and testing of a potential nuclear waste disposal site are both a geologic and an engineering problem. Disposal requires isolating the wastes from the surface and subsurface of the earth for a period of time of ten to hundreds of thousands of years. Engineers have never before been called upon to predict the behavior of structures or the flow of groundwater so far into the future.

  20. WASTE ISOLATION PILOT PLANT (WIPP): THE NATIONS' SOLUTION TO NUCLEAR WASTE STORAGE AND DISPOSAL ISSUES

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, Tammy Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-07-17

    In the southeastern portion of my home state of New Mexico lies the Chihuahauan desert, where a transuranic (TRU), underground disposal site known as the Waste Isolation Pilot Plant (WIPP) occupies 16 square miles. Full operation status began in March 1999, the year I graduated from Los Alamos High School, in Los Alamos, NM, the birthplace of the atomic bomb and one of the nation’s main TRU waste generator sites. During the time of its development and until recently, I did not have a full grasp on the role Los Alamos was playing in regards to WIPP. WIPP is used to store and dispose of TRU waste that has been generated since the 1940s because of nuclear weapons research and testing operations that have occurred in Los Alamos, NM and at other sites throughout the United States (U.S.). TRU waste consists of items that are contaminated with artificial, man-made radioactive elements that have atomic numbers greater than uranium, or are trans-uranic, on the periodic table of elements and it has longevity characteristics that may be hazardous to human health and the environment. Therefore, WIPP has underground rooms that have been carved out of 2,000 square foot thick salt formations approximately 2,150 feet underground so that the TRU waste can be isolated and disposed of. WIPP has operated safely and successfully until this year, when two unrelated events occurred in February 2014. With these events, the safety precautions and measures that have been operating at WIPP for the last 15 years are being revised and improved to ensure that other such events do not occur again.

  1. Waste Isolation Pilot Plant (WIPP) five-year Site Specific Plan

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development facility vested with the vital mission of demonstrating the safe disposal of radioactive transuranic (TRU) wastes resulting from our nation's defense activities and programs. It is the only facility in the United States specifically designed and constructed for the long-term storage of transuranic wastes. Since the inception of the WIPP project, work has continued to prepare the facility to receive TRU waste. A multitude of studies have been and continue to be conducted to demonstrate the safety of the WIPP facility in accordance with federal and state laws, state agreements, DOE Orders, etc. This Site Specific Plan outlines the implementation of activities at the WIPP project. 12 figs

  2. Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on an issues hierarchy and data needs for site characterization

    International Nuclear Information System (INIS)

    At the request of the Salt Repository Project (SRPO), Argonne National Laboratory conducted an independent peer review of a report by the Battelle Office of Nuclear Waste Isolation entitled ''Salt Repository Project Issues Hierarchy and Data Needs for Site Characterization (Draft).'' This report provided a logical structure for evaluating the outstanding questions (issues) related to selection and licensing of a site as a high-level waste repository. It also provided a first estimate of the information and data necessary to answer or resolve those questions. As such, this report is the first step in developing a strategy for site characterization. Microfiche copies of ''Draft Issues Hierarchy, Resolution Strategy, and Information Needs for Site Characterization and Environmental/Socioeconomic Evaluation - July, 1986'' and ''Issues Hierarchy and Data Needs for Site Characterization - February, 1985'' are included in the back pocket of this report

  3. The Waste Isolation Pilot Plant: A Success Story with International Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, M.

    2002-02-26

    The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) administers and operates the Waste Isolation Pilot Plant (WIPP) site, which hosts a deep geologic repository for safe disposal of U.S. defense-related TRU waste and is located 42 kilometers (km) east of Carlsbad, New Mexico. CBFO also manages the National Transuranic Waste Program (NTP), which oversees TRU waste management from generation to disposal. The WIPP began receiving waste in March 1999. In some areas of broad international interest, the CBFO has developed a leading expertise through its 25-year WIPP repository and TRU waste characterization activities. In addition to participating in relevant and beneficial experiments, the CBFO will provide the international community convenient access to this information by sponsoring and hosting symposia and workshops on relevant topics and by participation in international waste management organizations and topical meetings. In recognition of the successes at WIPP, the Inter national Atomic Energy Agency (IAEA) has designated WIPP as an International Center of Excellence and part of IAEA's Network of Centers of Excellence. The IAEA will foster cooperative training in and demonstration of waste disposal technologies in underground research facilities (URFs).such as WIPP. The CBFO, supported by its Science Advisor, has agreed to exchange scientific information with eight foreign radioactive waste management organizations, and three more national radioactive waste management and disposal organizations have expressed interest in similar agreements. These activities result in the cost-effective acquisition of scientific information in support of increased WIPP facility operational and post-closure assurance and reliability. It also demonstrates the CBFO's intent and resolve to honor international commitments and obligations.

  4. Risk assessment methodology development for waste isolation in geologic media

    International Nuclear Information System (INIS)

    This report constitutes the third phase of the review of reports prepared by Sandia for the USNRC; the first two phases were reported in Volumes 1 and 2 of NUREG/CR-1672. The reviewers generally agree that the compartment model used in Volume 1 to describe environmental transport is capable of accurately calculating the phenomena if suitable data is available. The sensitivity analysis of the environmental transport model as presented in Volume 2, was judged to be inferior to Volume 1. The reasons for selecting certain input variables for the sensitivity analysis are not clear. The input data and associated uncertainty ranges appear not to have been selected from real geophysical sources. The significance of results is not clear. Tabular and graphical results are not discussed. In Volume 3, the compartment model is used to derive the asymptotic values of Cm245 concentration in sub-zones of ground water, soil, surface water and sediment. Methodology is not discussed; nor how the study can be used in an overall risk assessment of a waste repository

  5. Waste Isolation Pilot Plant TruDock crane system analysis

    International Nuclear Information System (INIS)

    The WIPP TruDock crane system located in the Waste Handling Building was identified in the WIPP Safety Analysis Report (SAR), November 1995, as a potential accident concern due to failures which could result in a dropped load. The objective of this analysis is to evaluate the frequency of failure of the TruDock crane system resulting in a dropped load and subsequent loss of primary containment, i.e. drum failure. The frequency of dropped loads was estimated to be 9.81E-03/year or approximately one every 102 years (or, for the 25% contingency, 7.36E-03/year or approximately one every 136 years). The dominant accident contributor was the failure of the cable/hook assemblies, based on failure data obtained from NUREG-0612, as analyzed by PLG, Inc. The WIPP crane system undergoes a rigorous test and maintenance program, crane operation is discontinued following any abnormality, and the crane operator and load spotter are required to be trained in safe crane operation, therefore it is felt that the WIPP crane performance will exceed the data presented in NUREG-0612 and the estimated failure frequency is felt to be conservative

  6. The Geologic and Hydrogeologic Setting of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a mined repository constructed by the US Department of Energy for the permanent disposal of transuranic wastes generated since 1970 by activities related to national defense. The WIPP is located 42 km east of Carlsbad, New Mexico, in bedded salt (primarily halite) of the Late Permian (approximately 255 million years old) Salado Formation 655 m below the land surface. Characterization of the site began in the mid-1970s. Construction of the underground disposal facilities began in the early 1980s, and the facility received final certification from the US Environmental Protection Agency in May 1998. Disposal operations are planned to begin following receipt of a final permit from the State of New Mexico and resolution of legal issues. Like other proposed geologic repositories for radioactive waste, the WIPP relies on a combination of engineered and natural barriers to isolate the waste from the biosphere. Engineered barriers at the WIPP, including the seals that will be emplaced in the access shafts when the facility is decommissioned, are discussed in the context of facility design elsewhere in this volume. Physical properties of the natural barriers that contribute to the isolation of radionuclides are discussed here in the context of the physiographic, geologic, and hydrogeologic setting of the site

  7. Studies of geology and hydrology in the Basin and Range province, southwestern United States, for isolation of high-level radioactive waste: characterization of the Sonoran region, California

    International Nuclear Information System (INIS)

    The Sonoran region of California lies west of the Colorado River and adjoins the Mojave Desert on the west, Death Valley on the northwest, and the Salton trough on the south. The region is arid with annual precipitation ranging from less than 80 millimeters to as great as 250 millimeters in one mountain range; annual free-surface evaporation is as great as 2,500 millimeters. The characteristic basin and range topography of the region was caused by a mid-Tertiary period of intense crustal extension, accompanied by volcanic eruptions, clastic sedimentation, faulting, and tilting. Potential host media for isolation of high-level radioactive waste include granite and other coarsegrained plutonic rocks, ash-flow tuff, and basalt and basaltic andesite lava flows. Thick sections of the unsaturated zone in basin fill, intrusive, and volcanic rocks appear to have potential as host media. The region is bordered on the west by areas of relatively greater Quaternary faulting, vertical crustal uplift, and seismicity. The region has a few areas of Quaternary volcanic activity. Geothermal heat flows of 2.5 heat-flow units or greater and one earthquake of magnitude 6-7 have been recorded. The region includes topographically closed basins as well as basins that drain to the Colorado River. Dry lakes and playas occupy the closed basins. Ground-water recharge and surface runoff are small because of the small amount of precipitation and great potential evaporation. Natural ground-water discharge is by evaporation in the basin playas and by underflow to the Colorado River. Dissolved-solids concentration of ground water generally is less than 500 milligrams per liter, and much of it is of the sodium bicarbonate type. Ground water is saline in many of the playas, and chloride or sulfate is the predominant anion. Small tonnages of ore have been produced from numerous precious and fewer base-metal deposits. (author)

  8. Seismic Response of a Deep Underground Geologic Repository for Nuclear Waste at the Waste Isolation Pilot Plant in New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, P.E.

    1998-11-02

    The Waste Isolation Pilot Plant (WIPP) is a deep underground nuclear waste repository certified by the U.S. Environmental Protection Agency ,(EPA) to store transuranic defense-related waste contaminated by small amounts of radioactive materials. Located at a depth of about 655 meters below the surface, the facility is sited in southeastern New Mexico, about 40 Department of Energy underground facilities, waste disposal. kilometers east of the city of Carlsbad, New Mexico. The U.S. (DOE) managed the design and construction of the surface and and remains responsible for operation and closure following The managing and operating contractor for the DOE at the WIPP, Westinghouse Electric Corporation, maintains two rechmiant seismic monitoring systems located at the surface and in the underground. This report discusses two earthquakes detected by the seismic monitoring system, one a duratior magnitude 5.0 (Md) event located approximately 60 km east-southeast of the facility, and another a body-wave magnitude 5.6 (rob) event that occurred approximately 260 kilometers to the south-southeast.

  9. WIPP conceptual design report. Addendum J. Support equipment in the high level waste facility of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Aerojet Manufacturing Company (AMCO) received a contract in November 1976 to provide consulting services in assisting Holmes and Narver, Incorporated with the conceptual designs, cost estimates, and schedules of equipment used to handle waste casks, to decontaminate waste canisters and to overpack damaged or highly contaminated waste canisters for the Waste Isolation Pilot Plant (WIPP). Also, the layout of the hot cell in which canister handling, overpack and decontamination takes place was to be reviewed along with the time and motion study of the cell operations. This report has been prepared to present the results of the efforts and contains all technical and planning data developed during the program. The contents of this report are presented in three sections: (1) comments on the existing design criteria, equipment conceptual designs, hot cell design and time and motion studies of projected hot cell activities; (2) design descriptions of the equipment concepts and justification for varying from the existing concept (if a variation occurred). Drawings of each concept are provided in Appendix A. These design descriptions and drawings were used as the basis for the cost estimates; and (3) schedule projections and cost estimates for the equipment described in Section 2. Detail cost estimate backup data is provided in Appendix B

  10. ISOLATION AND SELECTION OF ALKALINE PROTEOLYTIC BACTERIA FROM LEATHER PR OCESSING WASTE AND ENZYME CHARACTERIZATION

    Directory of Open Access Journals (Sweden)

    MARITA ANGGARANi

    2004-01-01

    Full Text Available The aims of this experiment were to isolate alkaline protease producing bacteria from leather processing waste, and to study the biochemical properties of the enzyme produced by the selected bacteria. Nine bacterial isolates incubated at 37"C, revealed proteolytic activity on skim milk containing media. Four isolates were grown at pH 9 and another four isolates at pH 10 and only one isolate at pH 11. However, in further subculture, there were only three isolates that showed proteolytic activity, namely, D2, D7, and D l l . Among the three isolates, isolate D2 was the highest protease producer. The highest protease production (36.5U/L was reached after a 36-hr fermentation at pH 9. The optimum activity of D2 protease was observed at pH 8 and 60"C. The enzyme was stable at pH range of 7-10, and at temperature of 52-62"C. In the presence of 5mM EDTA or PMSF, the crude enzyme activity decreased to 7.04% and 23.29% respectively, which indicated that the enzyme might be a metal dependent serine protease. Zymogram analysis revealed the molecular weight of the enzyme was about 42.8kD.

  11. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    International Nuclear Information System (INIS)

    Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for the Waste Isolation Pilot Plant (WIPP) in New Mexico has developed over the past 25 years. National policy issues, negotiated agreements, and court settlements over the first half of the project had a strong influence on the amount and type of scientific data collected. Assessments and studies before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy negotiated agreements with the State of New Mexico. In the last third of the project, federal compliance policy and actual regulations were sketched out, but continued to evolve until 1996. During this eight-year period, four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed

  12. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    International Nuclear Information System (INIS)

    The opening of the Waste Isolation Pilot Plant on March 26, 1999, was the culmination of a regulatory assessment process that had taken 25 years. National policy issues, negotiated agreements, and court settlements during the first 15 years of the project had a strong influence on the amount and type of scientific data collected up to this point. Assessment activities before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to satisfy negotiated agreements with the State of New Mexico, or (3) to develop general understanding of selected natural phenomena associated with nuclear waste disposal. In the last 10 years, federal compliance policy and actual regulations were sketched out, and continued to evolve until 1996. During this period, stochastic simulations were introduced as a tool for the assessment of the WIPP's performance, and four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed

  13. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    Energy Technology Data Exchange (ETDEWEB)

    RECHARD,ROBERT P.

    2000-03-01

    The opening of the Waste Isolation Pilot Plant on March 26, 1999, was the culmination of a regulatory assessment process that had taken 25 years. National policy issues, negotiated agreements, and court settlements during the first 15 years of the project had a strong influence on the amount and type of scientific data collected up to this point. Assessment activities before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to satisfy negotiated agreements with the State of New Mexico, or (3) to develop general understanding of selected natural phenomena associated with nuclear waste disposal. In the last 10 years, federal compliance policy and actual regulations were sketched out, and continued to evolve until 1996. During this period, stochastic simulations were introduced as a tool for the assessment of the WIPP's performance, and four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.

  14. Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P.

    1998-04-01

    Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for the Waste Isolation Pilot Plant (WIPP) in New Mexico has developed over the past 25 years. National policy issues, negotiated agreements, and court settlements over the first half of the project had a strong influence on the amount and type of scientific data collected. Assessments and studies before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy negotiated agreements with the State of New Mexico. In the last third of the project, federal compliance policy and actual regulations were sketched out, but continued to evolve until 1996. During this eight-year period, four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.

  15. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 4. Alternatives for waste isolation and disposal

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Volume IV of the five-volume report contains information on alternatives for final storage and disposal of radioactive wastes. Section titles include: basic concepts for geologic isolation; geologic storage alternatives; geologic disposal alternatives; extraterrestrial disposal; and, transmutation. (JGB)

  16. Regulatory dilemmas of a trans-solutional problem: Spatial and temporal isolation of radioactive wastes

    International Nuclear Information System (INIS)

    This paper explores the 'trans-solutional' nature of nuclear waste control - that it is in essence beyond human solution. To protect present and future human health, radioactive wastes require effective isolation from the biosphere for the full hazardous life of the wastes. Waste sequestration is essential to protect human beings, other forms of life in the bio-system, and the environment from adverse mutational impacts of exposures to ionizing radiation experienced in excess of those received from naturally-occurring background sources. The linear hypothesis of dose-response describes the relationship of radiation exposures to health at least with respect to cancer induction and hereditary genetic effects. The issue of risks of low-level radiation effects remains in controversy, with pressures exerted on regulators to ignore or minimize those impacts. However, recent research indicates that chronic low-dose exposures via inhalation and ingestion pathways may also give rise to non-fatal non-cancer deleterious health effects. Fatal cancers, now the primary measure of radiation injury in setting standards, may be less significant to a population in the long run than more subtle low-level impacts affecting genetic material. The latter, hard to identify or measure, may reduce developmental and reproductive capability. Given the hazardous longevity of high-level wastes, it is imperative that both protective standards and waste regulation be framed within an ethic of species responsibility. In our half century we have generated vast amounts of long-lived waste, with more promised in the coming millennium. The regulatory obligation is to isolate all nuclear wastes to best prevent any releases to the biosphere now but also to assure future generations an equal opportunity when our 'disposal' methods inevitably fail over future time, to be able to retrieve and continue to isolate the wastes that we have caused to be produced. lt follows that the standards must not calculate

  17. Barriers of repository under the conditions of underground isolation of heat releasing radioactive waste in permafrost

    International Nuclear Information System (INIS)

    The main positions and the leading principle of the ensuring of the environmental safety of the method of the underground isolation of radioactive waste in permafrost rock are presented in this work and it is shown here the peculiarities in realization of the principle of the multibarrier protection. It is substantiated here the principle of the optimal time of the capacity for work of the repository's engineered barriers. The possibility of the exclusion of the radionuclides migration beyond the working volume of the repository during the time of the potential danger of radioactive waste is also substantiated in these papers

  18. Assessing efficiency of radioactive waste isolation in containers of different materials

    International Nuclear Information System (INIS)

    The mathematical model of dynamics of radionuclide release from the protective containers into host geological massif has been developed for the deep disposal of vitrified high- level radioactive waste. According to this model, the comparable efficiency estimation of high- activity waste isolation for two variants of container construction, in particularly, steel and dense corrosion- and radiation-resistant ceramics, has been realized. The considerable advantage of ceramic container in comparison with steel container was shown. The capacity of long-lived radionuclide containment has confirmed the perspectives of the ceramics as a barrier material

  19. Waste Isolation Pilot Plant contact-handled transuranic waste preoperational checkout: Final report

    International Nuclear Information System (INIS)

    This report documents the results of the WIPP CH TRU Preoperational Checkout which was completed between June 8 and June 14, 1988 during which period, a total of 10 TRUPACT shipping containers were processed from site receipt through emplacement of the simulated waste packages in the underground storage area. Since the design of WIPP includes provisions to unload an internally contaminated TRUPACT, in the controlled environment of the Overpack and Repair Room, one TRUPACT was partially processed through this sequence of operations to verify this portion of the waste handling process as part of the checkout. The successful completion of the CH TRU Preoperational Checkout confirmed the acceptability of WIPP operating procedures, personnel, equipment, and techniques. Extrapolation of time-line data using a computer simulation model of the waste handling process has confirmed that WIPP operations can achieve the design throughput capability of 500,000 ft3/year, if required, using two waste handling shifts. The single shift throughput capability of 273,000 ft3/year exceeds the anticipated operating receival rate of about 230,000 ft3/year. At the 230,000 ft3/year rate, the combined CH TRU annual operator dose and the average individual dose (based on minimum crew size) is projected to be 13.7 rem and 0.7 rem, respectively. 6 refs., 27 figs., 3 tabs

  20. Role of a buffer component within an engineered barrier waste package and a preliminary evaluation of bentonite as a backfill material

    International Nuclear Information System (INIS)

    This paper deals with the functions, properties, and compositions of backfill components to be used in the geologic disposal of high-level nuclear waste in basalt. A conceptual design for a repository located in basalt is being developed by the Basalt Waste Isolation Project (BWIP) in which these backfill components are part of the waste package and the repository sealing system (rooms, tunnels, and shafts). The first part of the paper concerns the role of a buffer component which is located between the primary and secondary physical barriers of the waste package (the canister and overpack). The second part of the paper deals with the chemical and physical properties of bentonite, which is a primary candidate for a backfill material both in the outer backfill barrier of the waste package and in the rooms, tunnels, and shafts above the waste package

  1. A preliminary investigation of vertical crustal movements in the United Kingdom in the context of subsurface nuclear waste isolation

    International Nuclear Information System (INIS)

    Two types of change will influence the environment of a subsurface nuclear waste isolation facility: natural geological changes and changes caused by the construction of the waste repository and introduction of the waste. This report is concerned with vertical crustal movements, which are an expression of natural geological changes. Vertical crustal movements observed outside the United Kingdom are reviewed, and vertical movements in a test region of the UK investigated by comparison of geodetic levellings. The implications of vertical crustal movement to waste isolation facilities and some potentially valuable lines of research are discussed. (author)

  2. Geologic isolation of nuclear waste at high latitudes: the role of ice sheets

    Science.gov (United States)

    Person, M.; McIntosh, J.; Iverson, N.; Neuzil, C.E.; Bense, V.

