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Sample records for wipp epa ensures

  1. Evaluation of the WIPP Project`s compliance with the EPA radiation protection standards for disposal of transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M. [Environmental Evaluation Group, Albuquerque, NM (United States)]|[Environmental Evaluation Group, Carlsbad, NM (United States)

    1998-03-01

    The US Environmental Protection Agency`s (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP`s compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy`s (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA`s proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA`s responses to EEG`s comments.

  2. Evaluation of the WIPP Project's compliance with the EPA radiation protection standards for disposal of transuranic waste

    International Nuclear Information System (INIS)

    Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M.

    1998-03-01

    The US Environmental Protection Agency's (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP's compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy's (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA's proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA's responses to EEG's comments

  3. Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards

    International Nuclear Information System (INIS)

    Neill, R.H.; Chaturvedi, L.; Clemo, T.M.

    1996-03-01

    The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites' compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site

  4. Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards

    Energy Technology Data Exchange (ETDEWEB)

    Neill, R.H.; Chaturvedi, L.; Clemo, T.M. [and others

    1996-03-01

    The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites` compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site.

  5. EPA's Response to the February 2014 Release of Radioactive Material from the Waste Isolation Pilot Plant (WIPP): EPA's WIPP Air Sampling Data from April 2014

    Science.gov (United States)

    In April 2014, U.S. Environmental Protection Agency (EPA) environmental monitoring and assessment team members reviewed DOE's air sampling plan, visited DOE's air samplers and placed air samplers onsite near existing DOE samplers to corroborate results.

  6. Critical scientific issues in the demonstration of WIPP compliance with EPA repository standards

    International Nuclear Information System (INIS)

    Weart, W.D.; Chu, M.S.Y.

    1997-01-01

    The Department of Energy submitted a Compliance Certification Application for the Waste Isolation Pilot Plant to the Environmental Protection Agency (EPA) in October, 1996. A critical part of this application was a Performance Assessment which predicts the cumulative radioactive release to the accessible environment over a time period of 10,000 years. Comparison of this predicted release to the EPA standard shows a comfortable margin of compliance. The scientific understanding that was critical to developing this assessment spans a broad range of geotechnical disciplines, and required a thorough understanding of the site's geology and hydrology. Evaluation of the geologic processes which are active in the site region establishes that there will be no natural breach of site integrity for millions of years, far longer than the 10,000 year regulatory period. Inadvertent human intrusion is, therefore, the only credible scenario to lead to potential radioactive release to the accessible environment. To substantiate this conclusion and to quantify these potential releases from human intrusion, it has been necessary to develop an understanding of the following processes: (1) salt creep and shaft seal efficacy; (2) gas generation from organic decomposition of waste materials and anoxic corrosion of metals in the waste and waste packages; (3) solubilities for actinides in brine; (4) fluid flow in Salado formation rocks, and (5) hydrologic transport of actinides in the overlying dolomite aquifers. Other issues which had to be evaluated to allow definition of breach scenarios were brine reservoir occurrences and their associated reservoir parameters, consequences of mining over the repository, and drilling for natural resources in the vicinity of the repository. Results of all these studies will be briefly summarized in this paper

  7. Report: EPA Should Assess Needs and Implement Management Controls to Ensure Effective Incorporation of Chemical Safety Research Products

    Science.gov (United States)

    Report #17-P-0294, June 23, 2017. With management controls that ensure the collaborative development of research products and prioritize chemical safety research needs, the EPA would be better able to conduct faster chemical risk assessments.

  8. The consideration and representation of retention processes in the WIPP performance assessment: justification of adopted approaches and interaction with the regulator. Part 2: EPA review process and approval justification

    International Nuclear Information System (INIS)

    Byrum, Ch.; Peake, T.

    2002-01-01

    The Environmental Protection Agency (EPA) was directed by Congress to review whether the Waste Isolation Pilot Plant (WIPP) would comply with EPA regulations on radioactive waste disposal. The review of the effectiveness of retardation in the Culebra Dolomite Member of the Rustler Formation was a major focus of the Agency's review since the Culebra is postulated to be the major long-term pathway for the movement of radionuclides. EPA review consisted of reviewing the Department of Energy's (DOE) data as well as conducting separate evaluations and modelling. EPA independent evaluation identified several issues of concern: First, steady-state conditions did not appear to be reached in some experiments. Second, the effect of actinide concentration did not appear to be addressed. Third, the effect of magnesium oxide backfill in the repository for creating alkaline pH conditions in the brines passing through was not considered. Fourth, the experiments for Am(III) failed for various reasons and Pu(V) was used to represent Am(III). EPA also considered other concerns voiced by different reviewers in its review. After receipt of information supplemental to DOE's Compliance Certification Application (CCA), EPA was able to determine that the experimental foundation supported the retardation conceptual model in the Culebra and the parameters used were adequate. EPA independent modelling confirmed DOE's modelling that indicated radionuclide releases through the Culebra would be greatly reduced by even low K d values. However, EPA did determine that DOE should have used a log-uniform probability distribution for the retardation distribution coefficients (K d s)instead of the uniform probability distribution used in DOE's compliance calculations. EPA required an additional Performance Assessment (PA), called the Performance Assessment Verification Test (PAVT). The change in the K d distribution from uniform to log-uniform was incorporated for the K d values used in the PAVT. The

  9. Report: EPA Needs to Improve Management Practices to Ensure a Successful Customer Technology Solutions Project

    Science.gov (United States)

    Report #10-P-0194, August 23, 2010. Although EPA indicated it could avoid spending more than $115.4 million over 8.5 years by consolidating the desktop computing environment, improved management practices are needed.

  10. Successes and Experiences of the WIPP Project

    International Nuclear Information System (INIS)

    Chu, Margaret S.Y.; Weart, Wendell D.

    2000-01-01

    In May 1998, the US Environmental Agency (EPA) certified the US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) as being in compliance with all of the applicable regulations governing the permanent disposal of spent nuclear fuel, high-level waste, and transuranic radioactive waste. The WIPP, a transuranic waste repository, is the first deep geologic repository in the US to have successfully demonstrated regulatory compliance with long-term radioactive waste disposal regulations and be certified to receive wastes. Many lessons were learned throughout the 25-year history of the WIPP--from site selection to the ultimate successful certification. The experiences and lessons learned from the WIPP may be of general interest to other repository programs in the world. The lessons learned include all facets of a repository program: programmatic, managerial, regulatory, technical, and social. This paper addresses critical issues that arose during the 25 years of WIPP history and how they influenced the program

  11. WIPP Recertification - An Environmental Evaluation Group Perspective

    International Nuclear Information System (INIS)

    Allen, L. E.; Silva, M. K.

    2003-01-01

    The Waste Isolation Pilot Plant (WIPP), a repository for defense transuranic (TRU) waste, was built and is operated by the U.S. Department of Energy (DOE). The WIPP Land Withdrawal Act (LWA) required initial certification of compliance of the WIPP by the U.S. Environmental Protection Agency (EPA). In addition, a recertification decision is required by the LWA every five years, dated from the initial receipt of TRU waste. The first TRU waste shipment arrived at the WIPP on March 26, 1999, and therefore the first recertification application is due from DOE to EPA by March 25, 2004. The Environmental Evaluation Group (EEG) provides technical oversight of the WIPP project on behalf of the State of New Mexico. The EEG considers the first recertification as a precedent setting event. Therefore, the EEG began the identification of recertification issues immediately following the initial certification decision. These issues have evolved since that time, based on discussions with the DOE and EEG's understanding of DOE's ongoing research. Performance assessment is required by the EPA certification and its results are needed to determine whether the facility remains in compliance at the time of the recertification application. The DOE must submit periodic change reports to the EPA which summarize activities and conditions that differ from the compliance application. Also, the EPA may request additional information from the DOE that may pertain to continued compliance. These changes and new information must be considered for recertification performance assessment

  12. The Wipp Disposal Decision Plan: the Successful Road Map for Transparent and Credible Decision-Making

    International Nuclear Information System (INIS)

    Eriksson, Leif G.

    2001-01-01

    The Waste Isolation Pilot Plant (WIPP) deep geological repository for long-lived, transuranic radioactive waste (TRUW) opened on the 26th of March 1999. Beginning on the 4th of April 1994, the United States Department of Energy (DOE), implemented the WIPP Disposal Decision Plan (DDP), which embodied the five-year vision and intents of the then DOE Manager of the Carlsbad Area Office (CAO), presently the Carlsbad Field Office (CBFO). The successful design and implementation of the DDP ensured good science, enhanced regulator and stake holder (affected and interested parties) interactions and acceptance of programmatic decisions, which resulted in the certification of the WIPP TRUW repository by the U.S. Environmental Protection Agency (EPA) on the 18th of May 1998, almost three years earlier than projected in November 1993. The present paper contains three sections: A concise background information on the CBFO's TRUW disposal program, incl. the legal framework, current status, and author-envisioned challenges and solutions; A description of the main components and attributes of the WIPP DDP. A summary of the lessons learned during and after the 1994 through 1998 implementation of the WIPP DDP

  13. The Wipp Disposal Decision Plan: the Successful Road Map for Transparent and Credible Decision-Making

    Energy Technology Data Exchange (ETDEWEB)

    Eriksson, Leif G. [GRAM, Inc., Albuquerque, NM (United States)

    2001-07-01

    The Waste Isolation Pilot Plant (WIPP) deep geological repository for long-lived, transuranic radioactive waste (TRUW) opened on the 26th of March 1999. Beginning on the 4th of April 1994, the United States Department of Energy (DOE), implemented the WIPP Disposal Decision Plan (DDP), which embodied the five-year vision and intents of the then DOE Manager of the Carlsbad Area Office (CAO), presently the Carlsbad Field Office (CBFO). The successful design and implementation of the DDP ensured good science, enhanced regulator and stake holder (affected and interested parties) interactions and acceptance of programmatic decisions, which resulted in the certification of the WIPP TRUW repository by the U.S. Environmental Protection Agency (EPA) on the 18th of May 1998, almost three years earlier than projected in November 1993. The present paper contains three sections: A concise background information on the CBFO's TRUW disposal program, incl. the legal framework, current status, and author-envisioned challenges and solutions; A description of the main components and attributes of the WIPP DDP. A summary of the lessons learned during and after the 1994 through 1998 implementation of the WIPP DDP.

  14. Hydraulic Characterization Activities in Support of the Shaft-Seals Fluid-Flow Modeling Integration into the WIPP EPA Compliance Certification Application

    International Nuclear Information System (INIS)

    Knowles, M.K.; Hurtado, L.D.; Dale, Tim

    1997-12-01

    The Waste Isolation Pilot Plant (WIPP) is a planned geologic repository for permanent disposal of transuranic waste generated by the U.S. Department of Energy. Disposal regions consist of panels and drifts mined from the bedded salt of the Salado Formation at a depth of approximately 650 m below the surface. This lithology is part of the 225 million year old Delaware Basin, and is geographically located in southeastern New Mexico. Four shafts service the facility needs for air intake, exhaust, waste handling, and salt handling. As the science advisor for the project, Sandia National Laboratories developed the WIPP shaft sealing system design. This design is a fundamental component of the application process for facility licensing, and has been found acceptable by stakeholders and regulatory agencies. The seal system design is founded on results obtained from laboratory and field experiments, numerical modeling, and engineering judgment. This paper describes a field test program to characterize the fluid flow properties in the WIPP shafts at representative seal locations. This work was conducted by Duke Engineering and Services under contract to Sandia National Laboratories in support of the seal system design

  15. WIPP 2004 Site Environmental Report

    International Nuclear Information System (INIS)

    2005-01-01

    The mission of Waste Isolation Pilot Plant (WIPP) is to safely and permanently 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 (U.S.). In 2004, 8,839 cubic meters (m3) of TRU waste were emplaced at WIPP. From the first receipt of waste in March 1999 through the end of 2004, 25,809 m3 of TRU waste had been emplaced at WIPP. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of WIPP environmental resources. DOE Order 450.1, Environmental Protection Program; DOE Order 231.1A, Environment, Safety, and Health Reporting; and DOE Order 5400.5, Radiation Protection of the Public and Environment, 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 2004 Site Environmental Report (SER) summarizes environmental data from 2004 that characterize environmental management performance and demonstrate compliance with applicable federal and state regulations. This report was prepared in accordance with DOE Order 231.1A, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2004 (DOE, 2005). The order and the guidance require that DOE facilities submit an annual SER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) further requires that the SER be provided to the New Mexico Environment Department (NMED).

  16. WIPP 2004 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2005-09-30

    The mission of Waste Isolation Pilot Plant (WIPP) is to safely and permanently 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 (U.S.). In 2004, 8,839 cubic meters (m3) of TRU waste were emplaced at WIPP. From the first receipt of waste in March 1999 through the end of 2004, 25,809 m3 of TRU waste had been emplaced at WIPP. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of WIPP environmental resources. DOE Order 450.1, Environmental Protection Program; DOE Order 231.1A, Environment, Safety, and Health Reporting; and DOE Order 5400.5, Radiation Protection of the Public and Environment, 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 2004 Site Environmental Report (SER) summarizes environmental data from 2004 that characterize environmental management performance and demonstrate compliance with applicable federal and state regulations. This report was prepared in accordance with DOE Order 231.1A, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2004 (DOE, 2005). The order and the guidance require that DOE facilities submit an annual SER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) further requires that the SER be provided to the New Mexico Environment Department (NMED).

  17. WIPP Pecos Management Reports

    Science.gov (United States)

    These reviews and evaluations compiled by Pecos Management Services, Inc. encompass the current and future WIPP activities in the program areas of TRU waste characterization, transportation, and disposal.

  18. WIPP [Waste Isolation Pilot Plant] test phase plan: Performance assessment

    International Nuclear Information System (INIS)

    1990-04-01

    The U.S. Department of Energy (DOE) is responsible for managing the disposition of transuranic (TRU) wastes resulting from nuclear weapons production activities of the United States. These wastes are currently stored nationwide at several of the DOE's waste generating/storage sites. The goal is to eliminate interim waste storage and achieve environmentally and institutionally acceptable permanent disposal of these TRU wastes. The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being considered as a disposal facility for these TRU wastes. This document describes the first of the following two major programs planned for the Test Phase of WIPP: Performance Assessment -- determination of the long-term performance of the WIPP disposal system in accordance with the requirements of the EPA Standard; and Operations Demonstration -- evaluation of the safety and effectiveness of the DOE TRU waste management system's ability to emplace design throughput quantities of TRU waste in the WIPP underground facility. 120 refs., 19 figs., 8 tabs

  19. WIPP documentation plan

    International Nuclear Information System (INIS)

    Plung, D.L.; Montgomery, T.T.; Glasstetter, S.R.

    1986-01-01

    In support of the programs at the Waste Isolation Pilot Plant (WIPP), the Publications and Procedures Section developed a documentation plan that provides an integrated document hierarchy; further, this plan affords several unique features: 1) the format for procedures minimizes the writing responsibilities of the technical staff and maximizes use of the writing and editing staff; 2) review cycles have been structured to expedite the processing of documents; and 3) the numbers of documents needed to support the program have been appreciably reduced

  20. Technical issues for WIPP

    International Nuclear Information System (INIS)

    Hunter, T.O.

    1979-01-01

    Emplacement of wastes in the WIPP will include experiments on various waste types which will provide essential data on waste-rock interaction and repository response. These experiments will include evolution of the synergistic effects of both heat production, radiation, and actual waste forms. While these studies will provide essential data on the validity of waste isolation in bedded salt, they will be preceded by a broad-based experimental program which will resolve many of the current technical issues providing not only an assessment of the safety of performing such experiments but also the technical basis for assurance that the appropriate experiments are performed. Data and predictive modeling techniques, which are currently available, can bound the consequences associated with these technical issues. Predictions of the impact on public safety based on these analyses indicate that safe waste disposal in WIPP salt beds is achievable; however, a major use of WIPP will be to conduct realistic experiments with HLW forms to address some of the unresolved details of these waste/salt interactions

  1. Waste Isolation Pilot Plant (WIPP) startup plan

    International Nuclear Information System (INIS)

    1988-03-01

    To allow the Waste Isolation Pilot Plant (WIPP) to transition from a Major System Acquisition to an operating demonstration facility, the Acquisition Executive and the Energy System Acquisition Advisory Board (ESAAB) must concur in the facility's readiness to receive waste. This action, designated in DOE Order 4700.1 as Key Decision Four, concludes with the Chairman of the ESAAB issuing a Record of Decision. Since the meeting leading to the Record of Decision is scheduled for August 1988, plans must be made to ensure all activities contributing to that decision are completed in a clear and well-coordinated process. To support that effort, this Start-Up Plan was prepared to identify and track key events necessary to verify WIPP's readiness to receive waste; this provides a management/scheduling/tracking tool for the DOE WIPP Project Office (WPO) and a tracking mechanism for the DOE Albuquerque Operations Office (DOE-AL) and for DOE Headquarters (DOE-HQ); and describe the process to ensure readiness is documented by providing relevant data and reports to the cognizant decision makers. The methods by which these two purposes are achieved are discussed in further detail in the remainder of this plan

  2. WIPP startup: Overcoming unprecedented challenges

    International Nuclear Information System (INIS)

    Hunt, Arlen E.

    1992-01-01

    Since its authorization by the U.S. Congress in Public Law 96-164, the Waste Isolation Pilot Plant Program has achieved significant progress. Subsequent to a Record of Decision based on the October 1980 Final Environmental Impact Statement (FEIS), the scientific and engineering challenge of constructing a 100-acre mined repository to demonstrate the safe and environmentally sound disposal of defense program generated transuranic waste became reality. Since initial conception, however, a complex program has evolved. Demonstration of compliance with the requirements of the Resource Conservation and Recovery Act (RCRA) and Environmental Protection Agency (EPA) disposal Standards defined in 10 CFR 191, Subpart B (yet to be repromulgated), became prerequisites to a disposal decision. On June 13, 1990, based on a supplement to the 1980 FEIS, the decision was made to redefine the program to include a formal test phase. This decision required an addendum to the Final Safety Analysis Report to assure commitment to safety considerations, an intensive operational readiness review effort, and the need for a No-Migration Determination for the Environmental Protection Agency. In addition to meeting the technical challenges, the need to satisfy a broad spectrum of oversight groups (some directly funded by the Department of Energy) was required. With the decision making process publicly displayed on the Secretary of Energy's Decision Plan, the unprecedented challenges of the WIPP Program were painstakingly met, one by one, in an accountable and visible manner. (author)

  3. WIPP - Pre-Licensing and Operations: Developer and Regulator Perspectives

    International Nuclear Information System (INIS)

    Peake, Tom; Patterson, R.