    2012-01-01

    Geologic isolation of high-level nuclear waste from the biosphere requires special consideration in countries at high latitudes (>40°N) owing to the possibility of future episodes of continental glaciation (Talbot 1999). It is now widely recognized that Pleistocene continental glaciations have had a profound effect on rates of sediment erosion (Cuffey & Paterson 2010) and deformation including tectonic thrusting (Pedersen 2005) as well as groundwater flow (Person et al. 2007; Lemieux et al. 2008a,b,c). In addition, glacial mechanical loads may have generated anomalous, or fossil, pore pressures within certain clay-rich confining units (e.g. Vinard et al. 2001). Because high-level nuclear wastes must be isolated from the biosphere as long as 1 million years (McMurry et al. 2003), the likelihood of one or more continental ice sheets overrunning high-latitude sites must be considered.

  3. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    International Nuclear Information System (INIS)

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980

  4. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980.

  5. Environmental impact statement for initiation of transuranic waste disposal at the waste isolation pilot plant

    International Nuclear Information System (INIS)

    WIPP's long-standing mission is to demonstrate the safe disposal of TRU waste from US defense activities. In 1980, to comply with NEPA, US DOE completed its first environmental impact statement (EIS) which compared impacts of alternatives for TRU waste disposal. Based on this 1980 analysis, DOE decided to construct WIPP in 1981. In a 1990 decision based on examination of alternatives in a 1990 Supplemental EIS, DOE decided to continue WIPP development by proceeding with a testing program to examine WIPP's suitability as a TRU waste repository. Now, as DOE's Carlsbad Area Office (CAO) attempts to complete its regulatory obligations to begin WIPP disposal operations, CAO is developing WIPP's second supplemental EIS (SEIS-II). To complete the SEIS-II, CAO will have to meet a number of challenges. This paper explores both the past and present EISs prepared to evaluate the suitability of WIPP. The challenges in completing an objective comparison of alternatives, while also finalizing other critical-path compliance documents, controlling costs, and keeping stakeholders involved during the decision-making process are addressed

  6. Isolation and identification of Salmonella from diarrheagenic infants and young animals, sewage waste and fresh vegetables

    OpenAIRE

    Amruta Nair; T. Balasaravanan; MALIK, S V S; Vysakh Mohan; Manesh Kumar; Jess Vergis; Rawool, Deepak B.

    2015-01-01

    Aim: This study was carried out to determine the prevalence, distribution, and identification of Salmonella serotypes in diarrheagenic infants and young animals, including sewage waste and fresh vegetables. Materials and Methods: A total of 550 samples were processed for the isolation of Salmonella spp., using standard microbiological and biochemical tests. Further polymerase chain reaction (PCR) detection of Salmonella genus was carried out using self-designed primers targeting invA gene ...

  7. Data used in preliminary performance assessment of the Waste Isolation Pilot Plant (1990)

    International Nuclear Information System (INIS)

    This report documents the data available as of August 1990 and used by the Performance Assessment Division of Sandia National Laboratories in its December 1990 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Parameter values are presented in table form for the geologic subsystem, engineered barriers, borehole flow properties, climate variability, and intrusion characteristics. Sources for the data and a brief discussion of each parameter are provided. 101 refs., 72 figs., 21 tabs

  8. The Environmental Protection Agency's waste isolation pilot plant certification process: The steps leading to our decision

    International Nuclear Information System (INIS)

    On May 13, 1998, the United States Environmental Protection Agency (EPA) issued its 'final certification decision' to certify that the U. S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) will comply with the radioactive waste disposal regulations set and the WIPP Compliance Criteria set forth at 40 CFR Parts 191 (US EPA, 1993) and 194 (US EPA, 1996) respectively. The WIPP will be the nation's first deep underground disposal facility for transuranic (TRU) radioactive waste generated as a result of defence activities. Since WIPP is a first-of-a-kind facility EPA's regulatory program contains an abundance of unique technical questions, as well as controversial policy considerations and legal issues. This paper presents the process that EPA undertook to reach its final decision. Oversight of the WIPP facility by EPA is governed by the WIPP Land Withdrawal Act (WIPP LWA), passed initially by Congress in 1992 and amended in 1996. The LWA required EPA to evaluate whether the WIPP will comply with Subparts B and C of 40 CFR Part 191, known as the disposal regulations. The EPA's final certification of compliance will allow the emplacement of radioactive waste in the WIPP to begin, provided that all other applicable health and safety standards have been met. The certification also allows Los Alamos National Laboratory (LANL) to strip TRU waste from specific waste streams for disposal at the WIPP. However, the certification is subject to several conditions, most notably that EPA must approve site-specific waste characterisation measures and quality assurance plans before allowing sites other than LANL to ship waste for disposal at the WIPP

  9. Status of Waste Isolation Pilot Plant compliance with 40 CFR 191B, December 1992

    Energy Technology Data Exchange (ETDEWEB)

    Marietta, M.G.; Anderson, D.R.

    1993-10-01

    Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the US Department of Energy (DOE) must evaluate compliance with long-term regulations of the US Environmental Protection Agency (EPA). Sandia National Laboratories (SNL) is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This paper describes the 1992 preliminary comparison with Subpart B of the Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191), which regulates long-term releases of radioactive waste. Results of the 1992 PA are preliminary, and cannot be used to determine compliance or noncompliance with EPA regulations because portions of the modeling system and data base are incomplete. Results are consistent, however, with those of previous iterations of PA, and the SNL WIPP PA Department has high confidence that compliance with 40 CFR 191B can be demonstrated. Comparison of predicted radiation doses from the disposal system also gives high confidence that the disposal system is safe for long-term isolation.

  10. Status of Waste Isolation Pilot Plant compliance with 40 CFR 191B, December 1992

    International Nuclear Information System (INIS)

    Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the US Department of Energy (DOE) must evaluate compliance with long-term regulations of the US Environmental Protection Agency (EPA). Sandia National Laboratories (SNL) is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This paper describes the 1992 preliminary comparison with Subpart B of the Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191), which regulates long-term releases of radioactive waste. Results of the 1992 PA are preliminary, and cannot be used to determine compliance or noncompliance with EPA regulations because portions of the modeling system and data base are incomplete. Results are consistent, however, with those of previous iterations of PA, and the SNL WIPP PA Department has high confidence that compliance with 40 CFR 191B can be demonstrated. Comparison of predicted radiation doses from the disposal system also gives high confidence that the disposal system is safe for long-term isolation

  11. Porous materials based on cenospheres for immobilization and long-term isolation of liquid radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    A.G. Anshits; T.A. Vereshchagina; O.M. Sharonova; N.N. Anshits; N.G. Vasilieva; M.V. Burdin; I.D. Zykova; S.V. Podoinitsyn [Institute of Chemistry and Chemical Technology (Russian Federation)

    2003-07-01

    Cenospheres, or hollow silica-alumina microspheres, is one of the valuable components within coal combustion fly ash. One of the promising areas of cenosphere application is conditioning liquid radioactive waste (LRW) to reduce waste volumes and to transform waste into a solid form suitable for transport and/or storage and/or long-term disposal. It was found that chemical composition of cenosphere material is similar to the composition of a granite rock in the Earth lithosphere. Due to this property in combination with the high mechanical strength, spherical design, thermal and chemical stability, cenospheres are considered to be the suitable material for LRW long-term isolation in the form of stable mineral-like silicaalumina ceramics (feldspars, pyroxene, polucite, and nepheline). Two types of engineering forms for the cenosphere material have been developed, such as molded block porous material (porous matrices) and microspherical porous material, which can be activated by impregnation with additives trapping radionuclides (Cs-137, Sr-90). Different glass crystalline materials based on the cenospheres for immobilization and longterm isolation of liquid radioactive waste will be presented in the report including porous matrices of 40-90% open-cell porosity, microspherical porous glasses and specific sorbents. Variants to use these materials for conditioning LRW and reducing their volume by a factor of 1500 are discussed. 14 refs., 4 figs., 1 tab.

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

    International Nuclear Information System (INIS)

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

  13. Study of rock-water-nuclear waste interactions in the Pasco Basin, Washington: Part II. Preliminary equilibrium-step simulations of basalt diagenesis

    International Nuclear Information System (INIS)

    Interactions between a large number of complex chemical and physical processes have resulted in significant changes in the Pasco Basin hydrochemical system since emplacement of the first basalt flow. In order to perform preliminary simulations of the chemical evolution of this system, certain simplifying assumptions and procedures were adopted and a computer model which operates on the principal of local equilibrium was used for the mass transfer calculations. Significant uncertainties exist in both the thermodynamic and reaction rate data which were input to the computer model. In addition, the compositional characteristics of the evolving hydrochemical system remain largely unknown, especially as a function of distance along the flow path. Given these uncertainties, it remains difficult to assess the applicability of the equilibrium-step approach even though reasonable matches between observed and simulated hydrochemical data were obtained. Given the uncertainties mentioned, the predictive abilities of EQ6 are difficult, if not impossible to evaluate; our simulations produced, at best, only qualitative agreement with observed product mineral assemblages and sequences, and fluid compositions

  14. The effect of waste package components on radionuclides released from spent fuel under hydrothermal conditions

    International Nuclear Information System (INIS)

    The Basalt Waste Isolation Project has conducted a series of hydrothermal experiments to characterize waste/barrier/rock interactions as a part of its study of the Columbia River basalts as a potential medium for a nuclear waste repository. Hydrothermal tests of 3--15 months duration were performed with light water reactor spent fuel and simulated groundwater, in combination with candidate container materials (low-carbon steel or copper) and/or basalt, in order to evaluate the effect of waste package materials on spent fuel radionuclide release behavior. In all experiments, 14C, 129I, and 137Cs occurred only as dissolved species, whereas the actinides occurred in 400 nm filtrates primarily as spent fuel particles. Actinide concentrations in 1.8 nm filtrates were below detection in steel-bearing experiments. In the system spent fuel + copper, apparent time-invariant concentrations of 14C and 137Cs were obtained, but in the spent fuel + steel system, the concentrations of 14C and 137Cs increased gradually throughout the experiments. In experiments containing basalt or steel + basalt, 137Cs concentrations decreased with time. In tests with copper + basalt, 14C and 129I concentrations attained time-variant values and 137Cs concentrations decreased. Concentrations for the actinides and fission products measured in these experiments were below those calculated from Federal regulations governing radionuclide release. 12 refs., 7 figs., 5 tabs

  15. Biosynthesis of Bio surfactant by Egyptian Local Bacterial Isolates Using Different Agricultural Wastes

    International Nuclear Information System (INIS)

    Fifteen bacterial isolates were isolated from sea water from the coast of the General Petroleum Company on Suez Gulf. They were screened for bio surfactant production using emulsification activity and haemolytic activity. The most potent isolate B11 were selected according to two parameters: The ability to grow and produce surfactant and its haemolytic activity on blood agar plates. The isolate B11 was characterized and identified as Bacillus licheniformis according to API system. The isolate was subjected to different doses of gamma irradiation in a trial to improve its ability for bio surfactant production which resulted in a passive effect on bio surfactant production. Three types of agricultural wastes (Rice straw, Cane Bagasse, Corn straw) were used as fertilizers for bio surfactant biosynthesis by the promising isolate in concentrations of 1, 2, 3, 4, 5 g/l. At five g/l concentration cane bagasse gave high production of bio surfactant with maximum capacity at (32%) flowed by rice straw at 18% and corn straw at 9.8 %.

  16. Data package format for certified transuranic waste for the Waste Isolation Pilot Plant: Revision 2

    International Nuclear Information System (INIS)

    These instructions have been prepared as a reference guide for those personnel responsible for the transmission of the data package to the WIPP. For those sites having automated data processing systems available for use, it should be understood that the shipper's computer system will be used to place the information into the specified format for transmittal. The method of input will, of course, depend upon the particular system being used. Prior to shipment, the shipper's computer system must retrieve the required information for all the packages in that shipment and write the information to an IBM or IBM-compatible personal computer in the data package format. The data package will then be transmitted in ASCII format over the specified communications system to the WIPP Waste Information System (WWIS) using RLINK, which will be furnished by WIPP. Therefore, these instructions are primarily for use by data processing personnel to aid them in programming the system to provide the transmittal information in the data package format. The method to input the data into the shipper's computer system should be determined through a joint effort between the waste generator/shipper and the data processing personnel

  17. Quality assurance criteria for Waste Isolation Pilot Plant performance assessment modeling

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) as a deep geologic repository for transuranic (TRU) and TRU-mixed wastes generated by DOE Defense Program activities. Regulatory agencies, including the Environmental Protection Agency (EPA) and New Mexico Environment Department, will be forced to rely upon system modeling to determine the potential compliance of the WIPP facility with federal regulations. Specifically, long-term modeling efforts are focused on compliance with 40 CFR Part 268, ''Land Disposal Restrictions,'' and 40 CFR Part 191, ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes.'' DOE plans to use the similar conceptual models and numerical codes to demonstrate compliance under both of these regulations. Sandia National Laboratories (SNL) has been developing a system model that will be used to demonstrate potential waste migration from the WIPP facility. Because the geologic system underlying the WIPP site is not completely understood, the software code to model the system must be developed to exacting standards for its predictions to be reliable and defensible. This is a complex model that consists of many submodules used to describe various migration pathways and processes that affect potential waste migration

  18. Compliance of the Waste Isolation Pilot Plant with 40 CFR 194.24(b)

    International Nuclear Information System (INIS)

    This paper presents aspects of DOE's demonstration of compliance with the EPA regulation of the Waste Isolation Pilot Plant (WIPP). The WIPP, a geologic repository for transuranic (TRU) waste, is located 2150 feet below the ground surface in a bedded salt formation about 20 miles east of Carlsbad, NM. Performance of the WIPP as a repository requires that releases to the accessible environment not exceed the limits of the regulation 40 CFR Part 191(1) either when the WIPP is undisturbed, or if there is intrusion into the repository by drilling. In 1996, the EPA promulgated 40 CFR Part 194(2): the implementing regulation for 40 CFR Part 191. The regulatory subsection addressed here, 40 CFR 194.24(b), directs the DOE to identify and analyze the components and characteristics of the TRU waste that can impact performance of the WIPP repository, and thereby possibly impact waste containment. DOE must also analyze those waste characteristics and components that will not affect repository performance

  19. Pressure grouting of fractured basalt flows

    International Nuclear Information System (INIS)

    This report describes a field trial of pressure grouting in basalt and the results of subsequent coring and permeability measurement activities. The objective was to show that the hydraulic conductivity of fractured basalt bedrock can be significantly reduced by pressure injection of cementitious materials. The effectiveness of the pressure grout procedure was evaluated by measuring the change in the hydraulic conductivity of the bedrock. The extent of grout penetration was established by analyzing postgrout injection drilling chips for the presence of a tracer in the grout and also by examining cores of the treated basalt. Downhole radar mapping was used to establish major lava flow patterns and follow water movement during a surface infiltration test. A site called Box Canyon, which is located northwest of the INEL, was chosen for this study due to the similarity of this surface outcrop geology to that of the underlying bedrock fracture system found at the Radioactive Waste Management Complex. This study showed that hydraulic conductivity of basalt can be reduced through pressure grouting of cementitious material

  20. Early-1990 status of performance assessment for the Waste Isolation Pilot Plant disposal system

    International Nuclear Information System (INIS)

    This paper summarizes the early-1990 status of the performance-assessment work being done to evaluate compliance of the Waste Isolation Pilot Plant with the U.S. Environmental Protection Agency regulation 40 CFR Part 191, Subpart B. This regulation sets environmental standards for radioactive waste disposal (Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes). As required by Subpart B, evaluations of compliance will include probabilistic numerical simulations of repository performance and qualitative judgments. Compliance appears uncertain only in the event of human intrusion into the repository after decommissioning. Issues affecting compliance following intrusion include properties of the plugs used to seal the intruding borehole, permeability and porosity of the waste, and possible pressurization of the repository by gas generated from the organic decomposition and corrosion of the waste and containers. Research is in progress to determine the probability of intrusion and to quantify parameter uncertainties needed to include these factors in simulations of repository performance. The Department of Energy (DOE) is following two strategies to assure compliance. First, passive marker systems will be designed and implemented to reduce the likelihood of intrusion and increase the likelihood that intruders will properly reseal the repository. Second, modifications to the form of the waste and the design of the repository to achieve acceptable performance if the intruding borehole is not adequately sealed will be designed. Goals include reductions in gas generation and waste permeability and porosity. Numerous modifications are technically possible. Work in progress will evaluate proposed modifications and recommend the most promising for further testing. The DOE is confident that compliance with Subpart B of 40 CFR 191 can be established using a combination of the two strategies

  1. SWIFT [Sandia Waste Isolation Flow and Transport] II self-teaching curriculum: Illustrative problems for the Sandia Waste-Isolation Flow and Transport model for fractured media

    International Nuclear Information System (INIS)