    2014-01-01

    The Waste Isolation Pilot Plant (WIPP) is a disposal system for defense-related transuranic (TRU) radioactive waste. Developed by the Department of Energy (DOE), WIPP is located in Southeastern New Mexico: radioactive waste is disposed of 2,150 feet underground in an ancient layer of salt with a total capacity of 6.2 million cubic feet of waste. Congress authorized the development and construction of WIPP in 1980 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. This paper makes a historical review of the site development, site operations (waste disposal operations started in 1999), communications between US EPA and DOE, the chronology of pre-licensing and pre-operations, the operational phase and the regulatory challenges, and the lessons learned after 12 years of operations

  4. WIPP Status and Plans - 2013 - 13379

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, R.A.; Franco, J. [U.S. Department of Energy, PO Box 3090, Carlsbad, NM 88220 (United States)

    2013-07-01

    An up-to-date look at the many aspects of America's only deep geologic long-lived radioactive waste repository is presented in this paper. WIPP's mission includes coordination of all Department of Energy (DOE) sites to prepare, package and characterize defense transuranic waste for final shipment and emplacement in WIPP. The Waste Isolation Pilot Plant (WIPP) is completing its 14. year of operations. Five of the ten planned disposal panels have been filled and sealed from ventilation, with about half of the legislated volume capacity consumed. About 11,000 shipments have been made successfully, traveling more than 40 million kilometers across the nation's highways. A fleet of new Type B shipping packages, the TRUPACT-III, has been added to the transportation capability, with an ongoing campaign to de-inventory large waste items from the Savannah River Site, while minimizing size reduction and repackaging. A new shipping and emplacement method for remote handled waste in shielded containers has been approved for disposal, and will significantly improve operational efficiency. Remote handled waste packaged in these shielded containers will be shipped, handled and emplaced as contact handled waste. Also described is a new criticality control over-pack container, which will improve efficiency when shipping high fissile-content waste streams consisting of Special Nuclear Material declared as waste from nuclear weapons sites. The paper describes the importance of the infrastructure at WIPP to ensure disposal site availability for defense transuranic waste sites across the weapons complex. With the facility reaching its original design lifetime, there are many infrastructure maintenance and improvements being planned and performed. (authors)

  5. Use of Performance Assessment in Support of Waste Isolation Pilot Plant (WIPP) Programmatic Activity Planning

    International Nuclear Information System (INIS)

    BASABILVAZO, GEORGE; JOW, HONG-NIAN; LARSON, KURT W.; MARIETTA, MELVIN G.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is being developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. A Compliance Certification Application (CCA) of the WIPP for such disposal was submitted to the U.S. Environmental Protection Agency (EPA) in October 1996, and was approved by EPA in May 1998. In June 1998, two separate, but related, lawsuits were filed, one against DOE and one against EPA. On March 22, 1999, the court ruled in favor of DOE, and on March 26, 1999, DOE formally began disposal operations at the WIPP for non-mixed (non-hazardous) TRU waste. Before the WIPP can begin receiving mixed (hazardous) TRU waste, a permit from the State of New Mexico for hazardous waste disposal needs to be issued. It is anticipated that the State of New Mexico will issue a hazardous waste permit by November 1999. It is further anticipated that the EPA lawsuit will be resolved by July 1999. Congress (Public Law 102-579, Section 8(f)) requires the WIPP project to be recertified by the EPA at least as frequently as once every five years from the first receipt of TRU waste at the WIPP site. As part of the DOE's WIPP project recertification strategy, Sandia National Laboratories (SNL) has used systems analysis and performance assessment to prioritize its scientific and engineering research activities. Two 1998 analyses, the near-field systems analysis and the annual sensitivity analysis, are discussed here. Independently, the two analyses arrived at similar conclusions regarding important scientific activities associated with the WIPP. The use of these techniques for the recent funding allocations at SNL's WIPP project had several beneficial effects. It increased the level of acceptance among project scientists that management had fairly and credibly compared alternatives when making prioritization decisions. It improved the ability of SNL and its project sponsor, the Carlsbad Area Office of the DOE, to

  6. WIPP operations planning: an overview

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Cossel, S.C.; Plung, D.L.

    1985-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first-of-a-kind facility for emplacement of radioactive waste in a geologic repository. The concern for safe and efficient operations - coupled with the domestic and international significance of this project - necessitates that WIPP be a ''model plant.'' To develop WIPP as a model plant, a unique planning methodology was employed to identify, evaluate, incorporate, and implement these elements that together will form the best possible overall operation. The resulting improvements in communication among project participants and the smooth transition being made from construction are equally attributable to the methodology employed and the operating program plan developed. 1 fig

  7. Sandia WIPP calibration traceability

    Energy Technology Data Exchange (ETDEWEB)

    Schuhen, M.D. [Sandia National Labs., Albuquerque, NM (United States); Dean, T.A. [RE/SPEC, Inc., Albuquerque, NM (United States)

    1996-05-01

    This report summarizes the work performed to establish calibration traceability for the instrumentation used by Sandia National Laboratories at the Waste Isolation Pilot Plant (WIPP) during testing from 1980-1985. Identifying the calibration traceability is an important part of establishing a pedigree for the data and is part of the qualification of existing data. In general, the requirement states that the calibration of Measuring and Test equipment must have a valid relationship to nationally recognized standards or the basis for the calibration must be documented. Sandia recognized that just establishing calibration traceability would not necessarily mean that all QA requirements were met during the certification of test instrumentation. To address this concern, the assessment was expanded to include various activities.

  8. Sandia WIPP calibration traceability

    International Nuclear Information System (INIS)

    Schuhen, M.D.; Dean, T.A.

    1996-05-01

    This report summarizes the work performed to establish calibration traceability for the instrumentation used by Sandia National Laboratories at the Waste Isolation Pilot Plant (WIPP) during testing from 1980-1985. Identifying the calibration traceability is an important part of establishing a pedigree for the data and is part of the qualification of existing data. In general, the requirement states that the calibration of Measuring and Test equipment must have a valid relationship to nationally recognized standards or the basis for the calibration must be documented. Sandia recognized that just establishing calibration traceability would not necessarily mean that all QA requirements were met during the certification of test instrumentation. To address this concern, the assessment was expanded to include various activities

  9. WIPP radiation dosimetry program

    International Nuclear Information System (INIS)

    Wu, C.F.

    1991-01-01

    Radiation dosimetry is the process by which various measurement results and procedures are applied to quantify the radiation exposure of an individual. Accurate and precise determination of radiation dose is a key factor to the success of a radiation protection program. The Waste Isolation Pilot Plant (WIPP), a Department of Energy (DOE) facility designed for permanent repository of transuranic wastes in a 2000-foot-thick salt bed 2150 feet underground, has established a dosimetry program developed to meet the requirements of DOE Order 5480.11, ''Radiation Protection for Occupational Workers''; ANSI/ASME NQA-1, ''Quality Assurance Program Requirements for Nuclear Facilities''; DOE Order 5484.1, ''Environmental Protection, Safety, and Health Protection Information Reporting Requirements''; and other applicable regulations

  10. WIPP gets thumbs up; Ward Valley time runs out

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    Legislation passed in late September clears the way for the Department of Energy to begin shipment of national defense transuranic (TRU) radioactive waste to the Waste Isolation Pilot Plant (WIPP), near Carlsbad, NM, as early as November 1997. On September 23, President Clinton signed the Fiscal Year 1997 Defense Authorization Bill, which contained amendments to the 1992 WIPP Land Withdrawal Act. The implementation of the law will help the DOE in its cleanup sites nationwide, and will enhance public health and safety by providing for the disposal of the waste in a 2150-ft underground salt formation, far away from population centers. Key components of the legislation include the following: (1) The US Environmental Protection Agency (EPA) will continue as primary regulator of WIPP. (2) The EPA will have one year to review the Compliance Certification Application, which the DOE was to submit by October 31, 1996. Upon EPA certification (expected in October 1997), the DOE will begin shipping transuranic waste in November 1997. (3) A six-month waiting period for waste shipments has been removed (previously, the DOE was required to wait 180 days after the Energy Secretary's decision to begin disposal operations). (4) New Mexico will receive $20 million immediately, and annually for 14 years, with the funds to be used for infrastructure and road improvements in the state

  11. WIPP Project Records Management Handbook

    International Nuclear Information System (INIS)

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) Records Management Handbook provides the WIPP Project Records Management personnel with a tool to use to fulfill the requirements of the WIPP Records Program and direct their actions in the important area of records management. The handbook describes the various project areas involved in records management, and how they function. The handbook provides the requirements for Record Coordinators and Master Record Center (MRC) personnel to follow in the normal course of file management, records scheduling, records turnover, records disposition, and records retrieval. More importantly, the handbook provides a single reference which encompasses the procedures set fourth in DOE Order 1324.2A, ''Records Disposition'' ASME NQA-1, ''Quality Assurance Program Requirements for Nuclear Facilities'' and DOE-AL 5700.6B, ''General Operations Quality Assurance.'' These documents dictate how an efficient system of records management will be achieved on the WIPP Project

  12. WIPP and the local communities

    International Nuclear Information System (INIS)

    Krenz, D.L.; Sankey, C.A.

    1986-01-01

    The Waste Isolation Pilot Plant (WIPP) is located 26 miles southeast of Carlsbad, New Mexico in southeastern New Mexico. Other neighboring communities include Lovington, Hobbs and Loving, New Mexico. In March 1983, the Site and Preliminary Design Validation (SPDV) phase of the project was completed. Full scale facility construction began in July of that year. Overall site construction is scheduled to be complete in December 1986. Construction completion will be followed by pre-operational and safety check-out in 1987, prior to receiving the first nuclear waste which is targeted for receipt on or after October 1988. WIPP has had a significant impact on the local communities. Many local people have been hired by the Department of Energy (DOE), Westinghouse Electric, and U.S. Army Corps of Engineers contractors, as well as associated sub-contractors. As of December 31, 1985, 64% of the 643 people working at WIPP were hired from an 80-mile or less radius of the WIPP site. The majority of local residents support WIPP. As declining potash and mining industries negatively impacted the economic condition of Southeastern New Mexico, WIPP brought jobs and new business opportunities to the area

  13. The legal, regulatory and safety basis for opening WIPP

    International Nuclear Information System (INIS)

    Dials, G.E.

    1997-01-01

    Current laws in the United States of America direct the U.S. Department of Energy (DOE) to site, design, operate, and decommission a deep geological repository for safe disposal of transuranic radioactive waste (TRUW) at the Waste Isolation Pilot Plant (WIPP) site. In 1993, the DOE established the Carlsbad Area Office (CAO) to integrate the nation's management of TRUW and to open the WIPP site for safe disposal of TRUW in compliance with applicable laws and regulations. The CAO submitted the final Compliance Certification Application (CCA) in 1996, and is on schedule to open WIPP in November 1997, about three years earlier than scheduled before the establishment of the CAO. The performance assessment (PA) embodied in the CCA demonstrates that WIPP meets the EPA's regulatory requirements for radioactive releases for the 10,000 year regulatory period in both the undisturbed and disturbed (human intrusion) scenarios. Detailed planning, compliance-based research and development (R and D), teamwork among project participants and early and open iterative interactions with the regulators, oversight groups and other interested parties in the certification/permitting process are key components of the progress in the safe disposal of long-lived radioactive wastes. (author)

  14. WIPP Facility Work Plan for Solid Waste Management Units

    International Nuclear Information System (INIS)

    2000-01-01

    This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA. A

  15. WIPP Facility Work Plan for Solid Waste Management Units

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2000-02-25

    This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED’s guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA

  16. EPA's Review of DOE's Inventory Tracking for TRU Wastes at Waste Control Specialists

    Science.gov (United States)

    On April 9, 2014, EPA's Waste Isolation Pilot Plant (WIPP) waste characterization team visited Waste Control Specialists (WCS) to determine whether DOE was meeting EPA's waste inventory tracking requirements at 40 CFR 194.24(c)(4).

  17. Performance assessment in support of compliance certification application for the WIPP project

    International Nuclear Information System (INIS)

    Jow, H.N.; Anderson, D.R.; Marietta, M.; Helton, J.; Basabilvazo, G.

    1998-03-01

    The Waste Isolation Pilot Plant (WIPP) is being developed by the US Department of Energy for the geologic (deep underground) disposal of transuranic (TRU) waste. A Compliance Certification Application (CCA) of the WIPP (1) for such disposal was submitted to the US Environmental Protection Agency (EPA) in October, 1996, and is currently under review, with a decision anticipated in late 1997. An important component of the CCA is a performance assessment (PA) for the WIPP carried out by Sandia National Laboratories. The final outcome of the PA is a complementary cumulative distribution function (CCDF) for radionuclide releases from the WIPP to the accessible environment and an assessment of the confidence with which this CCDF can be estimated. This paper describes the computational process used to develop the CCDF. The results of uncertainty and sensitivity analysis are also presented

  18. 2002 WIPP Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2002-09-30

    DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (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; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses 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.

  19. Evaluation of proposed panel closure modifications at WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Lawrence E.; Silva, Matthew K.; Channell, James K.; Abel, John F.; Morgan, Dudley R.

    2001-12-31

    A key component in the design of the WIPP repository is the installation of concrete structures as panel seals in the intake and exhaust drifts after a panel has been filled with waste containers. As noted in the EPA final rule, the panel seal closure system is intended to block brine flow between the waste panels at the WIPP. On April 17, 2001, the DOE proposed seven modifications to the EPA concerning the design of the panel closure system. EPA approval of these modifications is necessary since the details of the panel design are specified in EPA’s final rule as a condition for WIPP certification. However, the EPA has not determined whether a rulemaking would be required for these proposed design modifications. On September 4, 2001, the DOE withdrew the request, noting that it would be resubmitted on a future date. The Environmental Evaluation Group (EEG) contracted with two engineers, Dr. John Abel and Dr. Rusty Morgan, to evaluate the proposed modifications. The EEG has accepted the conclusions and recommendations from these two experts: 1) replacement of Salado Mass Concrete with a generic salt-based concrete; 2) replacement of the explosion wall with a construction wall; 3) replacement of freshwater grouting with salt-based grouting; 4) option to allow surface or underground mixing; and 5) option to allow up to one year for completion of closure. The proposed modification to allow local carbonate river rock as aggregate is acceptable pending demonstration that no problems will exist in the resulting concrete. The proposed modification to give the contractor discretion in removal of steel forms is not supported. Instead, several recommendations are made to specifically reduce the number of forms left, thereby reducing potential migration pathways.

  20. WIPP facility representative program plan

    International Nuclear Information System (INIS)

    1994-01-01

    This plan describes the Department of Energy (DOE), Carlsbad Area Office (CAO) facility representative (FR) program at the Waste Isolation Pilot Plant (WIPP). It provides the following information: (1) FR and support organization authorities and responsibilities; (2) FR program requirements; and (3) FR training and qualification requirements

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

    International Nuclear Information System (INIS)

    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

  2. Designing a database for performance assessment: Lessons learned from WIPP

    International Nuclear Information System (INIS)

    Martell, M.A.; Schenker, A.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA) Performance Assessment (PA) used a relational database that was originally designed only to supply the input parameters required for implementation of the PA codes. Reviewers used the database as a point of entry to audit quality assurance measures for control, traceability, and retrievability of input information used for analysis, and output/work products. During these audits it became apparent that modifications to the architecture and scope of the database would benefit the EPA regulator and other stakeholders when reviewing the recertification application. This paper contains a discussion of the WPP PA CCA database and lessons learned for designing a database

  3. A methodology of uncertainty/sensitivity analysis for PA of HLW repository learned from 1996 WIPP performance assessment

    International Nuclear Information System (INIS)

    Lee, Y. M.; Kim, S. K.; Hwang, Y. S.; Kang, C. H.

    2002-01-01

    The WIPP (Waste Isolation Pilot Plant) is a mined repository constructed by the US DOE for the permanent disposal of transuranic (TRU) wastes generated by activities related to defence of the US since 1970. Its historical disposal operation began in March 1999 following receipt of a final permit from the State of NM after a positive certification decision for the WIPP was issued by the EPA in 1998, as the first licensed facility in the US for the deep geologic disposal of radioactive wastes. The CCA (Compliance Certification Application) for the WIPP that the DOE submitted to the EPA in 1966 was supported by an extensive Performance Assessment (PA) carried out by Sandia National Laboratories (SNL), with so-called 1996 PA. Even though such PA methodologies could be greatly different from the way we consider for HLW disposal in Korea largely due to quite different geologic formations in which repository are likely to be located, a review on lots of works done through the WIPP PA studies could be the most important lessons that we can learn from in view of current situation in Korea where an initial phase of conceptual studies on HLW disposal has been just started. The objective of this work is an overview of the methodology used in the recent WIPP PA to support the US DOE WIPP CCA ans a proposal for Korean case

  4. WIPP: why are we waiting?

    International Nuclear Information System (INIS)

    Barker, K.

    1991-01-01

    Rooms cut into salt almost half a mile below the state of New Mexico could become the United States' first underground repository for defence generated transuranic waste. The Department of Energy (DoE) was hoping to ship the first waste to the Waste Isolation Pilot Plant (WIPP) this August, but the $800 million project has faced bureaucratic delays and a definite date has yet to be set. The state of New Mexico established the Environmental Evaluation Group (EEG) to perform an independent technical evaluation of the project with respect to potential radiation exposure for people or environmental degradation in the area around the WIPP site. The Waste Isolation Pilot Plant has two objectives: to perform scientific investigations into the behaviour of salt rock and its interactions with transuranic and mixed waste under a variety of conditions; and to demonstrate that transuranic waste can be safely handled, transported and stored in a geologic repository. The EEG is unhappy about proposed in-repository tests to assess the long term performance of WIPP. (author)

  5. The WIPP institutional program for states' involvement in WIPP transportation planning, and operations

    International Nuclear Information System (INIS)

    Leonard, R.