    Several documents have been written describing SWIFT II, the most current version of the SWIFT (Sandia Waste Isolation Flow and Transport) code. Reeves et al. [1986a], describes the theory and implementation, and Reeves et al. [1986b], describes the required input of data and parameters, Ward et al. [1984a] and [1984b] describe the comparison of the results from the SWIFT code with data and other existing codes. This document is devoted to assisting the analyst who desires to use the SWIFT II Code. The analyst is referred to the User's Manual for SWIFT II (Reeves et. al. [1986b] for detailed data input instructions. Eight examples are presented to illustrate the use of SWIFT II. The implementation of the numerical simulation of the physical problem is described for each example. For each problem, a listing of the input data and a microfiche listing of the output are provided

  2. The waste isolation pilot plant. Permanent isolation of defense transuranic waste in deep geologic salt. A national solution and international model

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant is located about 42 kilometers from the city of Carlsbad, New Mexico. It is an operating deep geologic repository in bedded salt 657 meters below the surface of the Chihuahuan desert. Since its opening in March of 1999, it has received about 12,000 shipments totaling about 91,000 cubic meters of defense related transuranic (TRU) wastes. Twenty-two sites have been cleaned up of their defense-legacy TRU waste. The WIPP's shipping program has an untarnished safety record and its trucks and trailers have safely traveled the equivalent of about 60 round-trips to the Moon. WIPP received, and deserved, a variety of safety accolades over its nearly 15 year working life. In February of 2014, however, two incidents resulted in a major operational suspension and reevaluation of its safety systems, processes and equipment. The first incident was an underground mining truck fire, followed nine days later by an airborne radiation release incident. Accident Investigation Board (AIB) reports on both incidents point to failures of plans, procedures and persons. The AIB recommendations for recovery from both these incidents are numerous and are being carefully implemented. One major recommendation is to no longer have different maintenance and safety requirements for nuclear handling equipment and mining equipment. Maintenance and cleanliness of mining equipment was cited as a contributing cause to the underground fire, and the idea that there can be lesser rigor in taking care of mining equipment, when it is being operated in the same underground space as the waste handling equipment, is not tenable. At some point in the future, the changes made in response to these two incidents will be seen as a valuable lesson learned on behalf of future repository programs. WIPP will once again be seen as a ''pilot'' in the nautical sense, in terms of 'showing the way' - the way to a national and international radioactive waste

  3. The waste isolation pilot plant. Permanent isolation of defense transuranic waste in deep geologic salt. A national solution and international model

    Energy Technology Data Exchange (ETDEWEB)

    Franco, Jose; Van Luik, Abraham [US Department of Energy, Carlsbad, NM (United States). Carlsbad Field Office

    2015-07-01

    The Waste Isolation Pilot Plant is located about 42 kilometers from the city of Carlsbad, New Mexico. It is an operating deep geologic repository in bedded salt 657 meters below the surface of the Chihuahuan desert. Since its opening in March of 1999, it has received about 12,000 shipments totaling about 91,000 cubic meters of defense related transuranic (TRU) wastes. Twenty-two sites have been cleaned up of their defense-legacy TRU waste. The WIPP's shipping program has an untarnished safety record and its trucks and trailers have safely traveled the equivalent of about 60 round-trips to the Moon. WIPP received, and deserved, a variety of safety accolades over its nearly 15 year working life. In February of 2014, however, two incidents resulted in a major operational suspension and reevaluation of its safety systems, processes and equipment. The first incident was an underground mining truck fire, followed nine days later by an airborne radiation release incident. Accident Investigation Board (AIB) reports on both incidents point to failures of plans, procedures and persons. The AIB recommendations for recovery from both these incidents are numerous and are being carefully implemented. One major recommendation is to no longer have different maintenance and safety requirements for nuclear handling equipment and mining equipment. Maintenance and cleanliness of mining equipment was cited as a contributing cause to the underground fire, and the idea that there can be lesser rigor in taking care of mining equipment, when it is being operated in the same underground space as the waste handling equipment, is not tenable. At some point in the future, the changes made in response to these two incidents will be seen as a valuable lesson learned on behalf of future repository programs. WIPP will once again be seen as a ''pilot'' in the nautical sense, in terms of 'showing the way' - the way to a national and international radioactive waste

  4. Guest editorial: The 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The appropriate disposal of radioactive waste is a problem of great importance, wide-spread interest, and some controversy. As part of the solution to this problem the Waste Isolation Pilot Plant (WIPP) is under development by the US Department of Energy (DOE) for the deep geologic disposal of transuranic (TRU) waste generated by defense programs in the United States. The DOE submitted a Compliance Certification Application (CCA)17 for the WIPP to the US Environmental Protection Agency (EPA) in October 1996, and a positive certification decision for the WIPP was issued by the EPA in May 1998. The first disposal of TRU waste in the WIPP took place in March 1999. The 1996 CCA for the WIPP was supported by an extensive performance assessment (PA) carried out by Sandia National Laboratories (SNL), with this PA often designated the 1996 WIPP PA, the 1996 CCA PA, or simply the 1996 PA. In turn, the 1996 PA was supported by site characterization activities, experimental programs, model development programs, data development programs, uncertainty and sensitivity analyses, a dedicated computational environment, a rigorous quality assurance (QA) program and a sequence of earlier PAs. Further, this PA was carried out in a regulatory environment defined by the following EPA regulations: Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR Part 191) and Criteria for the Certification and Re-Certification of the Waste Isolation Pilot Plant's Compliance with the 40 CFR Part 191 Disposal Regulations (40 CFR Part 194) The WIPP is the first licensed facility in the United States for the deep geologic disposal of radioactive waste. As a result, there is extensive interest in both the WIPP and the analyses that led to its certification by the EPA for the disposal of TRU waste. The WIPP program has produced large amounts of documentation both as part of the CCA itself and in large

  5. HUMIC ACID-LIKE MATTER ISOLATED FROM GREEN URBAN WASTES. PART II: PERFORMANCE IN CHEMICAL AND ENVIRONMENTAL TECHNOLOGIES

    OpenAIRE

    Enzo Montoneri; Piero Savarino; Stefano Bottigliengo; Giorgia Musso; Vittorio Boffa; Alessandra Bianco Prevot; Debora Fabbri; Edmondo Pramauro

    2008-01-01

    Novel uses of the organic fraction of municipal solid wastes for diversified technological applications are reported. A humic acid-like substance (cHAL2) isolated from green urban wastes was tested as a chemical auxiliary for fabric cleaning and dyeing, and as a catalyst for the photodegradation of dyes. The results illustrate the fact that biomass wastes can be an interesting source of products for the chemical market. Process and product development in this direction are likely to offer hig...

  6. Effects of wire rope in a Waste Isolation Pilot Plant (WIPP) waste shaft accident

    International Nuclear Information System (INIS)

    This report describes the empirical test program conducted on a 1/22-scale model of the WIPP facility. The model was designed to study the actions and effects of the wire rope used in the Koepe or friction-type hoist planned for use in the WIPP waste shaft during various accident scenarios. It is assumed that the hoist cable breaks and the cab (or shaft conveyance) falls to the bottom of the shaft during such an accident. The report gives the results of the study and makes recommendations for a continuing program of testing and redesign of the shaft to mitigate the effects of such an accident. The wire rope is shown to act as a good shock-absorbing material

  7. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's reports on preferred repository sites within the Palo Duro Basin, Texas

    International Nuclear Information System (INIS)

    Documents are being submitted to the Salt Repository Project Office (SRPO) of the US Department of Energy (DOE) by Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) to satisfy milestones of the Salt Repository Project of the Civilian Radioactive Waste Management Program. Some of these documents are being reviewed by multidisciplinary groups of peers to ensure DOE of their adequacy and credibility. Adequacy of documents refers to their ability to meet the standards of the US Nuclear Regulatory Commission, as enunciated in 10 CFR 60, and the requirements of the National Environmental Policy Act and the Nuclear Waste Policy Act of 1982. Credibility of documents refers to the validity of the assumptions, methods, and conclusions, as well as to the completeness of coverage. This report summarizes Argonne's review of ONWI's two-volume draft report entitled Identification of Preferred Sites within the Palo Duro Basin: Vol. 1 - Palo Duro Location A, and Vol. 2 - Palo Duro Location B, dated January 1984. Argonne was requested by DOE to review these documents on January 17 and 24, 1984 (see App. A). The review procedure involved obtaining written comments on the reports from three members of Argonne's core peer review staff and three extramural experts in related research areas. The peer review panel met at Argonne on February 6, 1984, and reviewer comments were integrated into this report by the review session chairman, with the assistance of Argonne's core peer review staff. All of the peer review panelists concurred in the way in which their comments were represented in this report (see App. B). A letter report and a draft of this report were sent to SRPO on February 10, 1984, and April 17, 1984, respectively. 5 references

  8. Isolation of Indole Utilizing Bacteria Arthrobacter sp. and Alcaligenes sp. From Livestock Waste.

    Science.gov (United States)

    Kim, Minsu; Lee, Jin-Hyung; Kim, Eonmi; Choi, Hyukjae; Kim, Younghoon; Lee, Jintae

    2016-06-01

    Indole is an interspecies and interkingdom signaling molecule widespread in different environmental compartment. Although multifaceted roles of indole in different biological systems have been established, little information is available on the microbial utilization of indole in the context of combating odor emissions from different types of waste. The present study was aimed at identifying novel bacteria capable of utilizing indole as the sole carbon and energy source. From the selective enrichment of swine waste and cattle feces, we identified Gram-positive and Gram-negative bacteria belonging to the genera Arthrobacter and Alcaligenes. Bacteria belonging to the genus Alcaligenes showed higher rates of indole utilization than Arthrobacter. Indole at 1.0 mM for growth was completely utilized by Alcaligenes sp. in 16 h. Both strains produced two intermediates, anthranilic acid and isatin, during aerobic indole metabolism. These isolates were also able to grow on several indole derivatives. Interestingly, an adaptive response in terms of a decrease in cell size was observed in both strains in the presence of indole. The present study will help to explain the degradation of indole by different bacteria and also the pathways through which it is catabolized. Furthermore, these novel bacterial isolates could be potentially useful for the in situ attenuation of odorant indole and its derivatives emitted from different types of livestock waste. PMID:27570307

  9. An evaluation of air effluent and workplace radioactivity monitoring at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Improvements are needed in the Waste Isolation Pilot Plant (WIPP) air effluent and workplace radioactivity monitoring prior to receipt of radioactive wastes. This report provides a detailed review Zf radioactivity air monitoring regulatory requirements and related facility design requirements. Air monitoring data, supplied by the Westinghouse Isolation Division, are analyzed. The WIPP Final Safety Analysis Report (FSAR) requires that the WIPP radiological facilities always have multiple confinement barriers to prevent the accidental release of radioactive material to the environment. The Waste Handling Building has standard confinement barriers that satisfy the regulatory requirements, but the underground confinement barriers.include a more complex system for filtering air in the event of-an accidental release. A continuous air monitor (CAM) is an integral part of the underground confinement barrier strategy. For the last four years'' the reliability and sensitivity of the CAMs have been the subject of numerous reports and meetings which are summarized in this report. Data supplied to the Environmental Evaluation Group (EEG) show that the Station A CAM, which monitors the underground.exhaust, does not satisfy the requirements of the FSAR. The CAM system is not fail-safe, and operations appear to be affected by high levels of salt aerosol and poor detector performance. Additional test information is needed to establish the limits of CAM performance. Findings and recommendations are also provided on alternative monitoring methods, procedures and calculations

  10. Isolation and Screening of Water Microbes for Decolourisation of Textile Dye Waste

    Directory of Open Access Journals (Sweden)

    J. K. Singh,

    2016-04-01

    Full Text Available Azo dyes are widely used in textile industry. Unused dyes, consisting mainly non biodegradable released along with waste water streams without any proper pre-treatment which cause nuisance for environment and accumulate in flora as well as fauna. These also exhibit allergic, carcinogenic and mutagenic properties for human beings. Isolation and screening of azo dye degrading bacteria are economic in biodegradation and detoxification. In the present study, 200 waste water samples were collected from dye-contaminated sites of textile industries and bacterial species such as Bacillus subtilis, Pseudomonas aeruginosa and Psuedomonas putida were isolated and identified. Evaluation of decolorizing properties of these bacteriae were done by UV-Vis spectroscopy (Amax 596 nm in different concentrations using different carbon sources such as Hans’s medium and GYP medium. Maximum decolourisation of 0.1% azo dyes were recorded to be 89.0%, 91% and 86% in Hans medium containing charcoal source by Bacillus subtilis, Pseudomonas aeruginosa and Psuedomonas putida respectively at 24 hrs. These bacterial isolates may be utilized in large scale for pre-treatment for ecological balance by avoiding water pollution.

  11. Test container design/fabrication/function for the Waste Isolation Pilot Plant gas generation experiment glovebox

    International Nuclear Information System (INIS)

    The gas generation experiments (GGE) are being conducted at Argonne National Laboratory-West (ANL0W) with contact handled transuranic (CH-TRU) waste in support of the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The purpose of the GGE is to determine the different quantities and types of gases that would be produced and the gas-generation rates that would develop if brine were introduced to CH-TRU waste under post-closure WIPP disposal room conditions. The experiment requires that a prescribed matrix of CH-TRU waste be placed in a 7.5 liter test container. After loaded with the CH-TRU waste, brine and inoculum mixtures (consisting of salt and microbes indigenous to the Carlsbad, New Mexico region) are added to the waste. The test will run for an anticipated time period of three to five years. The test container itself is an ASME rated pressure vessel constructed from Hastelloy C276 to eliminate corrosion that might contaminate the experimental results. The test container is required to maintain a maximum 10% head space with a maximum working pressure of 17.25 MPa (2,500 psia). The test container is designed to provide a gas sample of the head space without the removal of brine. Assembly of the test container lid and process valves is performed inside an inert atmosphere glovebox. Glovebox mockup activities were utilized from the beginning of the design phase to ensure the test container and associated process valves were designed for remote handling. In addition, test container processes (including brine addition, sparging, leak detection, and test container pressurization) are conducted inside the glovebox

  12. Citizens guide to the Waste Isolation Pilot Plant Compliance Certification Application to the EPA

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) has submitted an application to the US Environmental Protection Agency (EPA) for a certificate showing that the Waste Isolation Pilot Plant (WIPP) complies with strict environmental regulations designed to safeguard humans and the environment for at least 10,000 years. Congress gave the EPA authority to regulate the WIPP site for disposal of transuranic waste under the 1992 WIPP Land Withdrawal Act. The EPA has one year to review the Compliance Certification Application (CCA) before determining whether the DOE has successfully documented the WIPP's compliance with federal environmental standards. The application presents the conclusions of more than 20 years of scientific and engineering work specifically dedicated to disposal of transuranic waste at the WIPP. The application thoroughly documents how the natural characteristics of the WIPP site, along with engineered features, comply with the regulations. In the application, the DOE responds fully to the federal standards and to the EPA's certification criteria. This Citizens' Guide provides an overview of the CCA and its role in moving toward final disposal of transuranic waste

  13. Geomechanical monitoring system at the Waste Isolation Pilot Plant, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    This paper describes in detail the geomechanical instrumentation system and the data base that has been established from the geomechanical monitoring program. In addition, it describes the quality assurance and control measures that are in place to ensure that the data from the underground is accurate, traceable, and defensible. The system is installed at the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This facility is being developed for the disposal of transuranic nuclear wastes in underground excavations in salt 2150 feet below the surface. The purpose of the instrumentation system is to monitor the deformations and stress changes that are occurring in the rock with time. This information is needed to routinely assess conditions in the facility and to ensure that safe operating conditions are maintained

  14. A formal expert judgment procedure for performance assessments of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is an experimental facility located in southeastern New Mexico. It has been designed to determine the feasibility of the geologic disposal of defense-generated transuranic waste in a deep bedded-salt formation. The WIPP was also designed for disposal and will operate in that capacity if approved. The WIPP Performance Assessment Department at Sandia National Laboratories has been conducting analyses to assess the long-term performance of the WIPP. These analyses sometimes require the use of expert judgment. This Department has convened several expert-judgment panels and from that experience has developed an internal quality-assurance procedure to guide the formal elicitation of expert judgment. This protocol is based on the principles found in the decision-analysis literature

  15. A formal expert judgment procedure for performance assessments of the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Trauth, K.M. [Sandia National Labs., Albuquerque, NM (United States); Guzowski, R.V. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States). Business Administration & Economics Div.

    1994-09-01

    The Waste Isolation Pilot Plant (WIPP) is an experimental facility located in southeastern New Mexico. It has been designed to determine the feasibility of the geologic disposal of defense-generated transuranic waste in a deep bedded-salt formation. The WIPP was also designed for disposal and will operate in that capacity if approved. The WIPP Performance Assessment Department at Sandia National Laboratories has been conducting analyses to assess the long-term performance of the WIPP. These analyses sometimes require the use of expert judgment. This Department has convened several expert-judgment panels and from that experience has developed an internal quality-assurance procedure to guide the formal elicitation of expert judgment. This protocol is based on the principles found in the decision-analysis literature.

  16. Waste Isolation Pilot Plant site environmental report for calendar year 1990

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental impacts and establish baselines for future quantitative environmental impact evaluations. Surface water and groundwater, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include meteorological, air quality, soil properties, and the status of the local biological community. Ecological studies focus on the immediate area surrounding the site with emphasis on the salt storage pile, whereas baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in a preoperational state, no waste has been received; therefore, certain elements required by Order DOE 5400.1 are not presented in this report. 15 figs. 19 tabs

  17. Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

    International Nuclear Information System (INIS)

    The Overall project demonstrated that toxic metals (cesium Cs and strontium Sr) in aqueous and organic wastes can be isolated from the environment through reaction with kaolinite based sorbent substrates in high temperature reactor environments. In addition, a state-of-the art laser diagnostic tool to measure droplet characteristic in practical 'dirty' laboratory environments was developed, and was featured on the cover of a recent edition of the scientific journal ''applied Spectroscopy''. Furthermore, great strides have been made in developing a theoretical model that has the potential to allow prediction of the position and life history of every particle of waste in a high temperature, turbulent flow field, a very challenging problem involving as it does, the fundamentals of two phase turbulence and of particle drag physics

  18. Historical Background on the Performance Assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    RECHARD, ROBERT P

    1999-10-21

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the U.S. Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a Research and development facility for the safe management storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and after site selection, the U.S. Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance. assessment conducted in 1996, which is summarized in this special issue of Reliability Engineering and System Safety. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This paper provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project.

  19. Microbial Gas Generation Under Expected Waste Isolation Pilot Plant Repository Conditions: Final Report

    International Nuclear Information System (INIS)

    Gas generation from the microbial degradation of the organic constituents of transuranic (TRU) waste under conditions expected in the Waste Isolation Pilot Plant (WIPP) was investigated. The biodegradation of mixed cellulosic materials and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, hypalon, leaded hypalon, and neoprene) was examined. We evaluated the effects of environmental variables such as initial atmosphere (air or nitrogen), water content (humid (∼70% relative humidity, RH) and brine inundated), and nutrient amendments (nitogen phosphate, yeast extract, and excess nitrate) on microbial gas generation. Total gas production was determined by pressure measurement and carbon dioxide (CO2) and methane (CH4) were analyzed by gas chromatography; cellulose degradation products in solution were analyzed by high-performance liquid chromatography. Microbial populations in the samples were determined by direct microscopy and molecular analysis. The results of this work are summarized.