    1991-01-01

    The Supplemental Stipulated Agreement of 1982 between the state of New Mexico and the Department of Energy (DOE) committed the DOE to emergency response training in New Mexico. In 1988, the state of New Mexico and the DOE entered into a two-year agreement providing $203,017 for financial assistance and $67,000 for equipment to enhance the state's emergency response capability. In 1990, this agreement was extended for an additional two years providing $226,088 for financial assistance and $39,000 for emergency response equipment. Also, in 1988 an agreement between the Western Governors' Association and the United States Department of Transportation provided $1.0 million to seven western states (Colorado, Idaho, New Mexico, Oregon, Utah, Washington, and Wyoming) to identify and implement programs to help ensure the safe transportation of transuranic waste from western points of origin to the Waste Isolation Pilot Plant (WIPP). As part of this process, the Western Governors' Association and the seven states prepared the Report to Congress, Transport of Transuranic Wastes to the Waste Isolation Pilot Plant: State Concerns and Proposed Solutions. In July 1990, a five-year cooperative agreement between the Western Governors' Association and the DOE was signed providing $1.515 million in funding to seven states along the Hanford/WIPP route. This continued the work started under the Department of Transportation's cooperative agreement

  6. An evaluation of the proposed tests with radioactive waste at WIPP

    International Nuclear Information System (INIS)

    Chaturvedi, L.; Silva, M.

    1992-01-01

    This paper discusses the Waste Isolation Pilot Plant (WIPP) a planned repository for permanent disposal of transuranic (TRU) radiative waste that has resulted from the defense activities of the U.S. Government over the past 50 years. Only the waste that is currently stored in an easily retrievable mode at ten U.S. Department of Energy (DOE) laboratories around the country will be shipped to WIPP. The waste consists of various kinds of trash including paper, rubber, rags and metal that is contaminated with radionuclides with very long half-lives. The decision to dispose of the waste permanently will be made based on projections of the behavior of the waste and the repository of 10,000 years or more. DOE has proposed shipping a limited amount of waste to WIPP for a five year Test Phase to demonstrating compliance with the U.S. Environmental Protection Agency (EPA) Standard for long-term isolation

  7. Evaluation of the suitability of the WIPP site

    International Nuclear Information System (INIS)

    Neill, R.H.; Channell, J.K.; Chaturvedi, L.; Little, M.S.; Rehfeldt, K.; Spiegler, P.

    1983-05-01

    Determination of the suitability of the site for WIPP is only the first major phase in the evaluation of the radiological impact of the repository on the public health and safety. The Environmental Evaluation Group (EEG) will continue to independently review the design of the facility, the operational procedures, the criteria for packaging and shipment of the waste, the plans, procedures and results of the WIPP experiments, emergency preparedness, adherence to EPA and pertinent NRC regulations, and other important features of the project. EEG has concluded from existing evidence that the Los Medanos site for the WIPP project has been characterized in sufficient detail to warrant confidence in the validation of the site for the permanent emplacement of approximately 6 million cubic feet of defense transuranic waste. This conclusion is based on the assumption that the maximum surface dose rate for the unshielded remote-handled transuranic waste canisters will be 100 rem/hr with a maximum radionuclide concentration of 23 Ci/liter. The Site and Preliminary Design Validation program, through the drilling of two shafts to the selected repository level at 2160 ft below the surface and excavation of about 9000 ft of tunnels, has confirmed the interpretations made about the subsurface geological conditions at the site. For an assessment of the potential radiation effects of the nuclear waste repository on the public health and safety, it is necessary to understand the regional geological and hydrological setting. Much work has been done to understand these conditions and to address several specific issues which have arisen as a result of such studies. However, it is almost inevitable that some questions remain unanswered at a given time in the decision-making process. EEG has identified work which still needs to be done at the Los Medanos site in order to improve confidence in the worst case scenario models of possible breaches of the repository

  8. Proposed Changes to EPA's Transuranic Waste Characterization Approval Process

    International Nuclear Information System (INIS)

    Joglekar, R.D.; Feltcorn, E.M.; Ortiz, A.M.

    2003-01-01

    This paper describes the changes to the waste characterization (WC) approval process proposed in August 2002 by the U.S. Environmental Protection Agency (EPA or the Agency or we). EPA regulates the disposal of transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) repository in Carlsbad, New Mexico. EPA regulations require that waste generator/storage sites seek EPA approval of WC processes used to characterize TRU waste destined for disposal at WIPP. The regulations also require that EPA verify, through site inspections, characterization of each waste stream or group of waste streams proposed for disposal at the WIPP. As part of verification, the Agency inspects equipment, procedures, and interviews personnel to determine if the processes used by a site can adequately characterize the waste in order to meet the waste acceptance criteria for WIPP. The paper discusses EPA's mandate, current regulations, inspection experience, and proposed changes. We expect that th e proposed changes will provide equivalent or improved oversight. Also, they would give EPA greater flexibility in scheduling and conducting inspections, and should clarify the regulatory process of inspections for both Department of Energy (DOE) and the public

  9. WIPP Regulatory Compliance Strategy and Management Plan for demonstrating compliance to long-term disposal standards

    International Nuclear Information System (INIS)

    1994-05-01

    The primary purpose of this document is to provide a strategy by which the WIPP will demonstrate its ability to perform as a deep geologic repository. The document communicates the DOE's understanding of the regulations related to long-term repository performance; and provides the most efficient strategy that intergrates WIPP Project elements, ensures the sufficiency of information, and provides flexibility for changes in the TRU waste generation system to facilitate the disposal of defense-generated TRU wastes. In addition, this document forms a focal point between the DOE and its various external regulators as well as other stakeholders for the purpose of arriving at compliance decisions that consider all relevant input

  10. WIPP performance assessment: impacts of human intrusion

    International Nuclear Information System (INIS)

    Anderson, D.R.; Hunter, R.L.; Bertram-Howery, S.G.; Lappin, A.R.

    1989-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is a research and development facility that may become the USA's first and only mined geologic repository for transuranic waste. Human intrusion into the WIPP repository after closure has been shown by preliminary sensitivity analyses and calculations of consequences to be an important, and perhaps the most important, factor in long-term repository performance

  11. Basic data report for drillhole WIPP 11 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1982-02-01

    Seismic reflection data from petroleum industry sources showed anomalous reflectors in the Castile Formation over a small area about 3 miles north of the center of the Waste Isolation Pilot Plant (WIPP) site. Additional corroborative seismic reflection data were collected as part of WIPP investigations, and WIPP 11 was drilled to investigate the anomaly. WIPP 11 was drilled near the northwest corner of Section 9, T.22.S., R.31E. it penetrated, in descending order, sand dune deposits and the Gatuna Formation (29'), Santa Rosa Sandstone (132'), Dewey Lake Red Beds (502'), Rustler Formation (288'), Salado Formation (1379'), and most of the Castile Formation (1240'). Beds within the lower part of the Salado, and the upper anhydrite of the Castile, are thinner than normal; these beds are displaced upward structurally by the upper Castile halite which is highly thickened (about 968'). The lowest halite is thin (51') and the basal anhydrite was not completely penetrated. Subsequent seismic and borehole data has shown WIPP 11 to be in a structural complex now identified as the disturbed zone. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level waste, though there are no plans at this time to dispose of high level waste or spent fuel at WIPP

  12. Compilation of historical radiological data collected in the vicinity of the WIPP site

    International Nuclear Information System (INIS)

    Bradshaw, P.L.; Louderbough, E.T.

    1987-01-01

    The Radiological Baseline Program (RBP) at the Waste Isolation Pilot Plant (WIPP) has been implemented to characterize the radiological conditions at the site prior to receipt of radioactive wastes. Because southeastern New Mexico was the site of an underground nuclear test in 1961, various sampling programs have intermittently monitored background and elevated radiation levels in the vicinity of the WIPP. In addition, radiological characterization of the site region was performed during the 1970's in support of the WIPP Environmental Impact Statement. The historical data are drawn primarily from monitoring activities of the US Public Health Service (PHS), the Environmental Protection Agency (EPA), US Geological Survey (USGS) and Sandia National Laboratories, Albuquerque (SNLA). Information on air and water quality, meat, milk, biota and vegetation is included in the report. This survey is intended to provide a source of reference for historical data on radiological conditions in the vicinity of the WIPP site prior to the establishment of a systematic Radiological Baseline Program. 31 refs., 1 fig

  13. Basic data report for deepening of drillhole WIPP 13 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    1982-10-01

    WIPP 13 is a borehole drilled in eastern Eddy County, New Mexico, in section 17, T22S,R31E, in order to investigate a subsurface seismic disturbed zone. The first 1035 ft of the borehole were drilled in July and August 1978. The deepening of WIPP 13 was performed in 1979 between August and October. This report documents the deepening of WIPP 13 to 3861.8 ft. Only rocks of the Permian, Salado and Castile Formations were penetrated in the deepening. Cores were obtained for some portions of the hole and cuttings were collected from some of the sections which were not cored (see Table 1). A suite of geophysical logs was run to provide information on lithology, structure and geochemistry. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  14. WIPP fire hazards and risk analysis

    International Nuclear Information System (INIS)

    1991-05-01

    The purpose of this analysis was to conduct a fire hazards risk analysis of the Transuranic (TRU) contact-handled waste receipt, emplacement, and disposal activities at the Waste Isolation Pilot Plant (WIPP). The technical bases and safety envelope for these operations are defined in the approved WIPP Final Safety Analysis Report (FSAR). Although the safety documentation for the initial phase of the Test Program, the dry bin scale tests, has not yet been approved by the Department of Energy (DOE), reviews of the draft to date, including those by the Advisory Committee on Nuclear Facility Safety (ACNFS), have concluded that the dry bin scale tests present no significant risks in excess of those estimated in the approved WIPP FSAR. It is the opinion of the authors and reviewers of this analysis, based on sound engineering judgment and knowledge of the WIPP operations, that a Fire Hazards and Risk Analysis specific to the dry bin scale test program is not warranted prior to first waste receipt. This conclusion is further supported by the risk analysis presented in this document which demonstrates the level of risk to WIPP operations posed by fire to be extremely low. 15 refs., 41 figs., 48 tabs

  15. The WIPP Water Quality Sampling Program

    International Nuclear Information System (INIS)

    Uhland, D.; Morse, J.G.; Colton, D.

    1986-01-01

    The Waste Isolation Pilot Plant (WIPP), a Department of Energy facility, will be used for the underground disposal of wastes. The Water Quality Sampling Program (WQSP) is designed to obtain representative and reproducible water samples to depict accurate water composition data for characterization and monitoring programs in the vicinity of the WIPP. The WQSP is designed to input data into four major programs for the WIPP project: Geochemical Site Characterization, Radiological Baseline, Environmental Baseline, and Performance Assessment. The water-bearing units of interest are the Culebra and Magneta Dolomite Members of the Rustler Formation, units in the Dewey Lake Redbeds, and the Bell Canyon Formation. At least two chemically distinct types of water occur in the Culebra, one being a sodium/potassium chloride water and the other being a calcium/magnesium sulfate water. Water from the Culebra wells to the south of the WIPP site is distinctly fresher and tends to be of the calcium/magnesium sulfate type. Water in the Culebra in the north and around the WIPP site is distinctly fresher and tends to be of the sodium/potassium chloride type and is much higher in total dissolved solids. The program, which is currently 1 year old, will continue throughout the life of the facility as part of the Environmental Monitoring Program

  16. Pretest characterization of WIPP experimental waste

    International Nuclear Information System (INIS)

    Johnson, J.; Davis, H.

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, is an underground repository designed for the storage and disposal of transuranic (TRU) wastes from US Department of Energy (DOE) facilities across the country. The Performance Assessment (PA) studies for WIPP address compliance of the repository with applicable regulations, and include full-scale experiments to be performed at the WIPP site. These experiments are the bin-scale and alcove tests to be conducted by Sandia National Laboratories (SNL). Prior to conducting these experiments, the waste to be used in these tests needs to be characterized to provide data on the initial conditions for these experiments. This characterization is referred to as the Pretest Characterization of WIPP Experimental Waste, and is also expected to provide input to other programmatic efforts related to waste characterization. The purpose of this paper is to describe the pretest waste characterization activities currently in progress for the WIPP bin-scale waste, and to discuss the program plan and specific analytical protocols being developed for this characterization. The relationship between different programs and documents related to waste characterization efforts is also highlighted in this paper

  17. Analysis report for WIPP colloid model constraints and performance assessment parameters

    Energy Technology Data Exchange (ETDEWEB)

    Mariner, Paul E.; Sassani, David Carl

    2014-03-01

    An analysis of the Waste Isolation Pilot Plant (WIPP) colloid model constraints and parameter values was performed. The focus of this work was primarily on intrinsic colloids, mineral fragment colloids, and humic substance colloids, with a lesser focus on microbial colloids. Comments by the US Environmental Protection Agency (EPA) concerning intrinsic Th(IV) colloids and Mg-Cl-OH mineral fragment colloids were addressed in detail, assumptions and data used to constrain colloid model calculations were evaluated, and inconsistencies between data and model parameter values were identified. This work resulted in a list of specific conclusions regarding model integrity, model conservatism, and opportunities for improvement related to each of the four colloid types included in the WIPP performance assessment.

  18. The WIPP journey to waste receipt

    International Nuclear Information System (INIS)

    Barnes, G.J.; Whatley, M.E.

    1997-01-01

    In the early 1970s the federal government selected an area in southeastern New Mexico containing large underground salt beds as potentially suitable for radioactive waste disposal. An extensive site characterization program was initiated by the federal government. This site became the Waste Isolation Pilot Plant, better known as WIPP. It is now 1997, over two decades after the initial selection of the New Mexico site as a potential radioactive waste repository. Numerous scientific studies, construction activities, and environmental compliance documents have been completed. The US Department of Energy (DOE) has addressed all relevant issues regarding the safety of WIPP and its ability to isolate radioactive waste from the accessible environment. Throughout the last two decades up to the present time, DOE has negotiated through a political, regulatory, and legal maze with regard to WIPP. New regulations have been issued, litigation initiated, and public involvement brought to the forefront of the DOE decision-making process. All of these factors combined to bring WIPP to its present status--at the final stages of working through the licensing requirements for receipt of transuranic (TRU) waste for disposal. Throughout its history, the DOE has stayed true to Congress' mandates regarding WIPP. Steps taken have been necessary to demonstrate to Congress, the State of New Mexico, and the public in general, that the nation's first radioactive waste repository will be safe and environmentally sound. DOE's compliance demonstrations are presently under consideration by the cognizant regulatory agencies and DOE is closer than ever to waste receipt. This paper explores the DOE's journey towards implementing a permanent disposal solution for defense-related TRU waste, including major Congressional mandates and other factors that contributed to program changes regarding the WIPP project

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

    International Nuclear Information System (INIS)

    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

  20. Basic data report for drillhole WIPP 12 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    1982-10-01

    WIPP 12 is a borehole drilled in eastern Eddy County, New Mexico, to investigate the stratigraphy, structure and lithology in the WIPP area. WIPP 12 was drilled in section 17, T22S,R31E, between November 9 and December 7, 1978. The hole was drilled to a depth of 2785.8 ft. It encountered from top to bottom, 16.2 ft of sand, 3 ft of Mescalero Caliche and 9.6 ft of the Gatuna Formation, all of Quaternary age; 138.2 ft of the Triassic Santa Rosa Formation, 483 ft of the Dewey Lake Red Beds, 326 ft of the Rustler Formation, 1771.5 ft of the Salado Formation, and 48.3 ft of the Castile Formation, all of Permian age. Cores or cuttings were obtained for the entire hole. A suite of geophysical logs, including neutron gamma and density curves, was run to the full depth of WIPP 12. The borehole demonstrated that the elevation of the top of the Castile is about 160' above the same horizon in ERDA 9. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  1. Construction quality assurance program plan for the WIPP project, Carlsbad, NM

    International Nuclear Information System (INIS)

    1987-05-01

    The purpose of this plan is to describe the Quality Assurance (QA) Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Major Project Participants: the Architect-Engineer (Bechtel), the Construction Manager (US Army Corps of Engineers), the Scientific Advisor (Sandia National Laboratory), and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the construction, including site evaluation, design, and turnover phases of WIPP. Other work in progress during the same period is controlled by DOE documents applicable to that work effort. The prime responsibility for ensuring the quality of construction rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Construction Manager, the Construction Contractors, the Management and Operating Contractor, and the Architect-Engineer. Inspection and burden of proof of acceptability rests with the Construction Contractor as defined by the technical provisions of the contract and as otherwise specified by the DOE WIPP Project Office on an individual work-package basis. To the maximum extent possible, acceptance of work will be based upon first-hand witnessing by the Construction Manager and other representatives of the DOE organization

  2. WIPP site and vicinity geological field trip

    International Nuclear Information System (INIS)

    Chaturvedi, L.

    1980-10-01

    The Environmental Evaluation Group (EEG) is conducting an assessment of the radiological health risks to people from the Waste Isolation Pilot Plant (WIPP). As a part of this work, EEG is making an effort to improve the understanding of those geological issues concerning the WIPP site which may affect the radiological consequences of the proposed repository. One of the important geological issues to be resolved is the timing and the nature of the dissolution processes which may have affected the WIPP site. EEG organized a two-day conference of geological scientists, titled Geotechnical Considerations for Radiological Hazard Assessment of WIPP on January 17-18, 1980. During this conference, it was realized that a field trip to the site would further clarify the different views on the geological processes active at the site. The field trip of June 16-18, 1980 was organized for this purpose. This report provides a summary of the field trip activities along with the participants post field trip comments. Important field stops are briefly described, followed by a more detailed discussion of critical geological issues. The report concludes with EEG's summary and recommendations to the US Department of Energy for further information needed to more adequately resolve concerns for the geologic and hydrologic integrity of the site

  3. Reaching out to multiple stake holders E.P.A.'s public outreach and communications program for the waste isolation pilot plant

    International Nuclear Information System (INIS)

    Ferguson, R.; Malina, C.