  20. Hydraulic Testing of Salado Formation Evaporites at the Waste Isolation Pilot Plant Site: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Beauheim, Richard L.; Domski, Paul S.; Roberts, Randall M.

    1999-07-01

    This report presents interpretations of hydraulic tests conducted in bedded evaporates of the Salado Formation from May 1992 through May 1995 at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. The WIPP is a US Department of Energy research and development facility designed to demonstrate safe disposal of transuranic wastes from the nation's defense programs. The WIPP disposal horizon is located in the lower portion of the Permian Salado Formation. The hydraulic tests discussed in this report were performed in the WIPP underground facility by INTERA inc. (now Duke Engineering and Services, Inc.), Austin, Texas, following the Field Operations Plan and Addendum prepared by Saulnier (1988, 1991 ) under the technical direction of Sandia National Laboratories, Albuquerque, New Mexico.

  1. Waste Isolation Pilot Plant site environmental report for calendar year 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental impacts and establish baselines for future quantitative environmental impact evaluations. Surface water and groundwater, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include meteorological, air quality, soil properties, and the status of the local biological community. Ecological studies focus on the immediate area surrounding the site with emphasis on the salt storage pile, whereas baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in a preoperational state, no waste has been received; therefore, certain elements required by Order DOE 5400.1 are not presented in this report. 15 figs. 19 tabs.

  2. Historical Background on the Performance Assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the U.S. Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a Research and development facility for the safe management storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and after site selection, the U.S. Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance. assessment conducted in 1996, which is summarized in this special issue of Reliability Engineering and System Safety. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This paper provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project

  3. Microbial Gas Generation Under Expected Waste Isolation Pilot Plant Repository Conditions: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Gillow, J.B.; Francis, A.

    2011-07-01

    Gas generation from the microbial degradation of the organic constituents of transuranic (TRU) waste under conditions expected in the Waste Isolation Pilot Plant (WIPP) was investigated. The biodegradation of mixed cellulosic materials and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, hypalon, leaded hypalon, and neoprene) was examined. We evaluated the effects of environmental variables such as initial atmosphere (air or nitrogen), water content (humid ({approx}70% relative humidity, RH) and brine inundated), and nutrient amendments (nitogen phosphate, yeast extract, and excess nitrate) on microbial gas generation. Total gas production was determined by pressure measurement and carbon dioxide (CO{sub 2}) and methane (CH{sub 4}) were analyzed by gas chromatography; cellulose degradation products in solution were analyzed by high-performance liquid chromatography. Microbial populations in the samples were determined by direct microscopy and molecular analysis. The results of this work are summarized.

  4. Hydraulic Testing of Salado Formation Evaporites at the Waste Isolation Pilot Plant Site: Final Report

    International Nuclear Information System (INIS)

    This report presents interpretations of hydraulic tests conducted in bedded evaporates of the Salado Formation from May 1992 through May 1995 at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. The WIPP is a US Department of Energy research and development facility designed to demonstrate safe disposal of transuranic wastes from the nation's defense programs. The WIPP disposal horizon is located in the lower portion of the Permian Salado Formation. The hydraulic tests discussed in this report were performed in the WIPP underground facility by INTERA inc. (now Duke Engineering and Services, Inc.), Austin, Texas, following the Field Operations Plan and Addendum prepared by Saulnier (1988, 1991 ) under the technical direction of Sandia National Laboratories, Albuquerque, New Mexico

  5. Geomechanical monitoring system at the Waste Isolation Pilot Plant, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    This paper describes in detail the geomechanical instrumentation system and the database that has been established from the geomechanical monitoring program. In addition, it describes the quality assurance and control measures that are in place to ensure that the data from the underground is accurate, traceable, and defensible. The system is installed at the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This facility is being developed for the disposal of transuranic nuclear wastes in underground excavations in salt 655 meters below the surface. The purpose of the instrumentation system, is to monitor the deformations and stress changes that are occurring in the rock with time. This information is needed to routinely assess conditions in the facility and to ensure that safe operating conditions are maintained. The geomechanical monitoring system has provided data collection, quality control, and database maintenance, all of which are of vital importance to monitoring the geomechanical performance of underground excavations

  6. Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jost O.L. Wendt; Alan R. Kerstein; Alexander Scheeline; Arne Pearlstein; William Linak

    2003-08-06

    The Overall project demonstrated that toxic metals (cesium Cs and strontium Sr) in aqueous and organic wastes can be isolated from the environment through reaction with kaolinite based sorbent substrates in high temperature reactor environments. In addition, a state-of-the art laser diagnostic tool to measure droplet characteristic in practical 'dirty' laboratory environments was developed, and was featured on the cover of a recent edition of the scientific journal ''applied Spectroscopy''. Furthermore, great strides have been made in developing a theoretical model that has the potential to allow prediction of the position and life history of every particle of waste in a high temperature, turbulent flow field, a very challenging problem involving as it does, the fundamentals of two phase turbulence and of particle drag physics.

  7. 1987 annual water quality data report for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP), a Department of Energy facility located in southeastern New Mexico, is designed to demonstrate the safe disposal of transuranic radioactive waste resulting from the nation's defense programs. The Water Quality Sampling Program (WQSP) supports four major programs for the WIPP: site characterization, the Performance Assessment, Radiological Baseline Program, and the Ecological Monitoring Program. Results from 13 wells sampled under the WQSP are presented in this report. Water quality data from three water-bearing zones have been collected. These zones are the Culebra and Magenta Dolomite Members of the Rustler Formation and the Dewey Lake Red Beds. Results presented from the sampling include field chemistry data, general water quality parameters, trace metals, and priority pollutants. 15 refs., 55 figs., 54 tabs

  8. Continuous monitoring of natural ventilation pressure at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy research and development facility designed to demonstrate the permanent, safe disposal of US defense-generated transuranic waste. The waste storage horizon is 655 m (2150 ft) below surface in bedded salt. To date the WIPP project has not emplaced any waste. There are three intake shafts used to supply air to the underground. All air is exhausted through a single return shaft. The total design airflow during normal operations is 200 m3/s (424,000 cfm). The ventilation system is designed to provide separate air splits to construction, experimental, and storage activities. Separation is achieved by isolating the storage circuit from the construction or experimental circuits with bulkheads. Any air leakage must be towards the storage area of the facility. Field studies have shown that the pressure differential necessary to maintain the correct leakage direction is susceptible to the effects of natural ventilation; therefore, extensive studies and analyses have been conducted to quantify the natural ventilation effects on the WIPP underground airflow system. A component of this work is a monitoring system designed to measure the air properties necessary for calculation of the natural ventilation pressure (NVP). This monitoring system consists of measuring dry bulb temperature, relative humidity, and barometric pressure at strategic location on surface and underground. The psychometric parameters of the air are measured every fifteen minutes. From these data, trends can be determined showing the impact of NVP on the ventilation system during diurnal variations in surface climate. Both summer and winter conditions have been studied. To the author's knowledge this is the first reported instance of automatic and continuous production of time and temperature variant NVPs. This paper describes the results of the initial monitoring study

  9. Purification of Protease from Pseudomonas thermaerum GW1 Isolated from Poultry Waste Site

    OpenAIRE

    Gaur, Smriti; Agrahari, Sarita; Wadhwa, Neeraj

    2010-01-01

    An extracellular protease was purified from Pseudomonas thermaerum GW1 a new strain identified by morphological, biochemical and 16S rDNA sequencing. It was isolated from soil of Poultry waste site at Ghazipur near Ghaziabad, Delhi. The strain produces extra cellular protease in the culture media that was maintained at 37°C, 140 rpm. The media was harvested for protease after 48 hrs of incubation at 37°C in basal media supplemented with 1% casein. We report 6.08 fold purification of enzyme fo...

  10. Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2015-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

  11. Perspective of the Science Advisor to the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    WEART,WENDELL D.

    1999-09-03

    In 1975 Sandia National Laboratories (SNL) was asked by the predecessor to the Department of Energy to assume responsibility for the scientific programs necessary to assure the safe and satisfactory development of a geologic repository in the salt beds of southeast New Mexico. Sandia has continued in the role of Science Advisor to the Waste Isolation Pilot Plant (WIPP) to the present time. This paper will share the perspectives developed over the past 25 years as the project was brought to fruition with successful certification by the Environmental Protection Agency (EPA) on May 13, 1998 and commencement of operations on April 26, 1999.

  12. Condensed listing of surface boreholes at the Waste Isolation Pilot Plant Project through 31 December 1995

    International Nuclear Information System (INIS)

    This report contains a condensed listing of Waste Isolation Pilot Plant (WIPP) project surface boreholes drilled for the purpose of site selection and characterization through 31 December 1995. The US Department of Energy (DOE) sponsored the drilling activities, which were conducted primarily by Sandia National Laboratories. The listing provides physical attributes such as location (township, range, section, and state-plane coordinates), elevation, and total borehole depth, as well as the purpose for the borehole, drilling dates, and information about extracted cores. The report also presents the hole status (plugged, testing, monitoring, etc.) and includes salient findings and references. Maps with borehole locations and times-of-drilling charts are included

  13. Geotechnical assessment and instrumentation needs for isolation of nuclear waste in crystalline rocks: symposium proceedings

    International Nuclear Information System (INIS)

    On October 15-19, 1984, the Geotechnical Assessment and Instrumentation Needs (GAIN) Symposium was convened to examine the status of technology for the isolation of nuclear waste in crystalline rock. The objective of the 1984 GAIN Symposium was to provide technical input to the Crystalline Repository Project concerning: critical issues and information needs associated with development and assessment of a repository in crystalline rock; appropriate techniques and instrumentation for determining the information needed; and technology required to provide the measurement techniques and instrumentation for application in an exploratory shaft in crystalline rock. The findings and recommendations of the symposium are presented in these proceedings

  14. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992

    International Nuclear Information System (INIS)

    This volume documents model parameters chosen as of July 1992 that were used by the Performance Assessment Department of Sandia National Laboratories in its 1992 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Ranges and distributions for about 300 modeling parameters in the current secondary data base are presented in tables for the geologic and engineered barriers, global materials (e.g., fluid properties), and agents that act upon the WIPP disposal system such as climate variability and human-intrusion boreholes. The 49 parameters sampled in the 1992 Preliminary Performance Assessment are given special emphasis with tables and graphics that provide insight and sources of data for each parameter

  15. WIPP conceptual design report. Addendum F. HVAC systems energy analysis for Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    This report presents the results of a technical and economic analysis of alternative methods of meeting the heating, ventilating, and air conditioning requirements of the Waste Isolation Pilot Plant (WIPP) facilities proposed to be constructed in southeastern New Mexico. This report analyzes a total of ten WIPP structures to determine the most energy and economic efficient means of providing heating, ventilating, and air conditioning services. Additional analyses were performed to determine the merits of centralized versus dispersed refrigeration and heating facilities, and of performing supplemental domestic hot water heating with solar panels

  16. Life cycle costs for disposal and assured isolation of low-level radioactive waste in Connecticut

    International Nuclear Information System (INIS)

    This document presents life cycle costs for a low-level radioactive disposal facility and a comparable assured isolation facility. Cost projections were based on general plans and assumptions, including volume projections and operating life, provided by the Connecticut Hazardous Waste Management Service, for a facility designed to meet the State's needs. Life cycle costs include the costs of pre-construction activities, construction, operations, closure, and post-closure institutional control. In order to provide a better basis for understanding the relative magnitude of near-term costs and future costs, the results of present value analysis of ut-year costs are provided

  17. Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

  18. HUMIC ACID-LIKE MATTER ISOLATED FROM GREEN URBAN WASTES. PART II: PERFORMANCE IN CHEMICAL AND ENVIRONMENTAL TECHNOLOGIES

    Directory of Open Access Journals (Sweden)

    Enzo Montoneri

    2008-02-01

    Full Text Available Novel uses of the organic fraction of municipal solid wastes for diversified technological applications are reported. A humic acid-like substance (cHAL2 isolated from green urban wastes was tested as a chemical auxiliary for fabric cleaning and dyeing, and as a catalyst for the photodegradation of dyes. The results illustrate the fact that biomass wastes can be an interesting source of products for the chemical market. Process and product development in this direction are likely to offer high economic and environmental benefits in a modern, more sustainable waste treatment strategy.

  19. [Occurrence and isolation of human enteroviruses from the air of waste removal and disposal plants].

    Science.gov (United States)

    Pfirrmann, A; vanden Bossche, G

    1994-08-01

    Aerosols from waste treatment plants were examined with regard to the presence of airborne viruses. For the purpose of a comparative evaluation, two different collecting devices consisting of an electroprecipitator and a special-impinger apparatus were used for extraction and collection of viruses from air samples. The collected suspensions were concentrated and fractionated by means of hydroextraction in combination with a differential centrifugation procedure. After solubilisation of the sedimented material with the anionic detergent, sodium-dodecylsulfate, and following ultrasonic treatment, viral infectivity could be demonstrated in 12 out of 36 examined specimens, after inoculation on BGM cells. The highest virus isolation rates were obtained with the electroprecipitator. Based on the results of investigations of biological, physicochemical as well as antigenic characteristics, the isolated strains revealed to belong to the family of Picornaviridae. According to the results of additional characterization assays, the isolates were identified as Coxsackie-B and ECHO-viruses. The linkage between the occurrence of these viruses and a possible risk of infection for humans remains to be elucidated by further epidemiological studies. However, the results of the present work indicate that, besides of an increased dust and germ concentration in such facilities, there is substantial evidence of increased viral contamination as well. Enteroviruses are generally considered as indicator viruses revealing the presence of viral contaminants in tap water and sewage. As human enteroviruses can be regularly isolated from such aerosols, the detection of these viruses in air samples may also be an appropriate criterion to estimate the amount to which virus concentrations may build up within waste treatment plants. PMID:7802896

  20. Complex formation of U(VI) with Bacillus-isolates from a uranium mining waste pile

    International Nuclear Information System (INIS)

    Accumulation studies with vegetative cells and spores of three Bacillus isolates (JG-A 30, JG-A 12, JG-A 22, classified as Bacillus cereus, Bacillus sphaericus, Bacillus megaterium) from a uranium mining waste pile (Johanngeorgenstadt, Saxony) and their corresponding reference strains have shown that Bacilli accumulate high amounts of U(VI) in the concentration range examined (11-214 mg/L). Information on the binding strength and the reversibility were obtained from extraction studies with different extractants. With 0.01 M EDTA solution the uranium bound to the biomass was released almost quantitatively. The characterization of the bacterial-UO22+-complexes by time-resolved laser fluorescence spectroscopy (TRLFS) showed the formation of inner-sphere complexes with phosphate groups of the biomass. The results lead to the conclusion that the cell wall components with phosphate residues e.g., polysaccharides, teichoic and teichuroic acids or phospholipide layers of the membranes are responsible for the uranium binding. The spectroscopic studies of the U(VI)-complexes with isolated bacterial cell walls and isolated surface-layer proteins of the strain Bacillus sphaericus NCTC 9602 after cell fractionation have shown that the complexation of U(VI) with intact cells (vegetative cells or spores) is different from the coordination with isolated cell wall components, especially with the S-layer proteins. For all Bacillus strains studied in this work, a significant contribution of the S-layer proteins to the binding of uranyl to living cells can be excluded. (orig.)

  1. Supplement analysis of transuranic waste characterization and repackaging activities at the Idaho National Engineering Laboratory in support of the Waste Isolation Pilot Plant test program

    International Nuclear Information System (INIS)

    This supplement analysis has been prepared to describe new information relevant to waste retrieval, handling, and characterization at the Idaho National Engineering Laboratory (INEL) and to evaluate the need for additional documentation to satisfy the National Environmental Policy Act (NEPA). The INEL proposes to characterize and repackage contact-handled transuranic waste to support the Waste Isolation Pilot Plant (WIPP) Test Phase. Waste retrieval, handling and processing activities in support of test phase activities at the WIPP were addressed in the Supplemental Environmental Impact Statement (SEIS) for the WIPP. To ensure that test-phase wastes are properly characterized and packaged, waste containers would be retrieved, nondestructively examined, and transported from the Radioactive Waste Management Complex (RWMC) to the Hot-Fuel Examination Facility for headspace gas analysis, visual inspections to verify content code, and waste acceptance criteria compliance, then repackaging into WIPP experimental test bins or returned to drums. Following repackaging the characterized wastes would be returned to the RWMC. Waste characterization would help DOE determine WIPP compliance with US Environmental Protection Agency regulations governing disposal of transuranic waste and hazardous waste. Additionally, this program supports onsite compliance with Resource Conservation and Recovery Act (RCRA) requirements, compliance with the terms of the No-Migration Variance at WIPP, and provides data to support future waste shipments to WIPP. This analysis will help DOE determine whether there have been substantial changes made to the proposed action at the INEL, or if preparation of a supplement to the WIPP Final Environmental Impact Statement (DOE, 1980) and SEIS (DOE, 1990a) is required. This analysis is based on current information and includes details not available to the SEIS

  2. Radioactive waste disposal: Waste Isolation Pilot Plants (WIPP). March 1978-November 1989 (Citations from the NTIS data base). Report for Mar 78-Nov 89

    International Nuclear Information System (INIS)

    This bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, along with research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in related published bibliographies. (Contains 184 citations fully indexed and including a title list.)

  3. Role of borehole plugging in the evaluation of the waste isolation pilot plant

    International Nuclear Information System (INIS)

    Research on borehole plugging (BHP) is part of an integrated strategy to develop technology that can assure successful nuclear waste isolation. The application of this strategy to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico has included an assessment of the role BHP plays in the development of a repository at that site. This paper presents a description of the WIPP site, repository design, and the current research and development program. The status of drill holes -those drilled for petroleum and potash exploration and those drilled for site characterization- within the proposed site boundaries is presented. Sixty-six holes are present on the 7700 hectare (19,000 acre) site, yet only 8 penetrate as deep as the proposed repository location. The assumptions made about shaft and borehole sealing in consequence assessment studies are presented. The results of these studies indicate that borehole seals with effective permeabilities greater than tens of darcies would result in doses to maximally exposed individuals of less than 0.01% of natural background

  4. Biogeochemical Investigations to Evaluate the Performance of the Waste Isolation Pilot Plant (WIPP) (Invited)

    Science.gov (United States)

    Gillow, J. B.