    2001-01-01

    In October 1992, Congress enacted the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act which gave the U.S. Environmental Protection Agency (EPA) significant new responsibilities for overseeing the U.S. Department of Energy's (DOE) activities at the WIPP. The WIPP, which is designed to safely contain radioactive waste for at least 10 000 years, is located near Carlsbad, New Mexico, and is the world's first geological disposal facility for transuranic waste. In May 1998, EPA determined that the WIPP will safely contain transuranic waste, which is generated as a result of the U.S. nuclear weapons program, because DOE demonstrated that the facility will comply with the Agency's radioactive waste disposal standards. EPAS's decision allowed the DOE to begin disposing radioactive waste in the WIPP. As of October 2000, the WIPP has received over 75 shipments of transuranic radioactive waste. In implementing its new responsibilities, EPA committed to conducting an open public process that includes interaction with all interested parties. EPA believes that a successful communications and consultation program facilitates the regulatory oversight process and promotes sound public policy decisions. As a first step in meeting its commitment to an open public process, EPA conducted a public consultation and communication 'needs assessment'. The purpose of this assessment was to obtain input from citizen and environmental groups and the public on their key concerns about EPA's role and responsibilities at the WIPP, as well as to determine the best methods for communicating with them. Throughout the WIPP certification process, EPA provided opportunities for public involvement beyond those required in typical U.S. regulatory programs. Doing this, we believe, increased the public's understanding of EPA's role and responsibilities with respect to the WIPP project, enabled the public to make informed decisions about the project by increasing their knowledge about radiation and it

  4. Performance Demonstration Program Plan for the WIPP Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-02-01

    The Performance Demonstration Program is designed to ensure that compliance with the Quality Assurance Objective, identified in the Quality Assurance Program Plan for the WIPP Experimental-Waste Characterization Program (QAPP), is achieved. This Program Plan is intended for use by the WPO to assess the laboratory support provided for the characterization of WIPP TRU waste by the storage/generator sites. Phase 0 of the Performance Demonstration Program encompasses the analysis of headspace gas samples for inorganic and organic components. The WPO will ensure the implementation of this plan by designating an independent organization to coordinate and provide technical oversight for the program (Program Coordinator). Initial program support, regarding the technical oversight and coordination functions, shall be provided by the USEPA-ORP. This plan identifies the criteria that will be used for the evaluation of laboratory performance, the responsibilities of the Program Coordinator, and the responsibilities of the participating laboratories. 5 tabs

  5. US EPA's experiences implementing environmental safety standards at the Waste Isolation Pilot Plant - 16103

    International Nuclear Information System (INIS)

    Peake, R. Thomas; Byrum, Charles; Feltcorn, Ed; Lee, Raymond; Joglekar, Rajani; Ghose, Shankar; Eagle, Mike

    2009-01-01

    The U.S. Environmental Protection Agency (EPA or the Agency) developed environmental standards for the disposal of defense-related transuranic wastes for the U.S. Department of Energy's (DOE or the Department) Waste Isolation Pilot Plant (WIPP). EPA implements these standards for WIPP, which has been in operation for over ten years. The general environmental standards are set forth in the Agency's 40 CFR Part 191 Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes [1]. These standards are implemented by site-specific compliance criteria [2]. The WIPP Land Withdrawal Act requires DOE to submit a re-certification application every five years after the initial receipt of waste. DOE submitted the latest WIPP re-certification application in March 2009. For re-certification, DOE must identify changes that have occurred over the previous five years and analyze their impact on the potential long-term performance of the repository. Once EPA determines that the re-certification application is complete, the Agency has six months to review the application and make a final decision. During this review, EPA solicits and incorporates public comment where appropriate. During the first re-certification in 2004, several stakeholder groups brought up issues (e.g., karst) that were addressed in the original certification. EPA has received comments again raising some of these same issues for the 2009 re-certification. In addition, DOE must submit proposed changes to the WIPP repository to EPA for review and approval. This paper describes selected issues of concern to WIPP and highlights interactions between EPA as the regulatory authority and DOE as the implementing organization. In general EPA's experience points out the importance of communication, documentation and the regulator's responsibility in determining 'how much is enough'. (authors)

  6. WIPP Waste Characterization: Implementing Regulatory Requirements in the Real World

    International Nuclear Information System (INIS)

    Cooper Wayman, J.D.; Goldstein, J.D.

    1999-01-01

    It is imperative to ensure compliance of the Waste Isolation Pilot Project (WIPP) with applicable statutory and regulatory requirements. In particular, compliance with the waste characterization requirements of the Resource Conservation and Recovery Act (RCRA) and its implementing regulation found at 40 CFR Parts 262,264 and 265 for hazardous and mixed wastes, as well as those of the Atomic Energy Act of 1954, as amended, the Reorganization Plan No. 3 of 1970, the Nuclear Waste Policy Act of 1982, as amended, and the WIPP Land Withdrawal Act, as amended, and their implementing regulations found at 40 CFR Parts 191 and 194 for non-mixed radioactive wastes, are often difficult to ensure at the operational level. For example, where a regulation may limit a waste to a certain concentration, this concentration may be difficult to measure. For example, does the definition of transuranic waste (TRU) as 100 nCi/grain of alpha-emitting transuranic isotopes per gram of waste mean that the radioassay of a waste must show a reading of 100 plus the sampling and measurement error for the waste to be a TRU waste? Although the use of acceptable knowledge to characterize waste is authorized by statute, regulation and DOE Orders, its implementation is similarly beset with difficulty. When is a document or documents sufficient to constitute acceptable knowledge? What standard can be used to determine if knowledge is acceptable for waste characterization purposes? The inherent conflict between waste characterization regulatory requirements and their implementation in the real world, and the resolution of this conflict, will be discussed

  7. WIPP's Hazardous Waste Facility Permit Renewal Application

    International Nuclear Information System (INIS)

    Most, W.A.; Kehrman, R.F.

    2009-01-01

    Hazardous waste permits issued by the New Mexico Environment Department (NMED) have a maximum term of 10-years from the permit's effective date. The permit condition in the Waste Isolation Pilot Plant's (WIPP) Hazardous Waste Facility Permit (HWFP) governing renewal applications, directs the Permittees to submit a permit application 180 days prior to expiration of the Permit. On October 27, 1999, the Secretary of the NMED issued to the United States Department of Energy (DOE), the owner and operator of WIPP, and to Washington TRU Solutions LLC (WTS), the Management and Operating Contractor and the cooperator of WIPP, a HWFP to manage, store, and dispose hazardous waste at WIPP. The DOE and WTS are collectively known as the Permittees. The HWFP is effective for a fixed term not to exceed ten years from the effective date of the Permit. The Permittees may renew the HWFP by submitting a new permit application at least 180 calendar days before the expiration date, of the HWFP. The Permittees are not proposing any substantial changes in the Renewal Application. First, the Permittees are seeking the authority to dispose of Contact-Handled and Remote-Handled TRU mixed waste in Panel 8. Panels 4 through 7 have been approved in the WIPP Hazardous Waste Facility Permit as it currently exists. No other change to the facility or to the manner in which hazardous waste is characterized, managed, stored, or disposed is being requested. Second, the Permittees also seek to include the Mine Ventilation Rate Monitoring Plan, as Attachment Q in the HWFP. This Plan has existed as a separate document since May 2000. The NMED has requested that the Plan be submitted as part of the Renewal Application. The Permittees have been operating to the Mine Ventilation Rate Monitoring Plan since the Plan was submitted. Third, some information submitted in the original WIPP RCRA Part B Application has been updated, such as demographic information. The Permittees will submit this information in the

  8. Certifying the Waste Isolation Pilot Plant: Lessons Learned from the WIPP Experience

    International Nuclear Information System (INIS)

    Anderson, D.R.; Chu, Margaret S.Y.; Froehlich, Gary K.; Howard, Bryan A.; Howarth, Susan M.; Larson, Kurt W.; Pickering, Susan Y.; Swift, Peter N.

    1999-01-01

    In May 1998, the US Environmental Protection Agency (EPA) certified the US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) as being in compliance with applicable long-term regulations governing the permanent disposal of spent nuclear fuel, high-level, and transuranic radioactive wastes. The WIPP is the first deep geologic repository in the US to have successfully demonstrated regulatory compliance with long-term radioactive waste disposal requirements. The first disposal of TRU waste at WIPP occurred on March 26, 1999. Many of the lessons learned during the WIPP Project's transition from site characterization and experimental research to the preparation of a successful application may be of general interest to other repository programs. During a four-year period (1992 to 1996), the WIPP team [including the DOE Carlsbad Area Office (CAO), the science advisor to CAO, Sandia National Laboratories (SNL), and the management and operating contractor of the WIPP site, Westinghouse Electric Corporation (WID)] met its aggressive schedule for submitting the application without compromising the integrity of the scientific basis for the long-term safety of the repository. Strong leadership of the CAO-SNL-WID team was essential. Within SNL, a mature and robust performance assessment (PA) allowed prioritization of remaining scientific activities with respect to their impact on regulatory compliance. Early and frequent dialog with EPA staff expedited the review process after the application was submitted. Questions that faced SNL are familiar to geoscientists working in site evaluation projects. What data should be gathered during site characterization? How can we know when data are sufficient? How can we know when our understanding of the disposal system is sufficient to support our conceptual models? What constitutes adequate ''validation'' of conceptual models for processes that act over geologic time? How should we use peer review and expert judgment? Other

  9. The WIPP research and development test program

    International Nuclear Information System (INIS)

    Tyler, L.D.

    1985-01-01

    The WIPP (Waste Isolation Pilot Plant) is a DOE RandD Facility for the purpose of developing the technology needed for the safe disposal of the United States defense-related radioactive waste. The in-situ test program is defined for the thermal-structural interactions, plugging and sealing, and waste package interactions in a salt environment. An integrated series of large-scale underground tests address the issues of both systems and long-term isolation performance of a repository

  10. Preliminary safety assessment of the WIPP facility

    International Nuclear Information System (INIS)

    Balestri, R.J.; Torres, B.W.; Pahwa, S.B.; Brannen, J.P.

    1979-01-01

    This paper summarizes the efforts to perform a safety assessment of the Waste Isolation Pilot Plant (WIPP) facility being proposed for southeastern New Mexico. This preliminary safety assessment is limited to a consequence assessment in terms of the dose to a maximally exposed individual as a result of introducing the radionuclides into the biosphere. The extremely low doses to the organs as a result of the liquid breach scenarios are contrasted with the background radiation

  11. WIPP site and vicinity geological field trip

    International Nuclear Information System (INIS)

    Chaturvedi, L.

    1980-10-01

    The Environmental Evaluation Group is conducting an assessment of the radiological health risks to people from the Waste Isolation Pilot Plant. As a part of this work, EEG is making an effort to improve the understanding of those geological issues concerning the WIPP site which may affect the radiological consequences of the proposed repository. One of the important geological issues to be resolved is the timing and the nature of the dissolution processes which may have affected the WIPP site. EEG organized a two-day conference of geological scientists, on January 17-18, 1980. On the basis of the January conference and the June field trip, EEG has formed the following conclusions: (1) it has not been clearly established that the site or the surrounding area has been attacked by deep dissolution to render it unsuitable for the nuclear waste pilot repository; (2) the existence of an isolated breccia pipe at the site unaccompanied by a deep dissolution wedge, is a very remote possibility; (3) more specific information about the origin and the nature of the brine reservoirs is needed. An important question that should be resolved is whether each encounter with artesian brine represents a separate pocket or whether these occurrences are interconnected; (4) Anderson has postulated a major tectonic fault or a fracture system at the Basin margin along the San Simon Swale; (5) the area in the northern part of the WIPP site, identified from geophysical and bore hole data as the disturbed zone, should be further investigated to cleary understand the nature and significance of this structural anomaly; and (6) a major drawback encountered during the discussions of geological issues related to the WIPP site is the absence of published material that brings together all the known information related to a particular issue

  12. The WIPP transportation system: Demonstrated readiness

    International Nuclear Information System (INIS)

    Ward, T.R.; Spooner, R.

    1991-01-01

    The Department of Energy (DOE) has developed an integrated transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites to the Waste Isolation Pilot Plant (WIPP). The system consists of a Type B container, a specially- designed trailer, a lightweight tractor, the DOE ''TRANSCOM'' vehicle tracking system, and uniquely qualified and highly-trained drivers. In June of 1989, the National Academy of Sciences reviewed the transportation system and concluded that: ''The system proposed for transportation of TRU waste to WIPP is safer than that employed for any other hazardous material in the United States today and will reduce risk to very low levels'' (emphasis added). The next challenge facing the DOE was demonstrating that this system was ready to transport the TRU waste to the WIPP site efficiently and in the safest manner possible. Not only did the DOE feel that is was necessary to convince itself that the system was safe, but also representatives of the 20 states through which it would travel

  13. The WIPP transportation system: Demonstrated readiness

    International Nuclear Information System (INIS)

    Ward, T.R.; Spooner, R.

    1991-01-01

    The Department of Energy (DOE) has developed an integrated transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites to the Waste Isolation Pilot Plant (WIPP). The system consists of a Type B container, a specially-designed trailer, a lightweight tractor, the DOE ''TRANSCOM'' vehicle tracing system, and uniquely qualified and highly-trained drivers. In June of 1989, the National Academy of Sciences reviewed the transportation system and concluded that: ''The system proposed for transportation of TRU waste to WIPP is safer than that employed for any other hazardous material in the United States today and will reduce risk to very low levels.'' The next challenge facing the DOE was demonstrating that this system was ready to transport the TRU waste to the WIPP site in the safest manner possible. Not only did the DOE feel that it was necessary to convince itself that the system was safe, but also representatives of the 23 states through which it traveled

  14. Basic data report for drillhole WIPP 32 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1980-11-01

    WIPP 32 is an exploratory borehole drilled to examine the subsurface at a small topographic high in Nash Draw. The borehole is located in east-central Eddy County, New Mexico, in NE 1/4 SE 1/4 Sec. 33, T.22S., R.29E. and was drilled in August, 1979. The hole was drilled to a depth of 390 feet, and encountered, from top to bottom, the Rustler Formation (166') and the upper Salado Formation (224'). Core was taken from 4 to 353 feet. Geophysical logs were run the full length of the hole to measure formation properties. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

  15. WIPP conceptual design report. Addendum L. Mine safety code review for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1977-06-01

    An initial review of New Mexico and Federal mining standards and regulations has been made to determine their applicability to the WIPP conceptual design. These standards and regulations are reviewed point by point and the enclosed listing includes comments and recommendations for those which will affect the design and/or eventual operations of WIPP. The majority of the standards, both federal and state, are standard safe mining practices. Those standards are listed which are thought should be emphasized for development of the design; also those that would increase the hazard risk by strict compliance. Because the WIPP facility is different in many respects from mines for which the regulations were intended, strict compliance in some respects would provide an increased hazard, while in other instances the regulations are less strict than is desirable. These are noted in the attached review

  16. The integrated in situ testing program for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Matalucci, R.V.

    1987-03-01

    The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) Project in southeastern New Mexico as a research and development (R and D) facility for examining the response of bedded (layered) salt to the emplacement of radioactive wastes generated from defense programs. The WIPP Experimental Program consists of a technology development program, including laboratory testing and theoretical analysis activities, and an in situ testing program that is being done 659 m underground at the project site. This experimental program addresses three major technical areas that concern (1) thermal/structural interactions, (2) plugging and sealing, and (3) waste package performance. To ensure that the technical issues involved in these areas are investigated with appropriate emphasis and timing, an in situ testing plan was developed to integrate the many activities and tasks associated with the technical issues of waste disposal. 5 refs., 4 figs

  17. Purchasing Supplies, Equipment and Services Under EPA Grants

    Science.gov (United States)

    EPA developed this guidance to help ensure you meet EPA requirements when making such necessary purchases. With very few exceptions, you must follow a competitive process when you use EPA grant funds to acquire equipment and professional services.

  18. 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.

  19. The Revised WIPP Passive Institutional Controls Program - A Conceptual Plan - 13145

    International Nuclear Information System (INIS)

    Patterson, Russ; Klein, Thomas; Van Luik, Abraham

    2013-01-01

    The Department of Energy/Carlsbad Field Office (DOE/CBFO) is responsible for managing all activities related to the disposal of TRU and TRU-mixed waste in the geologic repository, 650 m below the land surface, at WIPP, near Carlsbad, New Mexico. The main function of the Passive Institutional Controls (PIC's) program is to inform future generations of the long-lived radioactive wastes buried beneath their feet in the desert. For the first 100 years after cessation of disposal operations, the rooms are closed and the shafts leading underground sealed, WIPP is mandated by law to institute Active Institutional Controls (AIC's) with fences, gates, and armed guards on patrol. At this same time a plan must be in place of how to warn/inform the future, after the AIC's are gone, of the consequences of intrusion into the geologic repository disposal area. A plan was put into place during the 1990's with records management and storage, awareness triggers, permanent marker design concepts and testing schedules. This work included the thoughts of expert panels and individuals. The plan held up under peer review and met the requirements of the U.S. Environmental Protection Agency (EPA). Today the NEA is coordinating a study called the 'Preservation of Records, Knowledge and Memory (RK and M) Across Generations' to provide the international nuclear waste repository community with a guide on how a nuclear record archive programs should be approached and developed. CBFO is cooperating and participating in this project and will take what knowledge is gained and apply that to the WIPP program. At the same time CBFO is well aware that the EPA and others are expecting DOE to move forward with planning for the future WIPP PIC's program; so a plan will be in place in time for WIPP's closure slated for the early 2030's. The DOE/CBFO WIPP PIC's program in place today meets the regulatory criteria, but complete feasibility of implementation is questionable, and may not be in conformance

  20. Basic data report for Drillhole WIPP 28 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1979-08-01

    WIPP 28 was drilled in Nash Draw (NE 1/4, sec. 18, T.21S., R.31E.) in Eddy County, New Mexico, to determine subsurface stratigraphy and examine dissolution features above undisturbed salt in the Salado Formation. Determination of dissolution rates will refine previous estimates and provide short-term (geologically) rates for WIPP risk assessments. The borehole encountered, from top to bottom, Mescalero caliche (12 ft with fill material for pad), Dewey Lake Red Beds (203 ft), Rustler Formation (316 ft), and the upper 270 ft of the Salado Formation. A dissolution residue, 58 ft thick, is at the top of the Salado Formation overlying halite-rich beds. In addition to obtaining nearly continuous core from the surface to total depth (801 ft), geophysical logs were taken to measure acoustic velocities, density, radioactivity, and formation resistivity. An interpretive report on dissolution in Nash Draw will be based on combined borehole basin data, surface mapping, and laboratory analyses of Nash Draw rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt

  1. Basic data report for drillhole WIPP 19 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    1980-03-01

    WIPP 19 is an exploratory borehole whose objective was to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between April 6 and May 4, 1978. The hole was drilled to a depth of 1038.2 feet and encountered, from top to bottom, surficial Holocene deposits (7', including artificial fill for drill pad), the Mescalero caliche (7'), the Santa Rosa Sandstone (82'), the Dewey Lake Red Beds (494'), the Rustler Formation (315'), and the upper portion of the Salado Formation (143'). Cuttings were collected at 10-foot intervals. A suite of geophysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 19 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

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

    International Nuclear Information System (INIS)

    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

  3. Basic data report for drillhole WIPP 21 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1980-03-01

    WIPP 21 is an exploratory borehole whose objective is to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between May 24 and 26, 1978. The hole was drilled to a depth of 1046 feet and encountered, from top to bottom, surficial Holocene deposits (6', including artificial fill for drill pad), the Mescalero caliche (6'), the Santa Rosa Sandstone (34'), the Dewey Lake Red Beds (487'), the Rustler Formation (308'), and the upper portion of the Salado Formation (178'). Cuttings were collected at 10-foot intervals. A suite of goephysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 21 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

  4. Basic data report for drillhole WIPP 18 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1980-03-01

    WIPP 18 is an exploratory borehole whose objective is to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between March 14 and 30, 1978. The hole was drilled to a depth of 1060 feet and encountered, from top to bottom, surficial Holocene deposits (5', including artificial fill for drill pad), the Mescalero caliche (4'), the Santa Rosa Sandstone (129'), the Dewey Lake Red Beds (475'), the Rustler Formation (315'), and the upper portion of the Salado Formation (132'). Cuttings were collected at 10-foot intervals. A suite of geophysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 18 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

  5. Basic data report for drillhole WIPP 25 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1979-09-01

    WIPP 25 was drilled on the eastern edge of Nash Draw (SW 1/4, Sec. 15, T22S, R30E) in Eddy County, New Mexico, to determine subsurface stratigraphy and examine dissolution features above undisturbed salt in the Salado Formation. Determination of dissolution rates will refine previous estimates and provide short-term (geologically) rates for WIPP risk assessments. The borehole encountered, from top to bottom, Pleistocene sediments (17 ft with fill material for pad), Dewey Lake Red Beds (215 ft, Rustler Formation (333 ft, and 90 ft of the upper Salado Formation. A dissolution residue, 37 ft thick, is at the top of the Salado Formation overlying halite-rich beds. In addition to obtaining nearly continuous core from the surface to total depth (655 ft, geophysical logs were taken to measure acoustic velocities, density, radioactivity, and formation resistivity. An interpretive report on dissolution in Nash Draw will be based on combined borehole basin data, surface mapping, and laboratory analyses of Nash Draw rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt

  6. Basic data report for Drillhole WIPP 22 (Waste Isolation Pilot Plant, WIPP)

    International Nuclear Information System (INIS)

    1980-03-01

    WIPP 22 is an exploratory borehole whose objective is to determine the nature of the near-surface formations after seismic information indicated a possible fault. The borehole is located in section 20, T.22S., R.31E., in eastern Eddy County, New Mexico, and was drilled between March 14 and 30, 1978. The hole was drilled to a depth of 1448 feet and encountered, from top to bottom, surficial Holocene deposits (6', including artificial fill for drill pad), the Mescalero caliche (7'), the Santa Rosa Sandstone (68'), the Dewey Lake Red Beds (492'), the Rustler Formation (311'), and the upper portion of the Salado Formation (565'). Cuttings were collected at 10-foot intervals. A suite of geophysical logs was run to measure acoustic velocities, density, and radioactivity. On the basis of comparison with other geologic sections drilled in the area, the WIPP 22 section is a normal stratigraphic sequence and it does not show structural disruption. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes. The WIPP will also provide facilities to research interactions between high-level waste and salt

  7. Basic data report for drillhole WIPP 26 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1979-08-01

    WIPP 26 was drilled in Nash Draw (SE 1/4 NE 1/4, sec. 29, T22S, R30E) in Eddy County, New Mexico, to determine subsurface stratigraphy and examine dissolution features above undisturbed salt in the Salado Formation. Determination of dissolution rates will refine previous estimates and provide short-term (geologically) rates for WIPP risk assessments. The borehole encountered, from top to bottom, surficial deposits (10 ft with full materials for pad), Rustler Formation (299 ft), and the upper 194 ft of the Salado Formation. A dissolution residue, 11 ft thick, is at the top of the Salado Formation overlying halite-rich beds. In addition to obtaining nearly continuous core from the surface to total depth (503 ft), geophysical logs were taken to measure acoustic velocities, density, radioactivity, and formation resistivity. An interpretive report on dissolution in Nash Draw will be based on combined borehole basin data, surface mapping, and laboratory analyses of Nash Draw rocks and fluids. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic defense wastes and to then be converted to a repository. The WIPP will also provide research facilities for interactions between high-level waste and salt

  8. WIPP: construction and progress on a successful nuclear waste repository

    International Nuclear Information System (INIS)

    Cooper, W.R.; Sankey, C.A.

    1985-01-01

    The Department of Energy is constructing the Waste Isolation Pilot Plant (WIPP) in Southeastern New Mexico. The facility will retrievably store transuranic waste from defense activities of the United States and conduct experiments with Defense high-level waste which will be retrieved at the end of the experiments. This paper describes the progress and the present status of activities at WIPP. 4 refs

  9. WIPP Magnesium Oxide (MgO) - Planned Change Request

    Science.gov (United States)

    On April 10, 2006, the DOE submitted a planned change request pertaining to the amount of MgO emplaced in the WIPP repository. MgO is an engineered barrier that DOE included as part of the original WIPP Certification Decision.

  10. Achieving WIPP certification for software. A white paper

    International Nuclear Information System (INIS)

    Matthews, S.D.; Adams, K.; Twitchell, K.E.

    1998-07-01

    The NMT-1 and NMT-3 organizations within the Chemical and Metallurgical Research (CMR) facility at the Los Alamos National Laboratory (LANL) is working to achieve Waste Isolation Pilot Plant (WIPP) certification to enable them to transport their TRU waste to WIPP. In particular, the NMT-1 management is requesting support from the Idaho National Engineering and Environmental Laboratory (INEEL) to assist them in making the Laboratory Information Management System (LIMS) software WIPP certifiable. Thus, LIMS must be compliant with the recognized software quality assurance (SQA) requirements stated within the QAPD. Since the Idaho National Engineering and Environmental Laboratory (INEEL) has achieved WIPP certification, INEEL personnel can provide valuable assistance to LANL by sharing lessons learned and recommendations. Thus, this white paper delineates the particular software quality assurance requirements required for WIPP certification

  11. Science to compliance: The WIPP success story

    International Nuclear Information System (INIS)

    Howarth, S.M.; Chu, M.S.; Shephard, L.E.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed to provide in-depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. The success of the program, however, is defined by the regulator in the context of compliance with performance criteria, rather than by the in-depth technical understanding typical of most scientific programs. The WIPP project was successful in making a transformation from science to compliance by refocusing and redirecting programmatic efforts toward the singular goal of meeting regulatory compliance requirements while accelerating the submittal of the Compliance Certification Application (CCA) by two months from the April 1994 Disposal Decision Plan (DDP) date of December 1996, and by reducing projected characterization costs by more than 40%. This experience is unparalleled within the radioactive waste management community and has contributed to numerous lessons learned from which the entire community can benefit

  12. WIPP shaft seal system parameters recommended to support compliance calculations

    Energy Technology Data Exchange (ETDEWEB)

    Hurtado, L.D.; Knowles, M.K. [Sandia National Labs., Albuquerque, NM (United States); Kelley, V.A.; Jones, T.L.; Ogintz, J.B. [INTERA Inc., Austin, TX (United States); Pfeifle, T.W. [RE/SPEC, Inc., Rapid City, SD (United States)

    1997-12-01

    The US Department of Energy plans to dispose of transuranic waste at the Waste Isolation Pilot Plant (WIPP), which is sited in southeastern New Mexico. The WIPP disposal facility is located approximately 2,150 feet (650 m) below surface in the bedded halite of the Salado Formation. Prior to initiation of disposal activities, the Department of Energy must demonstrate that the WIPP will comply with all regulatory requirements. Applicable regulations require that contaminant releases from the WIPP remain below specified levels for a period of 10,000 years. To demonstrate that the WIPP will comply with these regulations, the Department of Energy has requested that Sandia National Laboratories develop and implement a comprehensive performance assessment of the WIPP repository for the regulatory period. This document presents the conceptual model of the shaft sealing system to be implemented in performance assessment calculations conducted in support of the Compliance Certification Application for the WIPP. The model was developed for use in repository-scale calculations and includes the seal system geometry and materials to be used in grid development as well as all parameters needed to describe the seal materials. These calculations predict the hydrologic behavior of the system. Hence conceptual model development is limited to those processes that could impact the fluid flow through the seal system.

  13. WIPP shaft seal system parameters recommended to support compliance calculations

    International Nuclear Information System (INIS)

    Hurtado, L.D.; Knowles, M.K.; Kelley, V.A.; Jones, T.L.; Ogintz, J.B.; Pfeifle, T.W.

    1997-12-01

    The US Department of Energy plans to dispose of transuranic waste at the Waste Isolation Pilot Plant (WIPP), which is sited in southeastern New Mexico. The WIPP disposal facility is located approximately 2,150 feet (650 m) below surface in the bedded halite of the Salado Formation. Prior to initiation of disposal activities, the Department of Energy must demonstrate that the WIPP will comply with all regulatory requirements. Applicable regulations require that contaminant releases from the WIPP remain below specified levels for a period of 10,000 years. To demonstrate that the WIPP will comply with these regulations, the Department of Energy has requested that Sandia National Laboratories develop and implement a comprehensive performance assessment of the WIPP repository for the regulatory period. This document presents the conceptual model of the shaft sealing system to be implemented in performance assessment calculations conducted in support of the Compliance Certification Application for the WIPP. The model was developed for use in repository-scale calculations and includes the seal system geometry and materials to be used in grid development as well as all parameters needed to describe the seal materials. These calculations predict the hydrologic behavior of the system. Hence conceptual model development is limited to those processes that could impact the fluid flow through the seal system

  14. Geotechnical Perspectives on the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Francke, Chris T.; Hansen, Frank D.; Knowles, M. Kathyn; Patchet, Stanley J.; Rempe, Norbert T.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first nuclear waste repository certified by the United States Environmental Protection Agency. Success in regulatory compliance resulted from an excellent natural setting for such a repository, a facility with multiple, redundant safety systems, and from a rigorous, transparent scientific and technical evaluation. The WIPP story, which has evolved over the past 25 years, has generated a library of publications and analyses. Details of the multifaceted program are contained in the cited references. Selected geotechnical highlights prove the eminent suitability of the WIPP to serve its congressionally mandated purpose

  15. Basic data report for drillhole WIPP 13 (Waste isolation pilot plant - WIPP)

    International Nuclear Information System (INIS)

    1979-10-01

    The borehole WIPP-13 was drilled in the SW 1/4 section 17, T22S, R31E of eastern Eddy County during July and August, 1978, to investigate the nature of a resistivity anomaly. The stratigraphic section was normal, consisting of 13 feet of Quaternary deposits (including artificial fill for drill pad), 53 feet of the Triassic Santa Rosa Sandstone, 451 feet of Dewey Lake Red Beds, 269 feet of the Rustler Formation and 179 feet of the upper member of the Salado Formation. Consecutive cores were taken from 570 to 595, 656 to 729, and 827 to 878 feet. Cuttings were collected at 10-foot intervals throughout the rest of the hole. Geophysical logs were run to aid in interpretation of the stratigraphy. The WIPP is to demonstrate (through limited operations) disposal technology for transuranic (TRU) defense wastes. Eventual conversion of the facility to a repository for TRU defense wastes is anticipated. The WIPP will also provide research facilities for interactions between high-level waste and salt

  16. Basic data report for Drillhole WIPP 14 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1982-08-01

    Borehole WIPP 14 is an exploratory well drilled in eastern Eddy County, New Mexico, in section 9, T22S,R31E. The borehole was drilled to a depth of 1000.0 ft measured from ground level. It penetrated, from top to bottom, 15.4 ft of Quaternary sands, 125.6 ft of the Triassic Santa Rosa Sandstone, and in the Permian strata, 497.7 ft of the Dewey Lake Red Beds, 312.9 ft of the Rustler Formation and 48.4 ft of the Upper Salado Formation. Seven hundred feet of the well were cored, at consecutive and nonconsecutive 10-ft intervals to a depth of 925.5 ft. Cuttings were collected where core was not taken. Density, gamma ray neutron and caliper logs were run the full depth of the hole. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  17. Analytical technology in support of the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Villareal, R.

    1994-01-01

    The need for long-term disposal of defense-related transuranic (TRU) wastes became apparent as the DOE recognized the environmental consequences of maintaining waste storage facilities designed for short or interim storage periods, not long-term storage. In 1979, Congress authorized the Waste Isolation Pilot Plant (WIPP), a research and development facility and full-scale pilot plant, to demonstrate the safe management, storage, and disposal of TRU wastes. Environmental Protection Agency (EPA) regulations governing disposal of TRU wastes in 40 CFR 191 require that TRU waste disposal systems be designed to limit migration of radionuclides to the accessible environment for 10,000 years based on performance assessment results. The actinide source-term waste test program (STTP) is an experiment designed to quantitatively measure the time-dependent concentrations of plutonium, uranium, neptunium, thorium, and americium in TRU wastes immersed in brines that simulate the chemistry that may occur in WIPP disposal rooms, partially or completely contacted with brines. The total concentration of each actinide in brine is the sum of its dissolved and colloidally suspended components, as determined by variables including pcH, oxidation-reduction potential (Eh), chelating and complexing agents, sorption capacity, and colloidal suspension capabilities. To determine the effect of influencing variables on the concentration of actinides in WIPP brines, several TRU waste types will be characterized and loaded into specially designed noncorrosive test containers filled with brine containing additives to enhance the action of each influencing variable. The test container brine and headspace gases will be analyzed

  18. The WIPP transportation system: Dedicated to safety

    International Nuclear Information System (INIS)

    Ward, T.; McFadden, M.

    1993-01-01

    When developing a transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites, the Department of Energy (DOE) recognized and addressed many challenges. Shipments of waste to the Waste Isolation Pilot Plant (WIPP) were to cover a twenty-five year period and utilize routes covering over twelve thousand miles in twenty-three states. Enhancing public safety by maximizing the payload, thus reducing the number of shipments, was the primary objective. To preclude the requirement for overweight permits, the DOE started with a total shipment weight limit of 80,000 pounds and developed an integrated transportation system consisting of a Type ''B'' package to transport the material, a lightweight tractor and trailer, stringent driver requirements, and a shipment tracking system referred to as ''TRANSCOM''

  19. Radionuclide transport in sandstones with WIPP brine

    International Nuclear Information System (INIS)

    Weed, H.C.; Bazan, F.; Fontanilla, J.; Garrison, J.; Rego, J.; Winslow, A.M.

    1981-02-01

    Retardation factors (R) have been measured for the transport of 3 H, /sup 95m/Tc, and 85 Sr in WIPP brine using St. Peter, Berea, Kayenta, and San Felipe sandstone cores. If tritium is assumed to have R=1, /sup 95m/Tc has R=1.0 to 1.3 and therefore is essentially not retarded. Strontium-85 has R = 1.0 to 1.3 on St. Peter, Berea, and Kayenta, but R=3 on San Felipe. This is attributed to sorption on the matrix material of San Felipe, which has 45 volume % matrix compared with 1 to 10 volume % for the others. Retardation factors (R/sub s/) for 85 Sr calculated from static sorption measurements are unity for all the sandstones. Therefore, the static and transport results for 85 Sr disagree in the case of San Felipe, but agree for St. Peter, Berea, and Kayenta

  20. Second reference calculation for the WIPP

    International Nuclear Information System (INIS)

    Branstetter, L.J.

    1985-03-01

    Results of the second reference calculation for the Waste Isolation Pilot Plant (WIPP) project using the dynamic relaxation finite element code SANCHO are presented. This reference calculation is intended to predict the response of a typical panel of excavated rooms designed for storage of nonheat-producing nuclear waste. Results are presented that include relevant deformations, relative clay seam displacements, and stress and strain profiles. This calculation is a particular solution obtained by a computer code, which has proven analytic capabilities when compared with other structural finite element codes. It is hoped that the results presented here will be useful in providing scoping values for defining experiments and for developing instrumentation. It is also hoped that the calculation will be useful as part of an exercise in developing a methodology for performing important design calculations by more than one analyst using more than one computer code, and for defining internal Quality Assurance (QA) procedures for such calculations. 27 refs., 15 figs

  1. WIPP/SRL in-situ tests

    International Nuclear Information System (INIS)

    Mamsey, W.G.

    1990-01-01

    The Materials Interface Interactions Test (MIIT) is the only in-situ program involving the burial of simulated high-level waste forms operating in the United States. Fifteen glass and waste form compositions and their proposed package materials, supplied by 7 countries, are interred in salt at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. A joint effort between Sandia National Laboratories and Savannah River Laboratory, MIIT is the largest international cooperative in-situ venture yet undertaken. The objective of the current study is to document the waste form compositions used in the MIIT program and then to examine compositional correlations based on structural considerations, bonding energies, and surface layer formation. These correlations show important similarities between the many different waste glass compositions studied world wide and suggest that these glasses would be expected to perform well and in a similar manner

  2. Second benchmark problem for WIPP structural computations

    International Nuclear Information System (INIS)

    Krieg, R.D.; Morgan, H.S.; Hunter, T.O.