    2009-12-01

    The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy facility located in southeastern New Mexico, approximately 655 m (2150 ft.) below ground surface in a bedded salt, Permian evaporite formation. This mined geologic repository has been receiving transuranic (TRU) waste from defense-related and environmental-management activities since March 1999. TRU waste contains alpha-emitting transuranic nuclides with half-lives greater than twenty years at concentrations greater than 100 nCi/gram. These actinide-contaminated wastes were generated from nuclear-weapons production and related processing activities. They include various organics, adsorbed liquids, sludges, cellulosics, plastics, rubber, and a variety of metals and cemented materials. An extensive set of investigations were performed to establish the basis for TRU waste disposal at WIPP and to support initial certification from the U.S. Environmental Protection Agency. A significant element of the conceptual geochemical model for WIPP is the microbiologically-driven reactions leading to biodegradation of organic constituents in TRU wastes, as well as interactions with actinides present in the waste. This presentation will discuss the biogeochemical investigations that were performed to evaluate microbiological activity at WIPP, including studies of gas generation due to biodegradation of cellulose, plastic, and rubber materials and actinide-microbe interactions leading to changes in actinide chemical speciation. Highlights of this work are discussed here. Cellulose biodegradation in salt-brine systems results in the generation of carbon dioxide and hydrogen, and aqueous fermentation products (low molecular weight organic acids). Hypersaline brine can limit the range of microbial metabolic pathways, due to the energetic stresses of maintaining osmotic balance compatible with metabolic processes. Methanogenesis yields the lowest free energy per mole of carbon and as such is often not detected in

  5. DRSPALL :spallings model for the Waste Isolation Pilot Plant 2004 recertification

    International Nuclear Information System (INIS)

    This report presents a model to estimate the spallings releases for the Waste Isolation Pilot Plant Performance Assessment (WIPP PA). A spallings release in the context of WIPP PA refers to a portion of the solid waste transported from the subsurface repository to the ground surface due to inadvertent oil or gas drilling into the WIPP repository at some time after site closure. Some solid waste will be removed by the action of the drillbit and drilling fluid; this waste is referred to as cuttings and cavings. If the repository is pressurized above hydrostatic at the time of intrusion, solid waste material local to the borehole may be subject to mechanical failure and entrainment in high-velocity gases as the repository pressure is released to the borehole. Solid material that fails and is transported into the wellbore and thus to the surface comprise the spallings releases. The spallings mechanism is analogous to a well blowout in the modern oil and gas drilling industry. The current spallings conceptual model and associated computer code, DRSPALL, were developed for the 2004 recertification because the prior spallings model used in the 1996 WIPP Compliance Certification Application (CCA) was judged by an independent peer review panel as inadequate (DOE 1996, 9.3.1). The current conceptual model for spallings addresses processes that take place several minutes before and after a borehole intrusion of a WIPP waste room. The model couples a pipe-flow wellbore model with a porous flow repository model, allowing high-pressure gas to flow from the repository to the wellbore through a growing cavity region at the well bottom. An elastic stress model is applied to the porous solid domain that allows for mechanical failure of repository solids if local tensile stress exceeds the tensile strength of the waste. Tensile-failed solids may be entrained into the wellbore flow stream by a fluidized bed model, in which case they are ultimately transported to the land surface

  6. DRSPALL :spallings model for the Waste Isolation Pilot Plant 2004 recertification.

    Energy Technology Data Exchange (ETDEWEB)

    Gilkey, Amy P. (GRAM Inc., Albuquerque, NM); Hansen, Clifford W.; Schatz, John F. (John F. Schatz Research & Consulting, Inc., Del Mar, CA); Rudeen, David Keith (GRAM Inc., Albuquerque, NM); Lord, David L.

    2006-02-01

    This report presents a model to estimate the spallings releases for the Waste Isolation Pilot Plant Performance Assessment (WIPP PA). A spallings release in the context of WIPP PA refers to a portion of the solid waste transported from the subsurface repository to the ground surface due to inadvertent oil or gas drilling into the WIPP repository at some time after site closure. Some solid waste will be removed by the action of the drillbit and drilling fluid; this waste is referred to as cuttings and cavings. If the repository is pressurized above hydrostatic at the time of intrusion, solid waste material local to the borehole may be subject to mechanical failure and entrainment in high-velocity gases as the repository pressure is released to the borehole. Solid material that fails and is transported into the wellbore and thus to the surface comprise the spallings releases. The spallings mechanism is analogous to a well blowout in the modern oil and gas drilling industry. The current spallings conceptual model and associated computer code, DRSPALL, were developed for the 2004 recertification because the prior spallings model used in the 1996 WIPP Compliance Certification Application (CCA) was judged by an independent peer review panel as inadequate (DOE 1996, 9.3.1). The current conceptual model for spallings addresses processes that take place several minutes before and after a borehole intrusion of a WIPP waste room. The model couples a pipe-flow wellbore model with a porous flow repository model, allowing high-pressure gas to flow from the repository to the wellbore through a growing cavity region at the well bottom. An elastic stress model is applied to the porous solid domain that allows for mechanical failure of repository solids if local tensile stress exceeds the tensile strength of the waste. Tensile-failed solids may be entrained into the wellbore flow stream by a fluidized bed model, in which case they are ultimately transported to the land surface

  7. Conceptual structure of performance assessments conducted for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Marietta, M.G.; Rechard, R.P. [Sandia National Labs., Albuquerque, NM (United States)

    1993-04-01

    The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being developed by the US Department of Energy as a disposal facility for transuranic waste. In support of this project, Sandia National Laboratories is conducting an ongoing performance assessment (PA) for the WIPP. The ordered triple representation for risk proposed by Kaplan and Garrick is used to provide a clear conceptual structure for this PA. This presentation describes how the preceding representation provides a basis in the WIPP PA for (1) the definition of scenarios and the calculation of scenario probabilities and consequences, (2) the separation of subjective and stochastic uncertainties, (3) the construction of the complementary cumulative distribution functions required in comparisons with the US Environmental Protection Agency`s standard for the geologic disposal of radioactive waste (i.e., 40 CFR Part 191, Subpart B), and (4) the performance of uncertainty and sensitivity studies. Results obtained in a preliminary PA for the WIPP completed in December of 1991 are used for illustration.

  8. Developing a data acquisition system for the Waste Isolation Pilot Plant's in situ tests

    International Nuclear Information System (INIS)

    The US Department of Energy is developing the Waste Isolation Pilot Plant in southeastern New Mexico as an R and D facility to demonstrate the safe disposal of radioactive wastes from US defense programs. The in situ tests associated with this facility (659 m below the surface) address technical issues of thermal/structural interaction, waste package performance, and plugging and sealing. Data from these tests are collected by a Data Acquisition System (DAS) consisting of two distinct entities that use the IEEE-488 bus for communication. Up to 5000 data channels can be recorded every 4 hr from extensometers, stressmeters, thermocouples, closure gages, and other special gages. The DAS consists of a multitasking and multiuser ModComp computer housed in a surface trailer that converts the data to engineering units, stores the data in raw and converted form, and provides quick-look plots and data listings. The other part of the DAS consists of the seven underground remote enclosed instrument stations (sheds) located near each test room and up to 1800 m from the surface trailer that contains the instruments and signal conditioning to operate and monitor the tests. The ModComp system manages data acquisition and supports concurrently 12 on-line terminals and two dial-up access lines for data access, gage diagnostics, data handling and updating, and software development. Data are currently acquired from over 4000 gages with 15,000 defined measurands; the system can be expanded to 65,534 measurands. 4 refs., 7 figs

  9. Selected, annotated bibliography of studies relevant to the isolation of nuclear wastes

    International Nuclear Information System (INIS)

    This annotated bibliography of 705 references represents the first in a series to be published by the Ecological Sciences Information Center containing scientific, technical, economic, and regulatory information relevant to nuclear waste isolation. Most references discuss deep geologic disposal, with fewer studies of deep seabed disposal; space disposal is also included. The publication covers both domestic and foreign literature for the period 1954 to 1980. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Envirnmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Repository Design and Engineering; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for author(s), keywords, subject category, title, geographic location, measured parameters, measured radionuclides, and publication description

  10. Development of a gas-generation model for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Design-basis transuranic (TRU) waste to be emplaced in the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico may generate significant quantities of gas, which may affect the performance of the WIPP with respect to regulations for radioactive and/or chemically hazardous waste constituents. We are developing a model to predict gas generation in WIPP disposal rooms during and after filling and sealing. Currently, the model includes: (1) oxic and anoxic corrosion of steels and other Fe-base alloys, including passivation and depassivation; (2) microbial degradation of cellulosics with O2, NO3-, FeO(OH), SO42-, or CO2 as the electron acceptor; (3) α radiolysis of brine; (4) consumption of CO2 and, perhaps, H2S by Ca(OH)2 (in cementitious materials) and CaO (a potential backfill additive). The code simulates these processes and interactions among them by converting reactants (steels, cellulosics, etc.) to gases and other products at experimentally observed or estimated rates and plotting temporal reaction paths in three-dimensional phase diagrams for solids in the Fe-H2O-CO2-H2-H2S system

  11. Conceptual structure of performance assessments conducted for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being developed by the US Department of Energy as a disposal facility for transuranic waste. In support of this project, Sandia National Laboratories is conducting an ongoing performance assessment (PA) for the WIPP. The ordered triple representation for risk proposed by Kaplan and Garrick is used to provide a clear conceptual structure for this PA. This presentation describes how the preceding representation provides a basis in the WIPP PA for (1) the definition of scenarios and the calculation of scenario probabilities and consequences, (2) the separation of subjective and stochastic uncertainties, (3) the construction of the complementary cumulative distribution functions required in comparisons with the US Environmental Protection Agency's standard for the geologic disposal of radioactive waste (i.e., 40 CFR Part 191, Subpart B), and (4) the performance of uncertainty and sensitivity studies. Results obtained in a preliminary PA for the WIPP completed in December of 1991 are used for illustration

  12. Conceptual structure of performance assessments conducted for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant: (WIPP) in southeastern New Mexico is being developed by the US Department of Energy as a disposal facility for transuranic waste. In support of this project, Sandia National Laboratories is conducting an ongoing performance assessment (PA) for the WIPP. The ordered triple- representation for risk proposed by Kaplan and Garrick is used to provide a clear conceptual structure for this PA. This presentation describes how the preceding representation provides a basis in the WIPP PA for (1) the definition of scenarios and the calculation of scenario probabilities and consequences, (2) the separation of subjective and stochastic uncertainties, (3) the construction of the complementary cumulative distribution functions required in comparisons with the US Environmental Protection Agency's standard for the geologic disposal of radioactive waste (i.e., 40 CFR Part 191, Subpart B), and (4) the performance of uncertainty and sensitivity studies. Results obtained in a preliminary PA for the WIPP completed in December of 1991 are used for illustration

  13. Summary discussion of the 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is under development by the US Department of Energy (DOE) for the geologic disposal of transuranic waste. The construction of complementary cumulative distribution functions (CCDFs) for total radionuclide release from the WIPP to the accessible environment is described. The resultant CCDFs (1) combine releases due to cuttings and cavings, spallings, direct brine release, and long-term transport in flowing groundwater, (2) fall substantially to the left of the boundary line specified by the U.S. Environmental Protection Agency's (EPA's) standard 40 CFR 191 for the geologic disposal of radioactive waste, and (3) constitute an important component of the DOE's successful Compliance Certification Application to the EPA for the WIPP. Insights and perspectives gained in the performance assessment (PA) that led to these CCDFs are described, including the importance of (1) an iterative approach to PA, (2) uncertainty and sensitivity analysis, (3) a clear conceptual model for the analysis, (4) the separation of stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, (5) quality assurance procedures, (6) early involvement of peer reviewers, regulators, and stake holders, (7) avoidance of conservative assumptions, and (8) adequate documentation

  14. Probabilistic system assessment of the long-term safety of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the U.S. Department of Energy (DOE) must evaluate compliance with long-term regulations of the U.S. Environmental Protection Agency, specifically, the open-quotes Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastesclose quotes (40CFR191) and the open-quotes Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Actclose quotes (RCRA, IOCFR268.6). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance and to comply with the requirements of the Land Withdrawal Act (PL-102-579), which reinstated the major part of 40CFR191 for the WIPP as first promulgated in 1985 and also requires biennial PAs. An additional, nonregulatory objective, which has been requested by the DOE and National Academy of Sciences WIPP Panel, is to evaluate the long-term safety of the WIPP

  15. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

  16. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992

    International Nuclear Information System (INIS)

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA's Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6

  17. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992

    International Nuclear Information System (INIS)

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume of the 1992 PA contains results of uncertainty and sensitivity analyses with respect to the EPA's Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Additional information about the 1992 PA is provided in other volumes. Results of the 1992 uncertainty and sensitivity analyses indicate that, conditional on the modeling assumptions, the choice of parameters selected for sampling, and the assigned parameter-value distributions, the most important parameters for which uncertainty has the potential to affect compliance with 40 CFR 191B are: drilling intensity, intrusion borehole permeability, halite and anhydrite permeabilities, radionuclide solubilities and distribution coefficients, fracture spacing in the Culebra Dolomite Member of the Rustler Formation, porosity of the Culebra, and spatial variability of Culebra transmissivity. Performance with respect to 40 CFR 191B is insensitive to uncertainty in other parameters; however, additional data are needed to confirm that reality lies within the assigned distributions

  18. Uncertainty and Sensitivity Analysis in Performance Assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C.

    1998-12-17

    The Waste Isolation Pilot Plant (WIPP) is under development by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. This development has been supported by a sequence of performance assessments (PAs) carried out by Sandla National Laboratories (SNL) to assess what is known about the WIPP and to provide .tidance for future DOE research and development activities. Uncertainty and sensitivity analysis procedures based on Latin hypercube sampling and regression techniques play an important role in these PAs by providing an assessment of the uncertainty in important analysis outcomes and identi~ing the sources of thk uncertainty. Performance assessments for the WIPP are conceptually and computational] y interesting due to regulatory requirements to assess and display the effects of both stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, where stochastic uncertainty arises from the possible disruptions that could occur over the 10,000 yr regulatory period associated with the WIPP and subjective uncertainty arises from an inability to unambi-aously characterize the many models and associated parameters required in a PA for the WIPP. The interplay between uncertainty analysis, sensitivity analysis, stochastic uncertainty and subjective uncertainty are discussed and illustrated in the context of a recent PA carried out by SNL to support an application by the DOE to the U.S. Environmental Protection Agency for the certification of the WIPP for the disposal of TRU waste.

  19. Performance Assessment in Support of the 1996 Compliance Certification Application for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, D.R.; Basabilvazo, G.; Helton, J.C.; Jow, H.-N.; Marietta, M.G.

    1998-10-14

    The conceptual and computational structure of a performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) is described. Important parts of thk structure are @ maintenance of a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertain, with stochastic uncefinty arising from the many possible disruptions that could occur over the 10,000 Y regulatory period fiat applies to the WIPP and subjective uncertainty arising from `the imprecision with which many of the quantities rquired in tie `hdysis are known, (ii) use of Latin hypercttbe sampling to incorporate the effects of subjective uncefirtty, (iii) use of Monte Carlo (i.e., random) sampling to incorporate the effects of stochastic uncetinty, and OV) efficient use of tie necessarily limited number of mechanistic calculations that can be performed to SUPPOII the analysis. The WIPP is under development by the U.S. Department of Ener~ (DOE) for the geologic (i.e., deep underground) disposal of transuranic (TRU) waste, with the indicated PA supporting a ~Compliance Certification Application (CCA) by the DOE to the U.S. Environmental Protection Agency (EPA) in October 1996 for tie necessary certifications for the WIPP to begin operation. If certified, the WIPP will be the first operational faciliv in tie United States for the geologic disposal of ra&oactive waste.

  20. Summary discussion of the 1996 performance assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    HELTON,JON CRAIG; ANDERSON,D. RICHARD; BASABILVAZO,G.; JOW,HONG-NIAN; MARIETTA,MELVIN G.

    2000-05-19

    The Waste Isolation Pilot Plant (WIPP) is under development by the US Department of Energy (DOE) for the geologic disposal of transuranic waste. The construction of complementary cumulative distribution functions (CCDFs) for total radionuclide release from the WIPP to the accessible environment is described. The resultant CCDFs (1) combine releases due to cuttings and cavings, spallings, direct brine release, and long-term transport in flowing groundwater, (2) fall substantially to the left of the boundary line specified by the U.S. Environmental Protection Agency's (EPA's) standard 40 CFR 191 for the geologic disposal of radioactive waste, and (3) constitute an important component of the DOE's successful Compliance Certification Application to the EPA for the WIPP. Insights and perspectives gained in the performance assessment (PA) that led to these CCDFs are described, including the importance of (1) an iterative approach to PA, (2) uncertainty and sensitivity analysis, (3) a clear conceptual model for the analysis, (4) the separation of stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, (5) quality assurance procedures, (6) early involvement of peer reviewers, regulators, and stake holders, (7) avoidance of conservative assumptions, and (8) adequate documentation.

  1. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

  2. Selected, annotated bibliography of studies relevant to the isolation of nuclear wastes. [705 references

    Energy Technology Data Exchange (ETDEWEB)

    Hyder, L.K.; Fore, C.S.; Vaughan, N.D.; Faust, R.A.

    1980-09-01

    This annotated bibliography of 705 references represents the first in a series to be published by the Ecological Sciences Information Center containing scientific, technical, economic, and regulatory information relevant to nuclear waste isolation. Most references discuss deep geologic disposal, with fewer studies of deep seabed disposal; space disposal is also included. The publication covers both domestic and foreign literature for the period 1954 to 1980. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Envirnmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Repository Design and Engineering; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for author(s), keywords, subject category, title, geographic location, measured parameters, measured radionuclides, and publication description.