    1980-12-01

    This report describes the second benchmark problem for comparison of the structural codes used in the WIPP project. The first benchmark problem consisted of heated and unheated drifts at a depth of 790 m, whereas this problem considers a shallower level (650 m) more typical of the repository horizon. But more important, the first problem considered a homogeneous salt configuration, whereas this problem considers a configuration with 27 distinct geologic layers, including 10 clay layers - 4 of which are to be modeled as possible slip planes. The inclusion of layering introduces complications in structural and thermal calculations that were not present in the first benchmark problem. These additional complications will be handled differently by the various codes used to compute drift closure rates. This second benchmark problem will assess these codes by evaluating the treatment of these complications

  3. In-Situ Testing and Performance Assessment of a Redesigned WIPP Panel Closure - 13192

    Energy Technology Data Exchange (ETDEWEB)

    Klein, Thomas [URS-Professional Solutions, 4021 National Parks Highway Carlsbad, NM 88220 (United States); Patterson, Russell [Department of Energy-Carlsbad Field Office, 4021 National Parks Highway Carlsbad, NM 88220 (United States); Camphouse, Chris; Herrick, Courtney; Kirchner, Thomas; Malama, Bwalya; Zeitler, Todd [Sandia National Laboratories-Carlsbad, 4100 National Parks Highway Carlsbad, NM 88220 (United States); Kicker, Dwayne [SM Stoller Corporation-Carlsbad, 4100 National Parks Highway Carlsbad, NM (United States)

    2013-07-01

    There are two primary regulatory requirements for Panel Closures at the Waste Isolation Pilot Plant (WIPP), the nation's only deep geologic repository for defense related Transuranic (TRU) and Mixed TRU waste. The Federal requirement is through 40 CFR 191 and 194, promulgated by the U.S. Environmental Protection Agency (EPA). The state requirement is regulated through the authority of the Secretary of the New Mexico Environment Department (NMED) under the New Mexico Hazardous Waste Act (HWA), New Mexico Statutes Annotated (NMSA) 1978, chap. 74-4-1 through 74-4-14, in accordance with the New Mexico Hazardous Waste Management Regulations (HWMR), 20.4.1 New Mexico Annotated Code (NMAC). The state regulations are implemented for the operational period of waste emplacement plus 30 years whereas the federal requirements are implemented from the operational period through 10,000 years. The 10,000 year federal requirement is related to the adequate representation of the panel closures in determining long-term performance of the repository. In Condition 1 of the Final Certification Rulemaking for 40 CFR Part 194, the EPA required a specific design for the panel closure system. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) has requested, through the Planned Change Request (PCR) process, that the EPA modify Condition 1 via its rulemaking process. The DOE has also requested, through the Permit Modification Request (PMR) process, that the NMED modify the approved panel closure system specified in Permit Attachment G1. The WIPP facility is carved out of a bedded salt formation 655 meters below the surface of southeast New Mexico. Condition 1 of the Final Certification Rulemaking specifies that the waste panels be closed using Option D which is a combination of a Salado mass concrete (SMC) monolith and an isolation/explosion block wall. The Option D design was also accepted as the panel closure of choice by the NMED. After twelve years of waste handling

  4. WIPP R and D in situ test program

    International Nuclear Information System (INIS)

    Tyler, L.D.

    1987-01-01

    The Waste Isolation Pilot Plant (WIPP) is a Department of Energy (DOE) RandD Facility for the purpose of developing the technology needed for the safe disposal of the United States' defense-related radioactive waste. The in situ test program focus is to provide the models and data to demonstrate the facility performance for isolation of waste at WIPP. The program is defined for the WIPP sealing system, thermal-structural interactions and waste package performance. A number of integrated large-scale underground tests have been operational since 1983 and are ongoing. The tests address the issues of both systems design and long-term isolation performance of the WIPP repository

  5. Environmental Impact Statement: Waste Isolation Pilot Plant (WIPP): Executive summary

    International Nuclear Information System (INIS)

    1980-10-01

    The purpose of this document is to provide a summary of the environmental impact statement for the Waste Isolation Pilot Plant (WIPP) project. The Draft Environmental Impact Statement for the WIPP was published by the US Department of Energy (DOE) in April 1979. This document was reviewed and commented on by members of the general public, private organizations, and governmental agencies. The Final Environmental Impact Statement was subsequently published in October, 1980. This summary is designed to assist decision-maker and interested individuals in reviewing the material presented in the environmental impact statement for the WIPP project. To make this material widely available, this summary is published in both Spanish and English. Additional, more detailed information concerning the environmental and safety consequences of the WIPP project is available in the Final Environmental Impact Statement. Written comments and public hearing comments on the Draft Environmental Impact Statement are available for review. 27 refs., 4 figs., 7 tabs

  6. Environmental monitoring and cooperative resource management at the WIPP site

    International Nuclear Information System (INIS)

    1992-01-01

    This poster session by the Environmental Monitoring Section of the US DOE Waste Isolation Pilot Plant is to demonstrate that the DOE is committed to sound environmental management. This WIPP poster session demonstrates radiological as well as nonradiological environmental monitoring activities conducted routinely at the WIPP. And how data collected prior to the WIPP being operational is used to establish a preoperational baseline for environmental studies in which the samples collected during the operational phase will be compared. Cooperative Resource Management is a relatively new concept for governments agencies. It allows two or more agencies the ability to jointly share in funding a program or project and yet both agencies can benefit from the outcome. These programs are usually a biological type study. The WIPP cooperative agreement between the US BLM, DOE and its contractors is to continue the ongoing documentation of the diversity of the Chihuahuan desert

  7. Conclusions regarding geotechnical acceptability of the WIPP site

    International Nuclear Information System (INIS)

    Weart, W.D.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP) was authorized by Congress in 1980 as an unlicensed research and development (R and D) facility to demonstrate the safe disposal of radioactive wastes arising from the defense activities and programs of the United States. WIPP is now being constructed in southeast New Mexico, using salt beds about 655 m below the surface of the ground. Construction of the full WIPP facility will not commence until a preliminary underground excavation phase, called Site and Preliminary Design Validation (SPDV), is satisfactorily concluded in the summer of 1983. This SPDV program permits confirmation of subsurface geology, in drifts at planned facility depth that extend for 1555 m in a north-south direction, and in the two vertical shafts that provide access to these drifts. The subsurface studies are nearing completion, and it is therefore appropriate to draw conclusions regarding the geotechnical acceptability of the WIPP site. Four geotechnical elements are discussed: dissolution, deformation, hydrologic regime, and natural resources

  8. Disposal of TRU Waste from the PFP in pipe overpack containers to WIPP Including New Security Requirements

    International Nuclear Information System (INIS)

    HOPKINS, A.M.

    2003-01-01

    The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site, or a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, hanford incinerator ash and Sand, Slag and Crucible (SS and C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP

  9. Test Plan: WIPP bin-scale CH TRU waste tests

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1990-08-01

    This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs

  10. Preoperational radiation surveillance of the WIPP project by EEG during 1992

    International Nuclear Information System (INIS)

    Kenney, J.W.

    1994-02-01

    The purpose of the EEG preoperational monitoring program is to document the existing concentrations of selected radionuclides in various environmental media collected from the vicinity of the WIPP site to provide a basis of comparison of any effects of future WT-PP operations. The basic methodology for conducting environmental surveillance both on-site and off-site was outlined by Spiegler (1984). This report represents a continuation of the EEG baseline data beginning in 1985, previously reported in EEG-43, EEG-47, EEG-49 and EEG-51. Such radionuclide baseline data are important in order to determine whether future WIPP operations with radioactive waste have affected concentrations of these radionuclides in the environment. EEG data are consistent with similar environmental measurements obtained by DOE beginning in 1985. Since late 1985, the EEG has collected or received as split samples 2 443 air filters with particulates, 202 water samples, 16 biota samples and 13 soil/sediment samples. A total of 5,946 specific radionuclide analyses have been performed on these samples. As reported previously by EEG (EEG-43, EEG-47, EEG-49 and EEG-51), observed concentrations of U-238 daughter radionuclides were not in equilibrium with the parent radionuclide in water samples. This observation is consistent with different radionuclide mobility in the environment. In a notice of proposed rule making for 40 CFR 141 (US EPA 1991), the Environmental Protection Agency (EPA) National Primary Drinking Water Regulations reflect this in the calculated activity-to-mass ratio of 1.3 pCi/μg of uranium using a geometric mean of the U-234:U-238 ratio in water supplies of 2.7. Ra-226 and Ra- 228 were reported in a number of water samples in concentrations similar to those previously published by EEG and DOE

  11. WIPP/SRL Program - characterization of samples for burial in WIPP

    International Nuclear Information System (INIS)

    Holtzscheiter, R.C.; Wicks, G.G.

    1984-01-01

    The laboratory studies described in this report characterize the performance and homogeneity of waste glass from a 2-ft-dia glass slice taken from a full-scale 2 ft by 10 ft canister filled with glass at TNX. The leaching performance of glass samples extracted from the slice was determined as a function of radial position and will be used in support of existing programs. The waste glass produced at TNX and used for the burial tests in WIPP was very homogeneous. The extent of glass leaching in brine (using standard MCC-1 leach tests and based on boron extraction) was 15X less than that of leaching in deionized water

  12. Waste Isolation Pilot Plant (WIPP) fact sheet

    International Nuclear Information System (INIS)

    1993-01-01

    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

  13. Basic data report for drillhole WIPP 15 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    1981-11-01

    WIPP 15 is a borehole drilled in Marformation.h, 1978, in section 18, T.23S., R. 35E. of south-central Lea County. The purpose of WIPP 15 was to examine fill in San Simon Sink in order to extract climatic information and to attempt to date the collapse of the sink. The borehole was cored to total depth (810.5 feet) and encountered, from top to bottom, Quaternary calcareous clay, marl and sand, the claystones and siltstones of the Triassic Santa Rosa Formation. Neutron and gamma ray geophysical logs were run to measure density and radioactivity. The sink was about 547 feet of Quaternary fill indicating subsidence and deposition. Diatomaceous beds exposed on the sink margin yielded samples dated by 14 C at 20,570 +- 540 years BP and greater than 32,000 years BP; these beds are believed stratigraphically equivalent to ditomaceous beds at 153 to 266 feet depth in the core. Aquatic fauna and flora from the upper 98 feet of core indicate a pluvial period (probably Tohokan) followed by an arid or very arid time before the present climate was established. Aquifer pump tests performed in the Quaternary sands and clays show transmissivities to be as high as 600 feet squared per day. As the water quality was good, the borehole was released to the lessee as a potential water well

  14. Basic data report for drillhole WIPP 15 (Waste Isolation Pilot Plant-WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1981-11-01

    WIPP 15 is a borehole drilled in Marformation.h, 1978, in section 18, T.23S., R. 35E. of south-central Lea County. The purpose of WIPP 15 was to examine fill in San Simon Sink in order to extract climatic information and to attempt to date the collapse of the sink. The borehole was cored to total depth (810.5 feet) and encountered, from top to bottom, Quaternary calcareous clay, marl and sand, the claystones and siltstones of the Triassic Santa Rosa Formation. Neutron and gamma ray geophysical logs were run to measure density and radioactivity. The sink was about 547 feet of Quaternary fill indicating subsidence and deposition. Diatomaceous beds exposed on the sink margin yielded samples dated by /sup 14/C at 20,570 +- 540 years BP and greater than 32,000 years BP; these beds are believed stratigraphically equivalent to ditomaceous beds at 153 to 266 feet depth in the core. Aquatic fauna and flora from the upper 98 feet of core indicate a pluvial period (probably Tohokan) followed by an arid or very arid time before the present climate was established. Aquifer pump tests performed in the Quaternary sands and clays show transmissivities to be as high as 600 feet squared per day. As the water quality was good, the borehole was released to the lessee as a potential water well.

  15. Large-scale dynamic compaction demonstration using WIPP salt: Fielding and preliminary results

    International Nuclear Information System (INIS)

    Ahrens, E.H.; Hansen, F.D.

    1995-10-01

    Reconsolidation of crushed rock salt is a phenomenon of great interest to programs studying isolation of hazardous materials in natural salt geologic settings. Of particular interest is the potential for disaggregated salt to be restored to nearly an impermeable state. For example, reconsolidated crushed salt is proposed as a major shaft seal component for the Waste Isolation Pilot Plant (WIPP) Project. The concept for a permanent shaft seal component of the WIPP repository is to densely compact crushed salt in the four shafts; an effective seal will then be developed as the surrounding salt creeps into the shafts, further consolidating the crushed salt. Fundamental information on placement density and permeability is required to ensure attainment of the design function. The work reported here is the first large-scale compaction demonstration to provide information on initial salt properties applicable to design, construction, and performance expectations. The shaft seals must function for 10,000 years. Over this period a crushed salt mass will become less permeable as it is compressed by creep closure of salt surrounding the shaft. These facts preclude the possibility of conducting a full-scale, real-time field test. Because permanent seals taking advantage of salt reconsolidation have never been constructed, performance measurements have not been made on an appropriately large scale. An understanding of potential construction methods, achievable initial density and permeability, and performance of reconsolidated salt over time is required for seal design and performance assessment. This report discusses fielding and operations of a nearly full-scale dynamic compaction of mine-run WIPP salt, and presents preliminary density and in situ (in place) gas permeability results

  16. Concentration of uranium in the drinking and surface water around the WIPP site

    International Nuclear Information System (INIS)

    Khaing, H.; Lemons, B.G.; Thakur, P.

    2016-01-01

    Activity concentration of uranium isotopes ( 238 U, 234 U and 235 U) were analyzed in drinking and surface water samples collected in the vicinity of the WIPP site using alpha spectroscopy. The purpose of this study was to investigate the changes in uranium concentrations (if any) in the vicinity of the WIPP site and whether the February 14, 2014 radiation release event at the WIPP had any detectable impact on the water bodies around the WIPP. (author)

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

    International Nuclear Information System (INIS)

    1993-08-01

    Volume IV contains the following attachments for Module IV: VOC monitoring plan for bin-room tests (Appendix D12); bin emission control and VOC monitoring system drawings; bin scale test room ventilation drawings; WIPP supplementary roof support system, underground storage area, room 1, panel 1, DOE/WIPP 91-057; and WIPP supplementary roof support system, room 1, panel 1, geotechnical field data analysis bi-annual report, DOE/WIPP 92-024

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

    International Nuclear Information System (INIS)

    Olona, D.; Sala, D.

    1993-01-01

    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

  19. Status and Growth of Underground Science at WIPP

    Science.gov (United States)

    Rempe, Norbert T.

    2008-10-01

    The science community is increasingly taking advantage of research opportunities in the government-owned Waste Isolation Pilot Plant (WIPP), 655m underground near Carlsbad, NM. Discoveries so far include viable bacteria, cellulose, and DNA in 250 million-year old salt, preserved in an ultra-low background-radiation setting. Supplementing the overburden's shielding against cosmic radiation, terrestrial background from the host formation is less than five percent that of average crustal rock. In the past, WIPP accommodated development and testing of neutral current detectors for the Sudbury Neutrino Observatory and dark matter research, and it currently hosts two experiments pursuing neutrino-less double-beta decay. That scientists can listen to whispers from the universe in proximity to megacuries of radioactive waste lends, of course, credibility to the argument that WIPP itself is very safe. Almost a century of regional petroleum and potash extraction history and more than three decades of WIPP studies have generated a comprehensive body of knowledge on geology, mining technology, rock mechanics, geochemistry, and other disciplines relevant to underground science. Existing infrastructure is being used and can be expanded to fit experimental needs. WIPP's exemplary safety and regulatory compliance culture, low excavating and operating cost, and the high probability of the repository operating at least another 40 years make its available underground space attractive for future research and development. Recent proposals include low-photon energy counting to study internal dose received decades ago, investigations into ultra-low radiation dose response in cell cultures and laboratory animals (e.g., hormesis vs. linear no-threshold) and detectors for dark matter, solar and supernova neutrinos, and proton decay. Additional proposals compatible with WIPP's primary mission are welcome.

  20. Key Past and Present Hydrologic Issues at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Lappin, Allen R.; McKenna, Sean A.; Davies, Peter B.

    2000-01-01

    In May 1998, the U.S; Environmental Protection Agency (EPA) certified the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) to be in compliance with applicable portions of regulations governing the permanent disposal of radioactive wastes. The step was accomplished after 24 years of effort by Sandia National Laboratories, extending from initial site selection, through extensive site characterization and under-ground experimentalization to evaluation and demonstration of regulatory compliance. The strong focus on regulatory compliance extended over approximately five years, culminating in DOE's submittal of a Compliance Certification Application (CCA) in October, 1996. Specific lessons learned from the WIPP'S transition from site characterization/experimental research to a successful regulatory compliance application may be of general interest to participants in other repository problems. In summary, the three examples considered in this paper indicate that: It is critical that site-characterization and performance-assessment (PA) activities in a repository project advance through multiple iterative interactions. This is because there are parallel paths of evolution-within a projecy On one hand, there is a natural development in the conceptual understanding of the site and repository geology, hydrology, and geochemistry over time, as well as a normal increase in the roles of regulatory/safety issues relative to technical issues. On the other hand there is ongoing evolution in numerical-modeling, experimental, and PA techniques, as well as in understanding of the insights gained from these activities. However, even if conceptual models do not change, the modeling and documentation techniques and detailed logic supporting these models will change; as additional relevant information is collected within or outside the project. Some issues related to general site-characterization or site-suitability will remain of interest, even after initial

  1. Site evaluation for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Hill, L.R.

    1979-01-01

    Preliminary site selection activities for the WIPP are complete now; these consisted primarily of national and regional studies over the past fifteen years, and resulted in selection of the WIPP study area for geological characterization. The work of geological characterization should be considered to have begun with the drilling of ERDA 9 at the center of the WIPP study area and the initiation of seismic reflection work on the site. That geological characterization, which is primarily oriented to provide specific data concerning the present geology of the site, was virtually complete in December, 1978, when the Geological Characterization Report was submitted to the Department of Energy; much basic information has been gathered indicating no major technical problems with the site as it is now understood. Studies of long-term processes which might affect a repository or have an effect on safety analyses will now be the major geotechnical activity for the WIPP site evaluation team, some of these activities are already underway. These studies will deal with the age of significant features and the rates and processes which produce those features. The information so gained will be useful in increasing the confidence in evaluation of the safety of a repository

  2. Evaluation of the proposed WIPP site in southeast New Mexico

    International Nuclear Information System (INIS)

    Weart, W.D.