  3. Understanding and involvement: The key to public acceptance of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a research and development project of the US Department of Energy (DOE) that is authorized under Public Law 96-164 to demonstrate the safe disposal of radioactive wastes resulting from defense programs of the US. Westinghouse Electric Corporation is the management and operating contractor of the WIPP for the DOE. The transportation and disposal of transuranic radioactive wastes require an extensive public and media information program. This program must be able to respond to numerous information requests and concerns from state governments, citizens on the transportation routes, political leaders, public interest groups, emergency responders, and national and local media. The WIPP has developed a proactive program that aggressively provides information to these audiences through written and visual products, exhibits, presentations, and tours. As a result, thousands of interested parties have had their questions and concerns addressed, resulting in public understanding and support of the project's mission and its commitment to the safety of the public and the environment

  4. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's plan to decommission and reclaim exploratory shafts and related facilities

    International Nuclear Information System (INIS)

    The following recommendations are made for improving the Office of Nuclear Waste Isolation's plan for decommissioning and reclaiming exploratory shafts and other facilities associated with site characterization: (1) Discuss more comprehensively the technical aspects of activities related to decommissioning and reclamation. More detailed information will help convince the staff of the US Nuclear Regulatory Commission and others that the activities as outlined in the plan are properly structured and that the stated goals can be achieved. (2) Address in considerably greater detail how the proposed activities will satisfy specific federal, state, and local laws and regulations. (3) State clearly the precise purpose of the plan, preferably at the beginning and under an appropriate heading. (4) Also under an appropriate heading and immediately after the section on purpose, describe the scope of the plan. The tasks covered by this plan and closely related tasks covered by other appropriate plans should be clearly differentiated. (5) Discuss the possible environmental effects of drilling the exploratory shaft, excavating drifts in salt, and drilling boreholes as part of site characterization. Mitigation activities should be designed to counter specific potential impacts. High priority should be given to minimizing groundwater contamination and restoring the surface to a condition consistent with the proposed land use following completion of characterization activities at sites not chosen for repository construction. (6) Define ambiguous technical terms, either in the text when first introduced or in an appended glossary

  5. The effect of stratigraphic dip on multiphase flow at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy research and development facility for the underground disposal of transuranic waste from US defense-related activities. The WIPP repository is located within the Salado Formation, which is comprised of beds of pure and impure halite with thin interbeds of anhydrite and related clay seams. This formation is brine saturated with a pore pressure of approximately 12.5 MPa at the repository horizon. The Salado Formation dips gently southeast, on the average approximately 1 degree, with steeper dips locally. Elevated repository pressures, caused by gas generated as emplaced waste corrodes and degrades, may drive brine and gas out of the repository into the surrounding formation. Stratigraphic dip may cause increased brine inflow to the repository through countercurrent flow in the interbeds and enhanced gas migration distances in the updip direction due to buoyancy. Two-dimensional simulations of isolated WIPP repository room have been performed using TOUGH2 for horizontal and 1 degree dipping stratigraphy. The impact of dip on multiphase flow at the WIPP may be significant. With dip, an additional mechanism for brine inflow may occur, namely the formation of a cell of countercurrent brine and gas flow in the interbeds. The additional volume of brine inflow resulting from the countercurrent flow cell may be of similar magnitude to brine inflow without dip. Therefore, dip must be included in any repository model to include the countercurrent brine inflow mechanism. Gas migration may also be significantly influenced due to dip. Gas migration distances may increase dramatically with preferential migration updip

  6. Fluid flow through very low permeability materials: A concern in the geological isolation of waste

    Energy Technology Data Exchange (ETDEWEB)

    Deal, D.E.

    1992-12-31

    The geological isolation of waste usually involves the selection of sites where very low permeability materials exist, but there are few earth materials that are truly impermeable. Regulatory concerns for the containment of radioactive material extend for geologic periods of time (i.e., 10,000 years or more), and it becomes nearly impossible to ``assure`` the behavior of the site for such long periods of time. Experience at the Waste Isolation Pilot Plant (WIPP) shows that very slow movements of fluid can take place through materials that may, in fact, have no intrinsic permeability in their undisturbed condition. Conventional hydrologic models may not be appropriate to describe flow, may provide modeling results that could be in significant variance with reality, and may not be easy to defend during the compliance process. Additionally, the very small volumes of fluid and very slow flow rates involved are difficult to observe, measure, and quantify. The WIPP disposal horizon is excavated 655 m below the surface in bedded salt of Permian age. Salt has some unique properties, but similar hydrologic problems can be expected in site investigations were other relatively impermeable beds occur, and especially in deep sites where significant overburden and confining pressures may be encountered. Innovative techniques developed during the investigations at the WIPP may find utility when investigating other disposal sites. Ongoing work at the WIPP is expected to continue to advance understanding of flow through very low permeability materials. The study of flow under these conditions will become increasingly important as additional waste disposal sites are designed that require assurance of their safety for geological periods of time.

  7. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992

    International Nuclear Information System (INIS)

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume of the 1992 PA contains results of uncertainty and sensitivity analyses with respect to migration of gas and brine from the undisturbed repository. Additional information about the 1992 PA is provided in other volumes. Volume 1 contains an overview of WIPP PA and results of a preliminary comparison with 40 CFR 191, Subpart B. Volume 2 describes the technical basis for the performance assessment, including descriptions of the linked computational models used in the Monte Carlo analyses. Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses with respect to the EPA's Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Finally, guidance derived from the entire 1992 PA is presented in Volume 6. Results of the 1992 uncertainty and sensitivity analyses indicate that, conditional on the modeling assumptions and the assigned parameter-value distributions, the most important parameters for which uncertainty has the potential to affect gas and brine migration from the undisturbed repository are: initial liquid saturation in the waste, anhydrite permeability, biodegradation-reaction stoichiometry, gas-generation rates for both corrosion and biodegradation under inundated conditions, and the permeability of the long-term shaft seal

  8. Initial Q-list for the prospective Yucca Mountain repository based on items important to safety and waste isolation

    International Nuclear Information System (INIS)

    A method for identifying items important to safety based on a probabilistic risk assessment approach was developed and implemented for the conceptual design of the Yucca Mountain repository. No items were classified as important to safety; however, six items were classified as potentially important to safety. These were the shipping cask, the cranes and the truck or rail-care vehicle stops in the cask receiving and preparation area, the hot cell structure of the waste packaging hot cells, the cranes in the waste packaging hot cells, and the waste-handling building fire protection system. In addition, a method for identifying items important to waste isolation was developed and implemented. Two hydrogeologic units of the Yucca Mountain site were classified as important to waste isolation: the Calico Hills nonwelded zeolitic unit and the Calico Hills nonwelded vitric unit. The preliminary Q-list for the Yucca Mountain repository is comprised of the two units of the site classified as important to waste isolation and contains no items important to safety

  9. Initial Q-list for the prospective Yucca Mountain repository based on items important to safety and waste isolation

    International Nuclear Information System (INIS)

    A method for identifying items important to safety based on a probabilistic risk assessment approach was developed and implemented for the conceptual design of the Yucca Mountain repository. No items were classified as important to safety; however, six items were classified as potentially important to safety. These were the shipping cask, the cranes and the truck or rail-car vehicle stops in the cask receiving and preparation area, the hot cell structure of the waste packaging hot cells, the cranes in the waste packaging hot cells, and the waste-handling building fire protection system. In addition, a method for identifying items important to waste isolation was developed and implemented. Two hydrogeologic units of the Yucca Mountain site were classified as important to waste isolation: the Calico Hills nonwelded zeolitic unit and the Calico Hills nonwelded vitric unit. The preliminary Q-list for the Yucca Mountain repository is comprised of the two units of the site classified as important to waste isolation and contains no items important to safety

  10. Review comments on the report of the steering committee on waste acceptance criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    General comments by the EEG on waste acceptance criteria (WAC) as published in recent WIPP reports are: methods to be used by waste generating facilities to determine compliance with the WAC are lacking; provisions for inspection of the WIPP and the waste generating facility to determine compliance with WAC are needed; standardized terminology is needed in the WAC so that mandatory compliance is understood; some criteria apply only to CH- and RH-TRU wastes not to experimental high-level wastes; a statement should be included stating what further action would be taken if a contaminated waste shipment required overpacking. Specific comments are also included on gas generation, pyrophoric materials, toxic and corrosive materials, waste containers and overbacks, waste package size, surface dose rate, surface contamination, certification and labelling

  11. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 1, Chapters 1--6

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy's (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE's Environmental Management Program. Chapters 1--6 include an introduction, background information, description of the proposed action and alternatives, description of the affected environments, environmental impacts, and consultations and permits

  12. Waste Isolation Pilot Plant disposal phase supplemental environmental impact statement. Implementation plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The Implementation Plan for the Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (SEIS-II) has two primary purposes: (1) To report on the results of the scoping process (2) To provide guidance for preparing SEIS-II SEIS-II will be the National Environmental Policy Act (NEPA) review for WIPP`s disposal phase. Chapter 1 of this plan provides background on WIPP and this NEPA review. Chapter 2 describes the purpose and need for action by the Department of Energy (hereafter DOE or the Department), as well as a description of the Proposed Action and alternatives being considered. Chapter 3 describes the work plan, including the schedule, responsibilities, and planned consultations with other agencies and organizations. Chapter 4 describes the scoping process, presents major issues identified during the scoping process, and briefly indicates how issues will be addressed in SEIS-II.

  13. Waste Isolation Pilot Plant disposal phase supplemental environmental impact statement. Implementation plan

    International Nuclear Information System (INIS)

    The Implementation Plan for the Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (SEIS-II) has two primary purposes: (1) To report on the results of the scoping process (2) To provide guidance for preparing SEIS-II SEIS-II will be the National Environmental Policy Act (NEPA) review for WIPP's disposal phase. Chapter 1 of this plan provides background on WIPP and this NEPA review. Chapter 2 describes the purpose and need for action by the Department of Energy (hereafter DOE or the Department), as well as a description of the Proposed Action and alternatives being considered. Chapter 3 describes the work plan, including the schedule, responsibilities, and planned consultations with other agencies and organizations. Chapter 4 describes the scoping process, presents major issues identified during the scoping process, and briefly indicates how issues will be addressed in SEIS-II

  14. Computational implementation of a systems prioritization methodology for the Waste Isolation Pilot Plant: a preliminary example

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C.; Anderson, D.R.; Baker, B.L.; Bean, J.E.; Berglund, J.W.; Beyeler, W.; Blaine, R.; Economy, K.; Garner, J.W.; Hora, S.C.; Lincoln, R.C.; Marietta, M.G.; Mendenhall, F.T.; Prindle, N.H.; Rudeen, D.K.; Schreiber, J.D.; Shiver, A.W.; Smith, L.N.; Swift, P.N.; Vaughn, P

    1997-09-01

    A systems prioritization methodology (SPM) is under development for the Waste Isolation Pilot Plant (WIPP). The SPM is based on a large numerical integration problem that must be repeatedly evaluated to determine compliance probabilities associated with different experimental programs and design modifications. Due to the complexity and computational cost of the underlying integration problem, the implementation of the SPM must be planned very carefully. This presentation describes a preliminary application of the SPM, designated SPM-l, performed to provide insights to facilitate the development and implementation of the methodology. Topics illustrated by SPM-1 include definition of probability spaces on which the SPM is based, use of Latin hypercube sampling and simple random sampling to integrate over different probability spaces, selection of mechanistic calculations to be performed, efficient use of the limited number of mechanistic calculations that can be performed, and assembly of many individual calculations into a complete analysis.

  15. Scenario development for the Waste Isolation Pilot Plant: Building confidence in the assessment

    International Nuclear Information System (INIS)

    Scenario development is part of the iterative performance assessment (PA) process for the Waste Isolation Pilot Plant (WIPP). Scenario development for the WIPP has been the subject of intense external review and is certain to be the subject of continued scrutiny as the project proceeds toward regulatory compliance. The principal means of increasing confidence in this aspect of the PA will be through the use of the systematic and thorough procedure toward developing the scenarios and conceptual models on which the assessment is to be based. Early and ongoing interaction with project reviewers can assist with confidence building. Quality of argument and clarity of presentation in PA will be of key concern. Appropriate tools are required for documenting and tracking assumptions, through a single assessment phase, and between iterative assessment phases. Risks associated with future human actions are of particular concern to the WIPP project, and international consensus on the principles for incorporation of future human actions in assessments would be valuable

  16. Characterization of subjective uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    HELTON,JON CRAIG; MARTELL,MARY-ALENA; TIERNEY,MARTIN S.

    2000-05-18

    The 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) maintains a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, with stochastic uncertainty arising from the possible disruptions that could occur at the WIPP over the 10,000 yr regulatory period specified by the US Environmental Protection Agency (40 CFR 191,40 CFR 194) and subjective uncertainty arising from an inability to uniquely characterize many of the inputs required in the 1996 WIPP PA. The characterization of subjective uncertainty is discussed, including assignment of distributions, uncertain variables selected for inclusion in analysis, correlation control, sample size, statistical confidence on mean complementary cumulative distribution functions, generation of Latin hypercube samples, sensitivity analysis techniques, and scenarios involving stochastic and subjective uncertainty.

  17. Identification and evaluation of appropriate backfills for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    A backfill system has been designed for the Waste Isolation Pilot Plant (WIPP) which will control the chemical environment of the post-closure repository to a domain where the actinide solubility is within its lowest region. The actinide solubility is highly dependent on the chemical species which constitute the fluid, the resulting pH of the fluid, and the oxidation state of the actinide which is stable under the specific conditions. The use of magnesium oxide (MgO) has the backfill material not only controls the pH of the expected fluids, but also effectively removes carbonate from the system, which has a significant impact on actinide solubility. The backfill selection process, emplacement system design, and confirmatory experimental results are presented

  18. Ecological Monitoring Program at the Waste Isolation Pilot Plant: Second semiannual report, January 1985--June 1985

    International Nuclear Information System (INIS)

    This is the second semiannual report of the Ecological Monitoring Program (EMP) at the Waste Isolation Pilot Plant (WIPP) project in southeastern New Mexico. The purpose of the EMP is to quantify and assess the impacts of WIPP construction activities on the surrounding ecosystem. The predicted impacts include: (1) alteration of natural habitat, (2) deposition of salt and dust, and (3) increased human activity and noise. This report describes the data collection activities and presents results, analyses, and discussions for the period of January through June, 1985. Also included are data collected prior to this period which were not available for inclusion in the first EMP semiannual report and data collected after this period which provide a more complete basis for the analyses and discussion. The eight subprograms currently active in the EMP are: environmental photography, soil chemistry, soil microbiology, vegetation, wildlife, meteorology, air quality, and water quality. 16 refs., 37 figs., 17 tabs

  19. Geologic mapping of the air intake shaft at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Holt, R.M.; Powers, D.W. (IT Corporation (USA))

    1990-12-01

    The air intake shaft (AS) was geologically mapped from the surface to the Waste Isolation Pilot Plant (WIPP) facility horizon. The entire shaft section including the Mescalero Caliche, Gatuna Formation, Santa Rosa Formation, Dewey Lake Redbeds, Rustler Formation, and Salado Formation was geologically described. The air intake shaft (AS) at the Waste Isolation Pilot Plant (WIPP) site was constructed to provide a pathway for fresh air into the underground repository and maintain the desired pressure balances for proper underground ventilation. It was up-reamed to minimize construction-related damage to the wall rock. The upper portion of the shaft was lined with slip-formed concrete, while the lower part of the shaft, from approximately 903 ft below top of concrete at the surface, was unlined. As part of WIPP site characterization activities, the AS was geologically mapped. The shaft construction method, up-reaming, created a nearly ideal surface for geologic description. Small-scale textures usually best seen on slabbed core were easily distinguished on the shaft wall, while larger scale textures not generally revealed in core were well displayed. During the mapping, newly recognized textures were interpreted in order to refine depositional and post-depositional models of the units mapped. The objectives of the geologic mapping were to: (1) provide confirmation and documentation of strata overlying the WIPP facility horizon; (2) provide detailed information of the geologic conditions in strata critical to repository sealing and operations; (3) provide technical basis for field adjustments and modification of key and aquifer seal design, based upon the observed geology; (4) provide geological data for the selection of instrument borehole locations; (5) and characterize the geology at geomechanical instrument locations to assist in data interpretation. 40 refs., 27 figs., 1 tab.

  20. Geologic mapping of the air intake shaft at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The air intake shaft (AS) was geologically mapped from the surface to the Waste Isolation Pilot Plant (WIPP) facility horizon. The entire shaft section including the Mescalero Caliche, Gatuna Formation, Santa Rosa Formation, Dewey Lake Redbeds, Rustler Formation, and Salado Formation was geologically described. The air intake shaft (AS) at the Waste Isolation Pilot Plant (WIPP) site was constructed to provide a pathway for fresh air into the underground repository and maintain the desired pressure balances for proper underground ventilation. It was up-reamed to minimize construction-related damage to the wall rock. The upper portion of the shaft was lined with slip-formed concrete, while the lower part of the shaft, from approximately 903 ft below top of concrete at the surface, was unlined. As part of WIPP site characterization activities, the AS was geologically mapped. The shaft construction method, up-reaming, created a nearly ideal surface for geologic description. Small-scale textures usually best seen on slabbed core were easily distinguished on the shaft wall, while larger scale textures not generally revealed in core were well displayed. During the mapping, newly recognized textures were interpreted in order to refine depositional and post-depositional models of the units mapped. The objectives of the geologic mapping were to: (1) provide confirmation and documentation of strata overlying the WIPP facility horizon; (2) provide detailed information of the geologic conditions in strata critical to repository sealing and operations; (3) provide technical basis for field adjustments and modification of key and aquifer seal design, based upon the observed geology; (4) provide geological data for the selection of instrument borehole locations; (5) and characterize the geology at geomechanical instrument locations to assist in data interpretation. 40 refs., 27 figs., 1 tab

  1. Biosorption of Cadmium and Manganese Using Free Cells of Klebsiella sp. Isolated from Waste Water.

    Directory of Open Access Journals (Sweden)

    Yunnan Hou

    Full Text Available In the present study, we evaluated a bacterium that was isolated from waste water for its ability to take up cadmium and manganese. The strain, identified both biochemically and by its 16S rRNA gene sequence as Klebsiella, was named Yangling I2 and was found to be highly resistant to heavy metals. Surface characterization of the bacterium via SEM revealed gross morphological changes, with cells appearing as biconcave discs after metal exposure rather than their typical rod shape. The effects of pH, temperature, heavy metal concentration, agitation and biomass concentration on the uptake of Cd(II and Mn(II was measured using atomic absorption spectrophotometry. The results showed that the biosorption was most affected by pH and incubation temperature, being maximized at pH 5.0 and 30°C, with absorption capacities of 170.4 and 114.1 mg/g for Cd(II and Mn(II, respectively. Two models were investigated to compare the cells' capacity for the biosorption of Cd and Mn, and the Langmuir model based on fuzzy linear regression was found to be close to the observed absorption curves and yield binding constants of 0.98 and 0.86 for Cd and Mn, respectively. This strain of Klebsiella has approximately ten times the absorption capacity reported for other strains and is promising for the removal of heavy metals from waste water.

  2. Incorporating long-term climate change in performance assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Swift, P.N. [Sandia National Labs., Albuquerque, NM (United States); Baker, B.L. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States); Economy, K. [Ecodynamics Research Associates, Albuquerque, NM (United States); Garner, J.W. [Applied Physics, Inc., Albuquerque, NM (United States); Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Rudeen, D.K. [New Mexico Engineering Research Institute, Albuquerque, NM (United States)

    1994-03-01

    The United States Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico for the disposal of transuranic wastes generated by defense programs. Applicable regulations (40 CFR 191) require the DOE to evaluate disposal-system performance for 10,000 yr. Climatic changes may affect performance by altering groundwater flow. Paleoclimatic data from southeastern New Mexico and the surrounding area indicate that the wettest and coolest Quaternary climate at the site can be represented by that at the last glacial maximum, when mean annual precipitation was approximately twice that of the present. The hottest and driest climates have been similar to that of the present. The regularity of global glacial cycles during the late Pleistocene confirms that the climate of the last glacial maximum is suitable for use as a cooler and wetter bound for variability during the next 10,000 yr. Climate variability is incorporated into groundwater-flow modeling for WIPP PA by causing hydraulic head in a portion of the model-domain boundary to rise to the ground surface with hypothetical increases in precipitation during the next 10,000 yr. Variability in modeled disposal-system performance introduced by allowing had values to vary over this range is insignificant compared to variability resulting from other causes, including incomplete understanding of transport processes. Preliminary performance assessments suggest that climate variability will not affect regulatory compliance.

  3. Software quality assurance in the 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP), located in southeast New Mexico, is a deep geologic repository for the permanent disposal of transuranic waste generated by DOE defense-related activities. Sandia National Laboratories (SNL), in its role as scientific advisor to the DOE, is responsible for evaluating the long-term performance of the WIPP. This risk-based Performance Assessment (PA) is accomplished in part through the use of numerous scientific modeling codes, which rely for some of their inputs on data gathered during characterization of the site. The PA is subject to formal requirements set forth in federal regulations. In particular, the components of the calculation fall under the configuration management and software quality assurance aegis of the American Society of Mechanical Engineers(ASME) Nuclear Quality Assurance (NQA) requirements. This paper describes SNL's implementation of the NQA requirements regarding software quality assurance (SQA). The description of the implementation of SQA for a PA calculation addresses not only the interpretation of the NQA requirements, it also discusses roles, deliverables, and the resources necessary for effective implementation. Finally, examples are given which illustrate the effectiveness of SNL's SQA program, followed by a detailed discussion of lessons learned

  4. Historical Background on Assessment the Performance of the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P.

    1999-06-01

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the US Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a research and development facility for the safe management, storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and 25 years after site selection, the US Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance assessment conducted in 1996. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This report provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project. For example, the federal requirement to provide environmental impact statements and negotiated agreements with the State of New Mexico influenced the type of scientific areas that were investigated and the engineering analysis prior to 1989 for the WIPP.

  5. Scenario development for the Waste Isolation Pilot Plant compliance certification application

    Energy Technology Data Exchange (ETDEWEB)

    GALSON,D.A.; SWIFT,PETER N.; ANDERSON,D. RICHARD; BENNETT,D.G.

    1998-09-23

    Demonstrating compliance with the applicable regulations for the Waste Isolation Pilot Plant (WIPP) requires an assessment of the long-term performance of the disposal system. Scenario development is one starting point of this assessment, and generates inquiry about the present state and future evolution of the disposal system. Scenario development consists of four tasks: (1) identifying and classifying features, events and processes (FEPs), (2) screening FEPs according to well-defined criteria, (3) forming scenarios (combinations of FEPs) in the context of regulatory performance criteria and (4) specifying of scenarios for consequence analysis. The development and screening of a comprehensive FEP list provides assurance that the identification of significant processes and events is complete, that potential interactions between FEPs are not overlooked, and that responses to possible questions are available and well documented. Two basic scenarios have been identified for the WIPP: undisturbed performance (UP) and disturbed performance (DP). The UP scenario is used to evaluate compliance with the Environmental Protection Agency's (EPA's) Individual Dose (40 CFR Section 191-15) and Groundwater Protection (40 CFR Section 191-24) standards and accounts for all natural-, waste- and repository-induced FEPs that survive the screening process. The DP scenario is required for assessment calculations for the EPA's cumulative release standard (Containment Requirements, 40 CFR Section 191-13) and accounts for disruptive future human events, which have an uncertain probability of occurrence, in addition to the UP FEPs.

  6. Scenario development for the Waste Isolation Pilot Plant Compliance Certification Application

    Energy Technology Data Exchange (ETDEWEB)

    Galson, D.A.; Swift, P.N.; Anderson, D.R.; Bennett, D.G.; Crawford, M.B.; Hicks, T.W.; Wilmot, R.D.; Basabilvazo, G

    2000-09-01

    Demonstrating compliance with the applicable regulations for the Waste Isolation Pilot Plant (WIPP) requires an assessment of the long-term performance of the disposal system. Scenario development is one starting point of this assessment, and generates inquiry about the present state and future evolution of the disposal system. Scenario development consists of four tasks: (i) identifying and classifying features, events and processes (FEPs); (ii) screening FEPs according to well-defined criteria; (iii) forming scenarios (combinations of FEPs) in the context of regulatory performance criteria, and (iv) specifying of scenarios for consequence analysis. The development and screening of a comprehensive FEP list provides assurance that the identification of significant processes and events is complete, that potential interactions between FEPs are not overlooked, and that responses to possible questions are available and well documented. Two basic scenarios have been identified for the WIPP: undisturbed performance (UP) and disturbed performance (DP). The UP scenario is used to evaluate compliance with the Environmental Protection Agency's (EPA's) Individual Dose (40 CFR section 191.15) and Groundwater Protection (40 CFR section 191.24) standards and accounts for all natural and waste- and repository-induced FEPs that survive the screening process. The DP scenario is required for assessment calculations for the EPA's cumulative release standard (Containment Requirements, 40 CFR section 191.13) and accounts for disruptive future human events, which have an uncertain probability of occurrence, in addition to the UP FEPs.

  7. Scenario development for the waste isolation pilot plant compliance certification application

    International Nuclear Information System (INIS)

    Demonstrating compliance with the applicable regulations for the Waste Isolation Pilot Plant (WIPP) requires an assessment of the long-term performance of the disposal system. Scenario development is one starting point of this assessment, and generates inquiry about the present state and future evolution of the disposal system. Scenario development consists of four tasks: (i) identifying and classifying features, events and processes (FEPs), (ii) screening FEPs according to well-defined criteria, (iii) forming scenarios (combinations of FEPs) in the context of regulatory performance criteria, and (iv) specifying of scenarios for consequence analysis. The development and screening of a comprehensive FEP list provides assurance that the identification of significant processes and events is complete, that potential interactions between FEPs are not overlooked, and that responses to possible questions are available and well documented. Two basic scenarios have been identified for the WIPP: undisturbed performance (UP) and disturbed performance (DP). The UP scenario is used to evaluate compliance with the Environmental Protection Agency's (EPA's) Individual Dose (40 CFR - 191.15) and Groundwater Protection (40 CFR - 191.24) standards and accounts for all natural and waste- and repository-induced FEPs that survive the screening process. The DP scenario is required for assessment calculations for the EPA's cumulative release standard (Containment Requirements, 40 CFR - 191.13) and accounts for disruptive future human events, which have an uncertain probability of occurrence, in addition to the UP FEPs. (authors)

  8. Scenario development for the Waste Isolation Pilot Plant Compliance Certification Application

    International Nuclear Information System (INIS)

    Demonstrating compliance with the applicable regulations for the Waste Isolation Pilot Plant (WIPP) requires an assessment of the long-term performance of the disposal system. Scenario development is one starting point of this assessment, and generates inquiry about the present state and future evolution of the disposal system. Scenario development consists of four tasks: (i) identifying and classifying features, events and processes (FEPs); (ii) screening FEPs according to well-defined criteria; (iii) forming scenarios (combinations of FEPs) in the context of regulatory performance criteria, and (iv) specifying of scenarios for consequence analysis. The development and screening of a comprehensive FEP list provides assurance that the identification of significant processes and events is complete, that potential interactions between FEPs are not overlooked, and that responses to possible questions are available and well documented. Two basic scenarios have been identified for the WIPP: undisturbed performance (UP) and disturbed performance (DP). The UP scenario is used to evaluate compliance with the Environmental Protection Agency's (EPA's) Individual Dose (40 CFR section 191.15) and Groundwater Protection (40 CFR section 191.24) standards and accounts for all natural and waste- and repository-induced FEPs that survive the screening process. The DP scenario is required for assessment calculations for the EPA's cumulative release standard (Containment Requirements, 40 CFR section 191.13) and accounts for disruptive future human events, which have an uncertain probability of occurrence, in addition to the UP FEPs

  9. Scenario development for the Waste Isolation Pilot Plant compliance certification application

    International Nuclear Information System (INIS)

    Demonstrating compliance with the applicable regulations for the Waste Isolation Pilot Plant (WIPP) requires an assessment of the long-term performance of the disposal system. Scenario development is one starting point of this assessment, and generates inquiry about the present state and future evolution of the disposal system. Scenario development consists of four tasks: (1) identifying and classifying features, events and processes (FEPs), (2) screening FEPs according to well-defined criteria, (3) forming scenarios (combinations of FEPs) in the context of regulatory performance criteria and (4) specifying of scenarios for consequence analysis. The development and screening of a comprehensive FEP list provides assurance that the identification of significant processes and events is complete, that potential interactions between FEPs are not overlooked, and that responses to possible questions are available and well documented. Two basic scenarios have been identified for the WIPP: undisturbed performance (UP) and disturbed performance (DP). The UP scenario is used to evaluate compliance with the Environmental Protection Agency's (EPA's) Individual Dose (40 CFR Section 191-15) and Groundwater Protection (40 CFR Section 191-24) standards and accounts for all natural-, waste- and repository-induced FEPs that survive the screening process. The DP scenario is required for assessment calculations for the EPA's cumulative release standard (Containment Requirements, 40 CFR Section 191-13) and accounts for disruptive future human events, which have an uncertain probability of occurrence, in addition to the UP FEPs

  10. Incorporating long-term climate change in performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The United States Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico for the disposal of transuranic wastes generated by defense programs. Applicable regulations (40 CFR 191) require the DOE to evaluate disposal-system performance for 10,000 yr. Climatic changes may affect performance by altering groundwater flow. Paleoclimatic data from southeastern New Mexico and the surrounding area indicate that the wettest and coolest Quaternary climate at the site can be represented by that at the last glacial maximum, when mean annual precipitation was approximately twice that of the present. The hottest and driest climates have been similar to that of the present. The regularity of global glacial cycles during the late Pleistocene confirms that the climate of the last glacial maximum is suitable for use as a cooler and wetter bound for variability during the next 10,000 yr. Climate variability is incorporated into groundwater-flow modeling for WIPP PA by causing hydraulic head in a portion of the model-domain boundary to rise to the ground surface with hypothetical increases in precipitation during the next 10,000 yr. Variability in modeled disposal-system performance introduced by allowing head values to vary over this range is insignificant compared to variability resulting from other causes, including incomplete understanding of transport processes. Preliminary performance assessments suggest that climate variability will not affect regulatory compliance

  11. Incorporating long-term climate change in performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The United States Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico for the disposal of transuranic wastes generated by defense programs. Applicable regulations (40 CFR 191) require the DOE to evaluate disposal-system performance for 10,000 yr. Climatic changes may affect performance by altering groundwater flow. Paleoclimatic data from southeastern New Mexico and the surrounding area indicate that the wettest and coolest Quaternary climate at the site can be represented by that at the last glacial maximum, when mean annual precipitation was approximately twice that of the present. The hottest and driest climates have been similar to that of the present. The regularity of global glacial cycles during the late Pleistocene confirms that the climate of the last glacial maximum is suitable for use as a cooler and wetter bound for variability during the next 10,000 yr. Climate variability is incorporated into groundwater-flow modeling for WIPP PA by causing hydraulic head in a portion of the model-domain boundary to rise to the ground surface with hypothetical increases in precipitation during the next 10,000 yr. Variability in modeled disposal-system performance introduced by allowing had values to vary over this range is insignificant compared to variability resulting from other causes, including incomplete understanding of transport processes. Preliminary performance assessments suggest that climate variability will not affect regulatory compliance

  12. Historical Background on Assessingt the Performance of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the US Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a research and development facility for the safe management, storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and 25 years after site selection, the US Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance assessment conducted in 1996. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This report provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project. For example, the federal requirement to provide environmental impact statements and negotiated agreements with the State of New Mexico influenced the type of scientific areas that were investigated and the engineering analysis prior to 1989 for the WIPP

  13. Waste Isolation Pilot Plant annual site environmental report for calendar year 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) defined a comprehensive set of parameters which are monitored to detect potential environmental impacts and establish baselines for future environmental evaluations. Surface water and groundwater, air, soil, and biotics are monitored for radioactivity levels. Nonradiological environmental monitoring activities include air, water quality, soil properties, meteorological measurements and determination of the status of the local biological community. Ecological studies focus on the immediate area surrounding the WIPP site with emphasis on the salt storage pile. The baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in its preoperational phase (i.e., no waste has been received) certain operational requirements of DOE Orders 5400.1, 5400.5, and the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T) are not relevant. Therefore, this report does not discuss items such as radionuclide emissions and effluents and subsequent doses to the public.

  14. Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

    International Nuclear Information System (INIS)

    Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, non-radioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a post-flame location in the combustor. Cesium readily vaporizes in the high temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, and so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high temperature waste processing including incineration and vitrification

  15. Blending mining and nuclear industries at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    At the Waste Isolation Pilot Plant (WIPP) traditional procedures for underground mining activities have been significantly altered in order to assure underground safety and project adherence to numerous regulatory requirements. Innovative techniques have been developed for WIPP underground procedures, mining equipment, and operating environments. The mining emphasis at WIPP is upon the quality of the excavation, not (as in conventional mines) on the production of ore. The WIPP is a United States Department of Energy (DOE) project that is located 30 miles southeast of Carlsbad, New Mexico, where the nation's first underground engineered nuclear repository is being constructed. The WIPP site was selected because of its location amidst a 607 meter thick salt bed, which provides a remarkably stable rock formation for the permanent storage of nuclear waste. The underground facility is located 655 meters below the earth's surface, in the Salado formation, which comprises two-hundred million year old halites with minor amounts of clay and anhydrites. When completed, the WIPP underground facility will consist of two components: approximately 81 square kilometers of experimental areas, and approximately 405 square kilometers of repository. 3 figs

  16. Characterization of stochastic uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) maintains a separation between stochastic (i.e. aleatory) and subjective (i.e. epistemic) uncertainty, with stochastic uncertainty arising from the possible disruptions that could occur at the WIPP over the 10,000-yr regulatory period specified by the US Environmental Protection Agency (40 CFR 191, 40 CFR 194) and subjective uncertainty arising from an inability to uniquely characterize many of the inputs required in the 1996 WIPP PA. The characterization of stochastic uncertainty is discussed, including drilling intrusion time, drilling location, penetration of excavated/nonexcavated areas of the repository, penetration of pressurized brine beneath the repository, borehole plugging patterns, activity level of waste, and occurrence of potash mining. Additional topics discussed include sampling procedures, generation of individual 10,000-yr futures for the WIPP, construction of complementary cumulative distribution functions (CCDFs), mechanistic calculations carried out to support CCDF construction, the Kaplan/Garrick ordered triple representation for risk, and determination of scenarios and scenario probabilities

  17. Hydrogen generation by metal corrosion in simulated Waste Isolation Pilot Plant environments

    International Nuclear Information System (INIS)

    The corrosion and gas-generation characteristics of three material types: low-carbon steel (the current waste packaging material for the Waste Isolation Pilot Plant), Cu-base materials, and Ti-base materials were determined in both the liquid and vapor phase of Brine A, a brine representative of an intergranular Salado Formation brine. Test environments included anoxic brine and anoxic brine with overpressures of CO2, H2S, and H2. Low-carbon steel reacted at a slow, measurable rate with anoxic brine, liberating H2 on an equimolar basis with Fe reacted. Presence of CO2 caused the initial reaction to proceed more rapidly, but CO2-induced passivation stopped the reaction if the CO2 were present in sufficient quantities. Low-carbon steel immersed in brine with H2S showed no reaction, apparently because of passivation of the steel by formation of a protective iron sulfide reaction product. Cu- and Ti-base materials showed essentially no corrosion when exposed to brine and overpressures of N2, CO2, and H2S except for the rapid and complete reaction between Cu-base materials and H2S. No significant reaction took place on any material in any environment in the vapor-phase exposures

  18. Waste Isolation Pilot Plant: Site environmental report for calendar year 1991

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental Impacts and establish baselines for future quantitative environmental Impact evaluations. Surface water and groundwater, air, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include air quality, water quality, soil properties, meteorological, and the status of the local biological community. Ecological studies focus on the immediate area surrounding the site with emphasis on the salt storage pile, whereas baseline radiological surveillance covers a broader geographic area Including nearby ranches, villages, and cities. Since the WIPP is still in a preoperational state, and no waste has been received; certain elements required by DOE Order 5400.1 are not presented In this report. The most significant addition to the 1991 report is the inclusion of the first four appendices, the Radiological Baseline Program (DOE/WIPP 92-037), the Salt Impact Studies (DOE/WIPP 92-038), the Disturbed Land Reclamation Techniques (DOE/WIPP 92-039), and the Background Water Characterization for the WIPP (DOE/WIPP 92-013). These appendices are independently published and available to interested parties by the DOE reference number. These summaries will not be published in future ASER'S. They will, however, be referenced as a basis for evaluating similar data collected during the Test and subsequent Operational phases of the WIPP

  19. Computational implementation of a systems prioritization methodology for the Waste Isolation Pilot Plant: A preliminary example

    International Nuclear Information System (INIS)

    A systems prioritization methodology (SPM) is under development to provide guidance to the US DOE on experimental programs and design modifications to be supported in the development of a successful licensing application for the Waste Isolation Pilot Plant (WIPP) for the geologic disposal of transuranic (TRU) waste. The purpose of the SPM is to determine the probabilities that the implementation of different combinations of experimental programs and design modifications, referred to as activity sets, will lead to compliance. Appropriate tradeoffs between compliance probability, implementation cost and implementation time can then be made in the selection of the activity set to be supported in the development of a licensing application. Descriptions are given for the conceptual structure of the SPM and the manner in which this structure determines the computational implementation of an example SPM application. Due to the sophisticated structure of the SPM and the computational demands of many of its components, the overall computational structure must be organized carefully to provide the compliance probabilities for the large number of activity sets under consideration at an acceptable computational cost. Conceptually, the determination of each compliance probability is equivalent to a large numerical integration problem. 96 refs., 31 figs., 36 tabs

  20. Uncertainty analysis in the 1996 performance assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Anderson, D.R.; Jow, H.N.; Marietta, M.G. [Sandia National Labs., Albuquerque, NM (United States); Basabilvazo, G. [Dept. of Energy, Carlsbad, NM (United States)

    1998-07-01

    The appropriate treatment of uncertainty is now widely recognized as an essential component of performance assessments (PAs) for complex systems. When viewed at a high-level, the uncertainty in such analyses can typically be partitioned into two types: (1) stochastic uncertainty, which arises because the system can behave in many different ways and is thus a property of the system itself, and (2) subjective uncertainty, which arises from a lack of knowledge about quantities that are believed to have (or, at least, are assumed to have) fixed values and is thus a property of the analysts carrying out the study. The 1996 PA for the Waste Isolation Pilot Plant (WIPP) carried out at Sandia National Laboratories (SNL) will be used to illustrate the treatment of these two types of uncertainty in a real analysis. In particular, this PA supported a compliance certification application (CCA) by the US Department of Energy (DOE) to the US Environmental Protection Agency (EPA) for the certification of the WIPP for the geologic disposal of transuranic waste. Insights on the conceptual and computational structure of PAs for complex systems gained from these and other analyses are being incorporated into a new software system under development at SNL to facilitate the performance of analyses that maintain a separation between stochastic and subjective uncertainty.