    1979-01-01

    Five years of earth science characterization of the proposed Waste Isolation Pilot Plant (WIPP) site provide a high level of assurance that the area is satisfactory for development of a geologic repository. Ecological investigations and socioeconomic studies have indicated only relatively benign impacts will occur from construction, operation and long-term aspects of the repository

  3. WIPP: Lessons learned for state/DOE consultation and cooperation

    International Nuclear Information System (INIS)

    Neill, R.H.

    1986-01-01

    WIPP is intended to be a repository for permanent disposal of 6,200,000 cu ft of transuranic waste generated from the nation's defense programs. The waste is not fixed, up to 1% can be respirable and it is stored in conventional 17-C Type A Carbon steel drums with a design life of 20 years. (Storage began in 1970). The waste form is not fused in an insoluble glass matrix and there is no commitment by DOE for getters. The question arises of the need and desirability to perform experiments with high level wastes at WIPP. The original purpose in the Oct 1980 WIPP FIES stated ''...the experiments are not so much concerned with the WIPP itself, as they are with planning future high level waste repositories. They are to answer technical questions about the disposal of high level waste in bedded salt and to provide a valid demonstration of the concepts involved.'' The purpose of this paper is to provide information for RH TRU disposal and to generate scientific knowledge that may be helpful to others and not to demonstrate high level waste disposal

  4. Evaluation of the proposed WIPP site in southeast New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Weart, W.D.

    1979-01-01

    Five years of earth science characterization of the proposed Waste Isolation Pilot Plant (WIPP) site provide a high level of assurance that the area is satisfactory for development of a geologic repository. Ecological investigations and socioeconomic studies have indicated only relatively benign impacts will occur from construction, operation and long-term aspects of the repository.

  5. Proposed waste isolation pilot project (WIPP) and impacts in the state of New Mexico: a socio-economic analysis. Final report

    International Nuclear Information System (INIS)

    Cummings, R.D.; Burness, H.S.; Norton, R.D.

    1981-04-01

    This document is a final report for research conducted concerning the socio-economic impacts in the State of New Mexico that might attend the construction and operation of the proposed Waste Isolation Pilot Plant (WIPP). The proposed site for the WIPP, known as the Los Medanos site, is in Southeastern New Mexico's Eddy County, some 25 miles east of Carlsbad, New Mexico and some 40 miles from Hobbs, New Mexico, in adjacent Lea County. The purpose as set out in the US Department of Energy's environmental impact statements is for storage of TRU waste from the US defense program and the construction of a research and development area for experiments concerning the isolation of all types of nuclear waste in salt. The intended purpose of the study is to identify, measure (when possible) and assess the range of potential socio-economic impacts in the State that may be attributable to the WIPP. Every effort has been made by the authors to approach this task in an objective manner. In efforts to provide an objective analysis of the WIPP, however, particular attention was required in providing a comprehensive review of potential impacts. This means that however unlikely an impact might seem, the authors have purposely avoided pre-judging the potential magnitude of the impact and have applied their best efforts to measure it. On the other hnd, this study is not intended to provide a definitive calculation regarding the net balance of WIPP-related benefits and costs. To help ensure objectivity, two advisory boards, Technical Advisory Board and Public Advisory Board, were formed at the outset of the project for the purpose of providing periodic reviews of research efforts

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

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    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

  7. Grouts and concretes for the Waste Isolation Pilot Project (WIPP)

    International Nuclear Information System (INIS)

    Wakeley, L.D.

    1990-01-01

    The Structures Laboratory of the U.S. Army Engineer Waterways Experiment Station has conducted research on cement-based composites for the Waste Isolation Pilot Project (WIPP) since 1977, in cooperation with Sandia National Laboratories. Field testing requirements guided initial development of grouts. Concurrent and later laboratory studies explored the chemical stability and probable durability of these mixtures. Beginning in 1985, a series of small-scale seal performance tests at the WIPP prompted development of an expansive salt-saturated concrete. Important lessons learned from this ongoing work include: (1) carefully tailored mixtures can tolerate phase changes involving Ca, Al, and SO 4 , without loss of structural integrity; (2) handling and placement properties are probably more crucial to the mixtures than is exact phase composition; and (3) for the environment of a geologic repository, demonstrated chemical durability will be the best indicator of long-term performance

  8. Constitutive representation of damage development and healing in WIPP salt

    International Nuclear Information System (INIS)

    Chan, K.S.; Bodner, S.R.; Fossum, A.F.; Munson, D.E.

    1994-01-01

    There has been considerable interest in characterizing and modeling the constitutive behavior of rock salt with particular reference to long-term creep and creep failure. The interest is motivated by the projected use of excavated rooms in salt rock formations as repositories for nuclear waste. It is presumed that closure of those rooms by creep ultimately would encapsulate the waste material, resulting in its effective isolation. A continuum mechanics approach for treating damage healing is formulated as part of a constitutive model for describing coupled creep, fracture, and healing in rock salt. Formulation of the healing term is, described and the constitutive model is evaluated against experimental data of rock salt from the Waste Isolation Pilot Plant (WIPP) site. The results indicate that healing anistropy in WIPP salt can be modeled with an appropriate power-conjugate equivalent stress, kinetic equation, and evolution equation for damage healing

  9. Assessment of allowable transuranic activity levels for WIPP wastes

    International Nuclear Information System (INIS)

    1987-12-01

    This study provides a technical evaluation for the establishment of an upper limit on the transuranic content of waste packages to be received. To accomplish this, the predicted radiological performance of WIPP is compared to the radiological performance requirements applicable to WIPP. These performance requirements include radiation protection standards for both routine facility operations and credible operational accidents. These requirements are discussed in Chapter 2.0. From the margin between predicted performance and the performance requirements, the maximum allowable transuranic content of waste packages can then be inferred. Within the resulting compliance envelope, a waste acceptance criterion can be established that delineates the allowable level of transuranic radioactivity content for contact handled (CH) and remote handled (RH) waste packages. 13 refs., 8 tabs

  10. New Mexico Environmental Evaluation Group - experience in reviewing WIPP

    International Nuclear Information System (INIS)

    Neill, R.H.

    1983-01-01

    The purpose of the New Mexico Environmental Evaluation Group is to conduct an independent evaluation of the potential radiation exposure to people from WIPP--a radioactive waste facility intended to permanently dispose transuranic radioactive waste generated from the nation's nuclear weapons program. The concept of a State review of a proposed radioactive waste facility has been endorsed by both Federal and State legislative and executive agencies, and the experiences and interactions of the past four years to solve problems of this first-of-a-kind radioactive waste facility has led to many innovations in conflict resolution. The multidisciplinary Group's position is neither pro nor anti-WIPP and results are published and given broad dissemination to insure technical and public scrutiny of its work

  11. Comparative study of Waste Isolation Pilot Plant (WIPP) transportation alternatives

    International Nuclear Information System (INIS)

    1994-02-01

    WIPP transportation studies in the Final Supplement Environmental Impact Statement for WIPP are the baseline for this report. In an attempt to present the most current analysis, this study incorporates the most relevant data available. The following three transportation options are evaluated for the Disposal Phase, which is assumed to be 20 years: Truck shipments, consisting of a tractor and trailer, with three TRUPACT-IIs or one RH-72B; Regular commercial train shipments consisting of up to three railcars carrying up to 18 TRUPACT-IIs or up to six RH-72Bs; Dedicated train shipments consisting of a locomotive, an idle car, railcars carrying 18 TRUPACT-IIs or six RH-72Bs, another idle car, and a caboose or passenger car with an emergency response specialist. No other cargo is carried. This report includes: A consideration of occupational and public risks and exposures, and other environmental impacts; A consideration of emergency response capabilities; and An extimation of comparative costs

  12. Weatherization Innovation Pilot Program (WIPP): Technical Assistance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Hollander, A.

    2014-09-01

    The U.S. Department of Energy (DOE) Energy Efficiency and Renewable Energy (EERE) Weatherization and Intergovernmental Programs Office (WIPO) launched the Weatherization Innovation Pilot Program (WIPP) to accelerate innovations in whole-house weatherization and advance DOE's goal of increasing the energy efficiency and health and safety of low-income residences without the utilization of additional taxpayer funding. Sixteen WIPP grantees were awarded a total of $30 million in Weatherization Assistance Program (WAP) funds in September 2010. These projects focused on: including nontraditional partners in weatherization service delivery; leveraging significant non-federal funding; and improving the effectiveness of low-income weatherization through the use of new materials, technologies, behavior-change models, and processes.

  13. Los Alamos National Laboratory Develops ''Quick to WIPP'' Strategy

    International Nuclear Information System (INIS)

    Jones, R.; Allen, G.; Kosiewicz, S.; Martin, B.; LANL; Nunz, J.; Biedscheid, J.; Sellmer, T.; Willis, J.; Orban, J.; Liekhus, K.; Djordjevic, S.

    2003-01-01

    The Cerro Grande forest fire in May of 2000 and the terrorist events of September 11, 2001 precipitated concerns of the vulnerability of legacy contact-handled (CH), high-wattage transuranic (TRU) waste stored at Los Alamos National Laboratory (LANL). An analysis of the 9,100 cubic meters of stored CH-TRU waste revealed that 400 cubic meters or 4.5% of the inventory represented 61% of the risk. The analysis further showed that this 400 cubic meters was contained in only 2,000 drums. These facts and the question ''How can the disposition of this waste to the Waste Isolation Pilot Plant (WIPP) be accelerated?'' formed the genesis of LANL's Quick to WIPP initiative

  14. Comparative study of Waste Isolation Pilot Plant (WIPP) transportation alternatives

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    WIPP transportation studies in the Final Supplement Environmental Impact Statement for WIPP are the baseline for this report. In an attempt to present the most current analysis, this study incorporates the most relevant data available. The following three transportation options are evaluated for the Disposal Phase, which is assumed to be 20 years: Truck shipments, consisting of a tractor and trailer, with three TRUPACT-IIs or one RH-72B; Regular commercial train shipments consisting of up to three railcars carrying up to 18 TRUPACT-IIs or up to six RH-72Bs; Dedicated train shipments consisting of a locomotive, an idle car, railcars carrying 18 TRUPACT-IIs or six RH-72Bs, another idle car, and a caboose or passenger car with an emergency response specialist. No other cargo is carried. This report includes: A consideration of occupational and public risks and exposures, and other environmental impacts; A consideration of emergency response capabilities; and An extimation of comparative costs.

  15. HVAC fault tree analysis for WIPP integrated risk assessment

    International Nuclear Information System (INIS)

    Kirby, P.; Iacovino, J.

    1990-01-01

    In order to evaluate the public health risk from operation of the Waste Isolation Pilot Plant (WIPP) due to potential radioactive releases, a probabilistic risk assessment of waste handling operations was conducted. One major aspect of this risk assessment involved fault tree analysis of the plant heating, ventilation, and air conditioning (HVAC) systems, which comprise the final barrier between waste handling operations and the environment. 1 refs., 1 tab

  16. Test plan: Potash Core Test. WIPP experimental program borehole plugging

    International Nuclear Information System (INIS)

    Christensen, C.L.

    1979-09-01

    The Potash Core Test will utilize a WIPP emplaced plug to obtain samples of an in-situ cured plug of known mix constituents for bench scale testing. An earlier effort involved recovery at the salt horizon of Plug 217, a 17 year old plug in a potash exploration hole for bond testing, but the lack of particulars in the emplacement precluded significant determination of plug performance

  17. Permeability of WIPP Salt During Damage Evolution and Healing

    International Nuclear Information System (INIS)

    BODNER, SOL R.; CHAN, KWAI S.; MUNSON, DARRELL E.

    1999-01-01

    The presence of damage in the form of microcracks can increase the permeability of salt. In this paper, an analytical formulation of the permeability of damaged rock salt is presented for both initially intact and porous conditions. The analysis shows that permeability is related to the connected (i.e., gas accessible) volumetric strain and porosity according to two different power-laws, which may be summed to give the overall behavior of a porous salt with damage. This relationship was incorporated into a constitutive model, known as the Multimechanism Deformation Coupled Fracture (MDCF) model, which has been formulated to describe the inelastic flow behavior of rock salt due to coupled creep, damage, and healing. The extended model was used to calculate the permeability of rock salt from the Waste Isolation Pilot Plant (WIPP) site under conditions where damage evolved with stress over a time period. Permeability changes resulting from both damage development under deviatoric stresses and damage healing under hydrostatic pressures were considered. The calculated results were compared against experimental data from the literature, which indicated that permeability in damaged intact WIPP salt depends on the magnitude of the gas accessible volumetric strain and not on the total volumetric strain. Consequently, the permeability of WIPP salt is significantly affected by the kinetics of crack closure, but shows little dependence on the kinetics of crack removal by sintering

  18. Waste Isolation Pilot Plant (WIPP) site gravity survey and interpretation

    International Nuclear Information System (INIS)

    Barrows, L.J.; Fett, J.D.

    1983-04-01

    A portion of the WIPP site has been extensively surveyed with high-precision gravity. The main survey (in T22S, R31E) covered a rectangular area 2 by 4-1/3 mi encompassing all of WIPP site Zone II and part of the disturbed zone to the north of the site. Stations were at 293-ft intervals along 13 north-south lines 880 ft apart. The data are considered accurate to within a few hundredths of a milligal. Long-wavelength gravity anomalies correlate well with seismic time structures on horizons below the Castile Formation. Both the gravity anomalies and the seismic time structures are interpreted as resulting from related density and velocity variations within the Ochoan Series. Shorter wavelength negative gravity anomalies are interpreted as resulting from bulk density alteration in the vicinity of karst conduits. The WIPP gravity survey was unable to resolve low-amplitude, long-wavelength anomalies that should result from the geologic structures within the disturbed zone. It did indicate the degree and character of karst development within the surveyed area

  19. Actinide Solubility and Speciation in the WIPP [PowerPoint

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Donald T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-11-02

    The presentation begins with the role and need for nuclear repositories (overall concept, international updates (Sweden, Finland, France, China), US approach and current status), then moves on to the WIPP TRU repository concept (design, current status--safety incidents of February 5 and 14, 2014, path forward), and finally considers the WIPP safety case: dissolved actinide concentrations (overall approach, oxidation state distribution and redox control, solubility of actinides, colloidal contribution and microbial effects). The following conclusions are set forth: (1) International programs are moving forward, but at a very slow and somewhat sporadic pace. (2) In the United States, the Salt repository concept, from the perspective of the long-term safety case, remains a viable option for nuclear waste management despite the current operational issues/concerns. (3) Current model/PA prediction (WIPP example) are built on redundant conservatisms. These conservatisms are being addressed in the ongoing and future research to fill existing data gaps--redox control of plutonium by Fe(0, II), thorium (analog) solubility studies in simulated brine, contribution of intrinsic and biocolloids to the mobile concentration, and clarification of microbial ecology and effects.

  20. WIPP: a perspective from ten years of operating success - 16189

    International Nuclear Information System (INIS)

    Gregory, Phillip C.

    2009-01-01

    The Waste Isolation Pilot Plant (WIPP), located 35 miles east of Carlsbad, New Mexico, USA is the first and, to the author's knowledge, only facility in the world for the permanent disposal of defense related transuranic (TRU) waste. Soon after plutonium was first synthesized in 1940 by a team of scientists at the University of California Berkeley Laboratory, the need to find a permanent repository for plutonium contaminated waste was recognized due to the more than 24,000 year half-life of Plutonium-239 ( 239 Pu). In 1957 the National Academy of Sciences published a report recommending deep geological burial in bedded salt as a possible solution. However, more than 50 years passed before the solution was achieved when in 1999 WIPP received the first shipment of TRU waste from Los Alamos National Laboratory. Ten years later, more than 7,600 shipments of TRU waste have been disposed of in rooms mined in an ancient salt bed more than 2,000 feet underground. This paper provides a brief history of WIPP with an overview of the technical, regulatory, and political hurdles that had to be overcome before the idea of a permanent disposal facility became reality. The paper focuses primarily on the safe, uneventful transportation program that has moved 100,000- plus containers of TRU waste from various U.S. Department of Energy (DOE) generator and/or storage sites across the Unites States to southeastern New Mexico. (author)

  1. Actinide Solubility and Speciation in the WIPP [PowerPoint

    International Nuclear Information System (INIS)

    Reed, Donald T.

    2015-01-01

    The presentation begins with the role and need for nuclear repositories (overall concept, international updates (Sweden, Finland, France, China), US approach and current status), then moves on to the WIPP TRU repository concept (design, current status--safety incidents of February 5 and 14, 2014, path forward), and finally considers the WIPP safety case: dissolved actinide concentrations (overall approach, oxidation state distribution and redox control, solubility of actinides, colloidal contribution and microbial effects). The following conclusions are set forth: (1) International programs are moving forward, but at a very slow and somewhat sporadic pace. (2) In the United States, the Salt repository concept, from the perspective of the long-term safety case, remains a viable option for nuclear waste management despite the current operational issues/concerns. (3) Current model/PA prediction (WIPP example) are built on redundant conservatisms. These conservatisms are being addressed in the ongoing and future research to fill existing data gaps--redox control of plutonium by Fe(0, II), thorium (analog) solubility studies in simulated brine, contribution of intrinsic and biocolloids to the mobile concentration, and clarification of microbial ecology and effects.

  2. A coupled mechanical/hydrologic model for WIPP shaft seals

    International Nuclear Information System (INIS)

    Ehgartner, B.