  1. Computational implementation of a systems prioritization methodology for the Waste Isolation Pilot Plant: A preliminary example

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C. [Arizona State Univ., Tempe, AZ (United States). Dept. of Mathematics; Anderson, D.R. [Sandia National Labs., Albuquerque, NM (United States). WIPP Performance Assessments Departments; Baker, B.L. [Technadyne Engineering Consultants, Albuquerque, NM (United States)] [and others

    1996-04-01

    A systems prioritization methodology (SPM) is under development to provide guidance to the US DOE on experimental programs and design modifications to be supported in the development of a successful licensing application for the Waste Isolation Pilot Plant (WIPP) for the geologic disposal of transuranic (TRU) waste. The purpose of the SPM is to determine the probabilities that the implementation of different combinations of experimental programs and design modifications, referred to as activity sets, will lead to compliance. Appropriate tradeoffs between compliance probability, implementation cost and implementation time can then be made in the selection of the activity set to be supported in the development of a licensing application. Descriptions are given for the conceptual structure of the SPM and the manner in which this structure determines the computational implementation of an example SPM application. Due to the sophisticated structure of the SPM and the computational demands of many of its components, the overall computational structure must be organized carefully to provide the compliance probabilities for the large number of activity sets under consideration at an acceptable computational cost. Conceptually, the determination of each compliance probability is equivalent to a large numerical integration problem. 96 refs., 31 figs., 36 tabs.

  2. Characterization of stochastic uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    HELTON,JON CRAIG; DAVIS,FREDDIE J.; JOHNSON,J.D.

    2000-05-19

    The 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) maintains a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, with stochastic uncertainty arising from the possible disruptions that could occur at the WIPP over the 10,000 yr regulatory period specified by the US Environmental Protection Agency (40 CFR 191, 40 CFR 194) and subjective uncertainty arising from an inability to uniquely characterize many of the inputs required in the 1996 WIPP PA. The characterization of stochastic uncertainty is discussed including drilling intrusion time, drilling location penetration of excavated/nonexcavated areas of the repository, penetration of pressurized brine beneath the repository, borehole plugging patterns, activity level of waste, and occurrence of potash mining. Additional topics discussed include sampling procedures, generation of individual 10,000 yr futures for the WIPP, construction of complementary cumulative distribution functions (CCDFs), mechanistic calculations carried out to support CCDF construction the Kaplan/Garrick ordered triple representation for risk and determination of scenarios and scenario probabilities.

  3. Certification of VOC canister samplers for use at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) site is designed to demonstrate safe disposal of transuranic (TRU) mixed waste. An air monitoring program has been established at the WIPP site to verify that volatile organic compounds (VOCs) do not migrate out of the disposal unit. In this air monitoring program, modified commercially available dual canister samplers are used to collect air samples for VOC analysis. Sampler certification, sample collection, and sample analysis are performed based on the procedures contained in US Environmental Protection Agency's Compendium Method TO-14. The canister samplers are certified for cleanliness by passing humid zero air through the entire sampling system and collecting a sample in a canister over a 24-hour period. In addition, each canister sampler is certified for target compound recovery efficiency by passing a humid calibration gas standard through the entire sampling system and collecting a sample in a canister over a 24-hour period. In this paper, the authors discuss the techniques developed for meeting the stringent certification requirements of the monitoring program and present data to support the need for these stringent requirements

  4. Waste Isolation Pilot Plant annual site environmental report for calendar year 1992

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) defined a comprehensive set of parameters which are monitored to detect potential environmental impacts and establish baselines for future environmental evaluations. Surface water and groundwater, air, soil, and biotics are monitored for radioactivity levels. Nonradiological environmental monitoring activities include air, water quality, soil properties, meteorological measurements and determination of the status of the local biological community. Ecological studies focus on the immediate area surrounding the WIPP site with emphasis on the salt storage pile. The baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in its preoperational phase (i.e., no waste has been received) certain operational requirements of DOE Orders 5400.1, 5400.5, and the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T) are not relevant. Therefore, this report does not discuss items such as radionuclide emissions and effluents and subsequent doses to the public

  5. Geochemical overview of the Waste Isolation Pilot Plant near Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant is a US Department-of-Energy-sponsored repository for the long-term storage of transuranic defense-related nuclear waste, located in the Delaware Basin near Carlsbad, New Mexico. During excavation, numerous large fluid inclusions were collected from highly recrystallized halite at the repository horizon. The inclusion fluid compositions define two distinct populations, based on analyses for Ca, Mg, K, Na, Cl, Br, and SO/sub 4/. Chemical and mineralogical evidence supports our conclusions that the fluid inclusion compositions arise from early diagenetic changes involving alteration of calcium sulfate (gypsum or anhydrite) to polyhalite, and calcium carbonate (calcite or aragonite) to magnesite. Other brines occurring in the repository (as ''weeps'' oozing from the walls or collecting in drill holes in the floor) were also analyzed. These fluids were found to differ significantly from the fluid inclusions mainly by depletion of magnesium relative to potassium. The stratigraphic association of these fluids with argillaceous and anhydritic halite suggests an origin in evaporating seawater that was subsequently modified by dewatering of clays and/or gypsum, and selective uptake of magnesium relative to potassium during clay diagenesis. This interpretation is compatible with observations of a suite of authigenic minerals that includes quartz, magnesite, and magnesium silicates

  6. The underground main fan study at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) performed a feasibility analysis for the purpose of either modifying, supplementing, or replacing its two main mine fans. The WIPP, located near Carlsbad, New Mexico, is a US Department of Energy (DOE) facility designed to demonstrate the permanent, safe disposal of US defense-generated transuranic waste in a deep bedded salt deposit. Since the centrifugal fans were installed in 1988, multiple operational and performance concerns have been identified. A comprehensive engineering study was conducted in 1995 to: (1) qualify and quantify operational concerns; (2) evaluate possible alternatives; and (3) recommend an optimum solution. Multiple system modification and/or replacement scenarios were evaluated with associated cost estimates developed. The study considered replacement with either centrifugal or axial fans. Multiple fan duties are required at the WIPP. Therefore, Variable Frequency Drives and Inlet Vane Controls (IVC) were investigated for centrifugal fans. In-flight adjustable blades were investigated for axial fans. The study indicated that replacing the existing system with two double-width, double-inlet centrifugal fans equipped with IVCs was the best choice. This alternative provided the most desirable combination of: (1) ensuring the required operational readiness, and (2) improving system performance. The WIPP is currently planning to replace the first fan in 1997

  7. Audit of selected aspects of the Waste Isolation Pilot Plant cost structure, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    The Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, is a research and development facility intended to demonstrate that transuranic waste from the Government's defense activities can be safely disposed of in a deep geologic formation. The Fiscal Year 1994 budget for WIPP is about $185 million and includes funding for the operation of WIPP and for experiments being done by other DOE facilities. DOE's current plan is for WIPP to begin receiving transuranic waste in June 1998. This audit was requested by the Assistant Secretary for Environmental Management because two recent reports, one issues by the Office of Inspector General (OIG), were critical of the staffing and cost-effectiveness of WIPP, and because of recent mission changes at WIPP. The audit team consisted of representatives from the DOE, auditors from the OIG, and technical specialists hired by the OIG to assist in the audit. The purpose of the audit was to determine whether WIPP was appropriately staffed to meet programmatic requirements in the most cost-effective manner. The Secretary of Energy expected DOE facilities to benchmark their performance against other facilities to strive for best in class status, and the Westinghouse management and operating contract for WIPP required the facility to be operated in a cost-effective manner. However, the authors determined that Westinghouse did not use benchmarks and that WIPP could be managed more cost-effectively, with fewer personnel, while maintaining its current level of excellence. They concluded that the WIPP staffing level could be significantly reduced with a decrease in costs at WIPP of about $11.4 million per year

  8. Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA for re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)

  9. Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hoover, M.D.; Farrell, R.F. [DOE, Carlsbad, NM (United States); Newton, G.J.

    1995-12-01

    The recent 1995 WIPP Safety Analysis Report (SAR) Update provided detailed analyses of potential radiation doses to members of the public at the site boundary during postulated accident scenarios at the U.S. Department of Energy`s Waste Isolation Pilot Plant (WIPP). The SAR Update addressed the complete spectrum of potential accidents associated with handling and emplacing transuranic waste at WIPP, including damage to waste drums from fires, punctures, drops, and other disruptions. The report focused on the adequacy of the multiple layers of safety practice ({open_quotes}defense-in-depth{close_quotes}) at WIPP, which are designed to (1) reduce the likelihood of accidents and (2) limit the consequences of those accidents. The safeguards which contribute to defense-in-depth at WIPP include a substantial array of inherent design features, engineered controls, and administrative procedures. The SAR Update confirmed that the defense-in-depth at WIPP is adequate to assure the protection of the public and environment. As a supplement to the 1995 SAR Update, we have conducted additional analyses to confirm that these controls will also provide adequate protection to workers at the WIPP. The approaches and results of the worker dose assessment are summarized here. In conformance with the guidance of DOE Standard 3009-94, we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposures under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR Update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, members of the public, and the environment.

  10. Perspective of waste isolation research issues and assessment of consequences for radionuclide release

    International Nuclear Information System (INIS)

    The finiteness of research resources to address technical issues for nuclear waste management requires a realistic assessment of their importance. The most appropriate method for making this assessment is the combination of system studies, which include consideration of the role of all protective barrier, and consequence assessment models that can estimate the potential hazard imposed upon man for assumed violations of these barriers. Sensitivity analyses on certain issues can then be performed to determine the impact of various descriptive parameters. Work commensurate with this strategy has been initiated at Sandia. Some conclusions drawn from these studies specifically applicable to WIPP for the scenarios considered are that: Waste form and protective canisters are not essential as barriers. Assumed radionuclide dissolutioning is far in excess of that possible with developmental waste forms. Brine migration plays no significant role in long-term isolation; complications to retrievability can be avoided with numerous technical alternaives. Radionuclide sorption in geomedia near repositories plays an important role in reducing consequences, but sites with favorable geologic and hydrologic settings such as WIPP can tolerate essentially no reliance on sorption and still achieve inconsequential predicted doses. Plutonium sorption with K/sub d/ greater than 10 are sufficient to eliminate direct doses from plutonium. Borehole plugs are not required for primary protection. Continued scientific resolution of both real and perceived issues can, however, provide additional assurance and public confidence that consequences can be reduced beyond those predicted in bounding scenarios. In addition, such investigation will assure that appropriate limits are instituted for defining parameters and that all assumptions in predictive models are technically sound

  11. Report on the emergency response training and equipment activities through fiscal year 1992 for the transportation of transuranic waste to the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility with the mission of demonstrating the safe shipment, emplacement, and retrieval of radioactive transuranic (TRU) wastes resulting from the defense activities and programs of the United States. It is the only long-term storage facility constructed for TRU waste. This report provides the status on the Department of Energy (DOE) efforts as of September 30, 1992, regarding emergency response training provided to local, state, and tribal governments for waste shipments to the WIPP, as required by section 16(c)(1)(A) of the Waste Isolation Pilot Plant Land Withdrawal Act (Public Law 102-579). This is an update to the April 1992 report (DOE/WIPP 92003) which provided status through 1991. This report will be updated and issued annually. Because of a growing public awareness of transportation-activities involving nuclear materials, this report was prepared to provide a status of the DOE's activities in this regard, as well as the cooperative efforts between the DOE and state and tribal governments

  12. Flotation isolation of uranium(6) from acidic waste waters with the use of potassium soaps of dialkylphosphinic acids

    International Nuclear Information System (INIS)

    The applicability of potassium soaps of dialkylphosphinic acids of R2POOH type where R is C3-C10 hydrocarbon radical as uranium flotation collectors is investigated. Under similar conditions the degree of uranium flotation isolation from nitrate solutions is notably higher than from chloride solutions, and from the latter is higher than from sulfate solutions. The method of uranium flotation isolation using dialkylphosphinic acid soaps was tested in synthetic solutions simulating acid (pH = 2-5) waste waters. Possibility of flotation method to isolate 95-99% of uranium from acid solutions using potassium soaps of dialkylphosphinic acids is demonstrated

  13. Geochemistry of Salado Formation brines recovered from the Waste Isolation Pilot Plant (WIPP) repository

    International Nuclear Information System (INIS)

    Intergranular brines recovered from the repository horizon of the Waste Isolation Pilot Plant (WIPP) have major- and trace-element compositions that reflect seawater evaporation and diagenetic processes. Brines obtained from repository drill holes are heterogenous with respect to composition, but their compositional fields are distinct from those obtained from fluid inclusions in WIPP halite. The heterogeneity of brine compositions within the drill-hole population indicates a lack of mixing and fluid homogenization within the salt at the repository level. Compositional differences between intergranular (drill hole) and intragranular (fluid inclusions) brines is attributed to isolation of the latter from diagenetic fluids that were produced from dehydration reactions involving gypsum and clay minerals. Modeling of brine-rock equilibria indicates that equilibration with evaporite minerals controls the concentrations of major elements in the brine. Drill-hole brines are in equilibrium with the observed repository minerals halite, anhydrite, magnesite, polyhalite and quartz. The equilibrium model supports the derivation of drill-hole brines from near-field fluid, rather than large-scale vertical migration of fluids from the overlying Rustler or underlying Castile Formations. 13 refs., 6 figs., 6 tabs

  14. Thermoanaerobacter pentosaceus sp. nov., an anaerobic, extreme thermophilic, high ethanol-yielding bacterium isolated from household waste

    DEFF Research Database (Denmark)

    Tomás, Ana Faria; Karakashev, Dimitar Borisov; Angelidaki, Irini

    2013-01-01

    An extremely thermophilic, xylanolytic, spore-forming and strict anaerobic bacterium DTU01(T) was isolated from a continuously stirred tank reactor fed with xylose and household waste. Cells stained Gram-negative and were rod-shaped (0.5-2 µm in length). Spores were terminal with a diameter...

  15. Draft Genome Sequence of a Tetrabromobisphenol A–Degrading Strain, Ochrobactrum sp. T, Isolated from an Electronic Waste Recycling Site

    Science.gov (United States)

    Liang, Zhishu; Li, Guiying; Zhang, Guoxia; Das, Ranjit

    2016-01-01

    Ochrobactrum sp. T was previously isolated from a sludge sample collected from an electronic waste recycling site and characterized as a unique tetrabromobisphenol A (TBBPA)–degrading bacterium. Here, the draft genome sequence (3.9 Mb) of Ochrobactrum sp. T is reported to provide insights into its diversity and its TBBPA biodegradation mechanism in polluted environments. PMID:27445374

  16. Existing conditions socioeconomic portion. Waste isolation pilot plant environmental impact report, chapter 2, sections 2.2, 2.3

    International Nuclear Information System (INIS)

    The population characteristics and the economic setting of Eddy and Lea Counties, New Mexico, are reviewed as related to site selection for a radioactive waste isolation pilot plant. Sections are included on population distribution, basic industries, trade and services, financial resources, personal income, tourism, labor force, employment, land use, water systems, utilities, transportation, and local government

  17. Preliminary Systems Design Study assessment report. Volume 6, Waste Isolation Pilot Plant and transportation package acceptable concepts

    Energy Technology Data Exchange (ETDEWEB)

    Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

    1992-01-01

    The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques for the remediation of hazardous and transuranic waste stored at Radioactive Waste Management Complex`s Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept. This volume contains introduction section containing a brief SDS background and lists the general assumptions and considerations used during the development of the system concepts. The introduction section is followed by sections describing two system concepts that produce a waste form in compliance with the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) and transportation package (TRAMPAC) requirements. This system concept category is referred to as Waste Form 4, ``WIPP and TRAMPAC Acceptable.`` The following two system concepts are under this category: Sort, Treat, and Repackage System (4-BE-2); Volume Reduction and Packaging System (4-BE-4).

  18. Effects of waste drilling fluid on bacterial isolates from a mangrove swamp oilfield location in the Niger delta of Nigeria

    International Nuclear Information System (INIS)

    Four bacteria strains isolated from a mangrove swamp oilfield location in the Niger Delta of Nigeria were cultured aerobically in the presence of 1.0% waste drilling fluid, to determine the effect of the waste on their growth. A 2-h lag phase of growth was produced by the waste in cultures of Micrococcus and Pseudomonas species, while the waste increased the lag phases of Alcaligenes and Staphylococcus species to 4 h. The exponential phase of growth of Pseudomonas sp. was depressed by the waste drilling fluid but fluid stimulated the exponential phases of Micrococcus and Alcaligenes spp. There was enhancement of the growth rate of Alcaligenes and Micrococcus spp. while those of Staphylococcus and Pseudonomas spp. were decreased. The depressed growth rates of Staphylococcus and Pseudonomas spp. in the presence of the waste drilling fluid might lead to a decrease in their contribution to the removal of the waste from the environment during spillage or disposal and, therefore, may result in an accumulation of the waste in the environment. (author)

  19. Isolation of bacterial cellulose nanocrystalline from pineapple peel waste: Optimization of acid concentration in the hydrolysis method

    Science.gov (United States)

    Anwar, Budiman; Rosyid, Nurul Huda; Effendi, Devi Bentia; Nandiyanto, Asep Bayu Dani; Mudzakir, Ahmad; Hidayat, Topik

    2016-02-01

    Isolation of needle-shaped bacterial cellulose nanocrystalline with a diameter of 16-64 nm, a fiber length of 258-806 nm, and a degree of crystallinity of 64% from pineapple peel waste using an acid hydrolysis process was investigated. Experimental showed that selective concentration of acid played important roles in isolating the bacterial cellulose nanocrystalline from the cellulose source. To achieve the successful isolation of bacterial cellulose nanocrystalline, various acid concentrations were tested. To confirm the effect of acid concentration on the successful isolation process, the reaction conditions were fixed at a temperature of 50°C, a hydrolysis time of 30 minutes, and a bacterial cellulose-to-acid ratio of 1:50. Pineapple peel waste was used as a model for a cellulose source because to the best of our knowledge, there is no report on the use of this raw material for producing bacterial cellulose nanocrystalline. In fact, this material can be used as an alternative for ecofriendly and cost-free cellulose sources. Therefore, understanding in how to isolate bacterial cellulose nanocrystalline from pineapple peel waste has the potential for large-scale production of inexpensive cellulose nanocrystalline.

  20. Draft forecast of the final report for the comparison to 40 CFR Part 191, Subpart B, for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Bertram-Howery, S.G.; Marietta, M.G.; Anderson, D.R.; Gomez, L.S.; Rechard, R.P. (Sandia National Labs., Albuquerque, NM (USA)); Brinster, K.F.; Guzowski, R.V. (Science Applications International Corp., Albuquerque, NM (USA))

    1989-12-01

    The United States Department of Energy is planning to dispose of transuranic wastes, which have been generated by defense programs, at the Waste Isolation Pilot Plant. The WIPP Project will assess compliance with the requirements of the United States Environmental Protection Agency. This report forecasts the planned 1992 document, Comparison to 40 CFR, Part 191, Subpart B, for the Waste Isolation Pilot Plant (WIPP). 130 refs., 36 figs., 11 tabs.