    1991-06-01

    Effective sealing of the Waste Isolation Pilot Plant (WIPP) shafts will be required to isolate defense-generated transuranic wastes from the accessible environment. Shafts penetrate water-bearing hard rock formations before entering a massive creeping-salt formation (Salado) where the WIPP is located. Short and long-term seals are planned for the shafts. Short-term seals, a composite of concrete and bentonite, will primarily be located in the hard rock formations separating the water-bearing zones from the Salado Formation. These seals will limit water flow to the underlying long-term seals in the Salado. The long-term seals will consist of lengthly segments of initially unsaturated crushed salt. Creep closure of the shaft will consolidate unsaturated crushed salt, thereby reducing its permeability. However, water passing through the upper short-term seals and brine inherent to the salt host rock itself will eventually saturate the crushed salt and consolidation could be inhibited. Before saturating, portions of the crushed salt in the shafts are expected to consolidate to a permeability equivalent to the salt host rock, thereby effectively isolating the waste from the overlying water-bearing formations. A phenomenological model is developed for the coupled mechanical/hydrologic behavior of sealed WIPP shafts. The model couples creep closure of the shaft, crushed salt consolidation, and the associated reduction in permeability with Darcy's law for saturated fluid flow to predict the overall permeability of the shaft seal system with time. 17 refs., 6 figs., 1 tab

  3. The WIPP transportation system -- ''Safer than any other''

    International Nuclear Information System (INIS)

    Ward, T.R.; Spooner, R.

    1991-01-01

    The Department of Energy (DOE) has developed an integrated transportation system to transport transuranic (TRU) waste from ten widely dispersed generator sites to the Waste Isolation Pilot Plant (WIPP). The system consists of a Type B container, a specially designed trailer, a lightweight tractor, the DOE TRANSCOM satellite-based vehicle tracking system, and uniquely qualified and highly trained drivers. The DOE has demonstrated that this system is ready to transport the TRU waste to the WIPP site efficiently and safely. Since the system was put in place in November 1988, it has been repeatedly upgraded and enhanced to incorporate additional safety measures. In June of 1989, the National Academy of Sciences (NAS) reviewed the transportation system and concluded that ''the system proposed for transportation of TRU waste to WIPP is safer than that employed for any other hazardous material in the United States today and will reduce risk to very low levels'' (emphasis added). The NAS conclusion was made before the DOE implemented the Enhanced Driver Training Course for carrier drivers. The challenge facing the DOE was to examine the transportation system objectively and determine what additional improvements could be made to further enhance safety

  4. WIPP conceptual design report. Addendum M. Computer system and data processing requirements for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Young, R.

    1977-06-01

    Data-processing requirements for the Waste Isolation Pilot Plant (WIPP) dictate a computing system that can provide a wide spectrum of data-processing needs on a 24-hour-day basis over an indeterminate time. A computer system is defined as a computer or computers complete with all peripheral equipment and extensive software and communications capabilities, including an operating system, compilers, assemblers, loaders, etc., all applicable to real-world problems. The computing system must be extremely reliable and easily expandable in both hardware and software to provide for future capabilities with a minimum impact on the existing applications software and operating system. The computer manufacturer or WIPP operating contractor must provide continuous on-site computer maintenance (maintain an adequate inventory of spare components and parts to guarantee a minimum mean-time-to-repair of any portion of the computer system). The computer operating system or monitor must process a wide mix of application programs and languages, yet be readily changeable to obtain maximum computer usage. The WIPP computing system must handle three general types of data processing requirements: batch, interactive, and real-time. These are discussed. Data bases, data collection systems, scientific and business systems, building and facilities, remote terminals and locations, and cables are also discussed

  5. Preoperational radiation surveillance of the WIPP Project by EEG for the years 1993 - 1995

    Energy Technology Data Exchange (ETDEWEB)

    Kenney, J.W.; Gray, D.H.; Ballard, S.C. [Environmental Evaluation Group, Carlsbad, NM (United States)

    1998-03-01

    Average {sup 241}Am, {sup 239+240}Pu and {sup 238}Pu concentrations measured in ambient air near the Waste Isolation Pilot Plant (WIPP) site during 1993, 1994 and 1995 are consistent with similar data reported by the U.S. Environmental Protection Agency (EPA) and Los Alamos National Laboratory (LANL) for Espanola, Pojoaque and Santa Fe, New Mexico. Through the use of replicate analyses of matrix blanks minimum detectable activity (MDA), minimum detectable concentration (MDC) and action levels (ACTL) were established for the Environmental Evaluation Group (EEG) measurement system. Using MDA data from fixed air sampler (FAS) filters and conservative assumptions applied in the National Council on Radiation Protection and Measurements (NCRP) Report 123 (NCRP 1996), it is shown that the EEG sampling and measurement methodology is capable of detecting effluent air emissions which would produce a dose that is approximately 1000 times below the 40 CFR 191 Subpart A limit of 2.5E{sup -4} Sv/y (25 mrem/y). A similar calculation using the NCRP worksheet with storm water effluent MDCs found the EEG measurement program capable of detecting actinide emissions which would result in a dose that is approximately 10 times below the dose limits in 40 CFR 191 Subpart A and 40 CFR 61 Subpart H.

  6. Leveraging Radioactive Waste Disposal at WIPP for Science

    Science.gov (United States)

    Rempe, N. T.

    2008-12-01

    Salt mines are radiologically much quieter than other underground environments because of ultra-low concentrations of natural radionuclides (U, Th, and K) in the host rock; therefore, the Waste Isolation Pilot Plant (WIPP), a government-owned, 655m deep geologic repository that disposes of radioactive waste in thick salt near Carlsbad, New Mexico, has for the last 15 years hosted highly radiation-sensitive experiments. Incidentally, Nature started her own low background experiment 250ma ago, preserving viable bacteria, cellulose, and DNA in WIPP salt. The Department of Energy continues to make areas of the WIPP underground available for experiments, freely offering its infrastructure and access to this unique environment. Even before WIPP started disposing of waste in 1999, the Room-Q alcove (25m x 10m x 4m) housed a succession of small experiments. They included development and calibration of neutral-current detectors by Los Alamos National Laboratory (LANL) for the Sudbury Neutrino Observatory, a proof-of-concept by Ohio State University of a flavor-sensitive neutrino detector for supernovae, and research by LANL on small solid- state dark matter detectors. Two currently active experiments support the search for neutrino-less double beta decay as a tool to better define the nature and mass of the neutrino. That these delicate experiments are conducted in close vicinity to, but not at all affected by, megacuries of radioactive waste reinforces the safety argument for the repository. Since 2003, the Majorana collaboration is developing and testing various detector designs inside a custom- built clean room in the Room-Q alcove. Already low natural background readings are reduced further by segmenting the germanium detectors, which spatially and temporally discriminates background radiation. The collaboration also demonstrated safe copper electro-forming underground, which minimizes cosmogenic background in detector assemblies. The largest currently used experimental

  7. Origin of the brines near WIPP from the drill holes ERDA-6 and WIPP-12 based on stable isotope concentrations of hydrogen and oxygen

    International Nuclear Information System (INIS)

    Spiegler, P.; Updegraff, D.

    1983-03-01

    Pathways which might alter the isotopic compositions of deuterium and oxygen-18 meteoric water, seawaters, and in hydration waters in gypsum to the isotopic compositions of brines encountered at ERDA-6 and WIPP-12 are discussed. Present geologic conditions do not favor the alteration of the isotopic compositions of waters that exist near the WIPP site to those of the brines by these pathways. It is concluded that the brines encountered at ERDA-6 and WIPP-12 are probably derived from ancient ocean waters that have been isotopically enriched in oxygen-18 by exchange interaction with rock. The dehydration of gypsum as a process of origin of these brines cannot be ruled out

  8. EPA Administrative Enforcement Dockets

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EPA Administrative Enforcement Dockets database contains the electronic dockets for administrative penalty cases filed by EPA Regions and Headquarters. Visitors...

  9. Approach to calculating upper bounds on maximum individual doses from the use of contaminated well water following a WIPP repository breach. Report EEG-9

    International Nuclear Information System (INIS)

    Spiegler, P.

    1981-09-01

    As part of the assessment of the potential radiological consequences of the proposed Waste Isolation Pilot Plant (WIPP), this report evaluates the post-closure radiation dose commitments associated with a possible breach event which involves dissolution of the repository by groundwaters and subsequent transport of the nuclear waste through an aquifer to a well assumed to exist at a point 3 miles downstream from the repository. The concentrations of uranium and plutonium isotopes at the well are based on the nuclear waste inventory presently proposed for WIPP and basic assumptions concerning the transport of waste as well as treatment to reduce the salinity of the water. The concentrations of U-233, Pu-239, and Pu-240, all radionuclides originally emplaced as waste in the repository, would exceed current EPA drinking water limits. The concentrations of U-234, U-235, and U-236, all decay products of plutonium isotopes originally emplaced as waste, would be well below current EPA drinking water limits. The 50-year dose commitments from one year of drinking treated water contaminated with U-233 or Pu-239 and Pu-240 were found to be comparable to a one-year dose from natural background. The 50-year dose commitments from one year of drinking milk would be no more than about 1/5 the dose obtained from ingestion of treated water. These doses are considered upper bounds because of several very conservative assumptions which are discussed in the report

  10. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP). Attachments: Volume 4 of 4

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    Volume IV contains the following attachments for Module IV: VOC monitoring plan for bin-room tests (Appendix D12); bin emission control and VOC monitoring system drawings; bin scale test room ventilation drawings; WIPP supplementary roof support system, underground storage area, room 1, panel 1, DOE/WIPP 91-057; and WIPP supplementary roof support system, room 1, panel 1, geotechnical field data analysis bi-annual report, DOE/WIPP 92-024.

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

    International Nuclear Information System (INIS)

    1993-08-01

    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)

  12. A regional water balance for the WIPP site and surrounding area

    International Nuclear Information System (INIS)

    Hunter, R.L.

    1987-01-01

    A water balance or budget is developed as an accounting of the components of a closed hydrologic system. In the WIPP study area, water-budget techniques have previously been used to compute leakage from Lake Avalon and from potash refinery spoil ponds. A general expression for a closed hydrologic system is presented. In a developed area like the WIPP region, the water budget must include many usage factors, such as municipal or industrial pumpage. In the WIPP water-budget study area, inflows are precipitation, surface- and ground-water inflow, and the artificial addition of surface and ground water. Outflows are surface runoff, evaporation and transpiration, and ground-water outflow. Changes in storage in the WIPP region have also been documented. The WIPP water balance described here is based on a combination of long-term averages and figures for 1980. 12 refs., 5 figs., 1 tab

  13. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2012-01-01

    It saddens us deeply to learn of the passing away of Jean-Paul Diss who died suddenly on 7 June 2012 at his home.  A tribute can be read on the GAC-EPA site. * * * * * Information: http://gac-epa.org/ e-mail: gac-epa@gac-epa.org

  14. Environmental monitoring at the WIPP site CY 1976

    International Nuclear Information System (INIS)

    Brewer, L.W.; Metcalf, J.H.

    1977-08-01

    Measurements made in the WIPP study area indicate background exposure levels of 8-9 μR/hr. These measured data are in good agreement with calculated exposure rates (7.5-9.6 μrad/hr). Airborne gross beta concentrations, which were low (0.02 pCi/m 3 ), confirmed the presence of global fallout from the Chinese nuclear tests conducted in the atmosphere during the fall. The air-quality measurements, except for a few unexplained excursions, were less than State and/or Federal air-quality standards

  15. WIPP air-intake shaft disturbed-rock zone study

    International Nuclear Information System (INIS)

    Dale, T.; Hurtado, L.D.

    1996-01-01

    The disturbed-rock zone surrounding the air-intake shaft at the Waste Isolation Pilot Plant (WIPP) site was investigated to determine the extent and the permeability of the disturbed-rock zone as a function of radial distance from the 6.1 m diameter shaft, at different elevations within the Salado. Gas- and brine-permeability tests were performed in the bedded halite of the Salado formation at two levels within the air-intake shaft. The gas- and brine-permeability test results demonstrated that the radial distance to an undisturbed formation permeability of 1 x 10 -21 m 2 was less than 3.0 m

  16. A Monte Carlo procedure for the construction of complementary cumulative distribution functions for comparison with the EPA release limits for radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C.; Shiver, A.W.

    1994-10-01

    A Monte Carlo procedure for the construction of complementary cumulative distribution functions (CCDFs) for comparison with the US Environmental Protection Agency (EPA) release limits for radioactive waste disposal (40 CFR 191, Subpart B) is described and illustrated with results from a recent performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP). The Monte Carlo procedure produces CCDF estimates similar to those obtained with stratified sampling in several recent PAs for the WIPP. The advantages of the Monte Carlo procedure over stratified sampling include increased resolution in the calculation of probabilities for complex scenarios involving drilling intrusions and better use of the necessarily limited number of mechanistic calculations that underlie CCDF construction.

  17. A Monte Carlo procedure for the construction of complementary cumulative distribution functions for comparison with the EPA release limits for radioactive waste disposal

    International Nuclear Information System (INIS)

    Helton, J.C.; Shiver, A.W.

    1994-10-01

    A Monte Carlo procedure for the construction of complementary cumulative distribution functions (CCDFs) for comparison with the US Environmental Protection Agency (EPA) release limits for radioactive waste disposal (40 CFR 191, Subpart B) is described and illustrated with results from a recent performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP). The Monte Carlo procedure produces CCDF estimates similar to those obtained with stratified sampling in several recent PAs for the WIPP. The advantages of the Monte Carlo procedure over stratified sampling include increased resolution in the calculation of probabilities for complex scenarios involving drilling intrusions and better use of the necessarily limited number of mechanistic calculations that underlie CCDF construction

  18. Ensuring Software IP Cleanliness

    Directory of Open Access Journals (Sweden)

    Mahshad Koohgoli

    2007-12-01

    Full Text Available At many points in the life of a software enterprise, determination of intellectual property (IP cleanliness becomes critical. The value of an enterprise that develops and sells software may depend on how clean the software is from the IP perspective. This article examines various methods of ensuring software IP cleanliness and discusses some of the benefits and shortcomings of current solutions.

  19. Ensuring Software IP Cleanliness

    OpenAIRE

    Mahshad Koohgoli; Richard Mayer

    2007-01-01

    At many points in the life of a software enterprise, determination of intellectual property (IP) cleanliness becomes critical. The value of an enterprise that develops and sells software may depend on how clean the software is from the IP perspective. This article examines various methods of ensuring software IP cleanliness and discusses some of the benefits and shortcomings of current solutions.

  20. Ensuring effective project management

    International Nuclear Information System (INIS)

    Ward, J.N.

    1980-01-01

    A brief description is given of the organisation methods employed by the Bechtel Power Corporation, in their contract with Mississippi Power and Light Company for the design, construction and procurement activities for the Grand Gulf Nuclear Station. The aim is to ensure effective management, and good communications at all stages of construction, between the project team and the client. (U.K.)

  1. Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

    International Nuclear Information System (INIS)

    Martell, M.A.; Hansen, F.; Weiner, R.

    1998-01-01

    Use of nature's laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia

  2. Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

    Energy Technology Data Exchange (ETDEWEB)

    Martell, M.A.; Hansen, F.; Weiner, R.

    1998-10-01

    Use of nature`s laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia.

  3. WIPP [Waste Isolation Pilot Plant]/SRL in situ tests: Part 2, Pictorial history of MIIT [Materials Interface Interactions Tests] and final MIIT matrices, assemblies, and sample listings

    International Nuclear Information System (INIS)

    Wicks, G.G.; Weinle, M.E.; Molecke, M.A.

    1987-01-01

    In situ testing of Savannah River Plant [SRP] waste glass is an important component in ensuring technical and public confidence in the safety and effective performance of the wasteforms. Savannah River Laboratory [SRL] is currently involved in joint programs involving field testing of SRP waste in Sweden, Belgium, and the United Kingdom. Most recently, this in situ effort has been expanded to include the first field tests to be conducted in the United States, involving burial of a variety of simulated nuclear waste systems. This new effort, called the Materials Interface Interactions Tests or MIIT, is a program jointly conducted by Sandia National Laboratory/Waste Isolation Pilot Plant [WIPP] and SRL. Over 1800 samples, supplied by the United States, France, West Germany, Belgium, Canada, Japan, and the United Kingdom, were buried approximately 650m below the earth's surface in the salt geology at WIPP, near Carlsbad, New Mexico. The MIIT program is one of the largest cooperative efforts ever undertaken in the waste management field; the data produced from these tests are designed to benefit a wide cross-section of the waste management community. An earlier document provided an overview of the WIPP MIIT program and described its place in the waste glass assessment program at Savannah River. This document represents the second in this series and its objectives include: (1) providing a pictorial history of assembly and installation of wasteforms, metals, and geologic samples in WIPP; (2) providing 'finalized and completed' sample matrices for the entire 7-part MIIT program; (3) documenting final sample assemblies by the use of schematic drawings, including each sample, its orientation, and its environment; and (4) providing a complete listing of all samples and the means for managing analyses and resulting data

  4. WIPP Benchmark calculations with the large strain SPECTROM codes

    International Nuclear Information System (INIS)

    Callahan, G.D.; DeVries, K.L.

    1995-08-01

    This report provides calculational results from the updated Lagrangian structural finite-element programs SPECTROM-32 and SPECTROM-333 for the purpose of qualifying these codes to perform analyses of structural situations in the Waste Isolation Pilot Plant (WIPP). Results are presented for the Second WIPP Benchmark (Benchmark II) Problems and for a simplified heated room problem used in a parallel design calculation study. The Benchmark II problems consist of an isothermal room problem and a heated room problem. The stratigraphy involves 27 distinct geologic layers including ten clay seams of which four are modeled as frictionless sliding interfaces. The analyses of the Benchmark II problems consider a 10-year simulation period. The evaluation of nine structural codes used in the Benchmark II problems shows that inclusion of finite-strain effects is not as significant as observed for the simplified heated room problem, and a variety of finite-strain and small-strain formulations produced similar results. The simplified heated room problem provides stratigraphic complexity equivalent to the Benchmark II problems but neglects sliding along the clay seams. The simplified heated problem does, however, provide a calculational check case where the small strain-formulation produced room closures about 20 percent greater than those obtained using finite-strain formulations. A discussion is given of each of the solved problems, and the computational results are compared with available published results. In general, the results of the two SPECTROM large strain codes compare favorably with results from other codes used to solve the problems

  5. WIPP Salado hydrology program data report No. 1

    International Nuclear Information System (INIS)

    Saulnier, G.J. Jr.; Domski, P.S.; Palmer, J.B.; Roberts, R.M.; Stensrud, W.A.; Jensen, A.L.

    1991-05-01

    WIPP Salado Hydrology Program Data Report number-sign 1 presents hydrologic data collected during permeability tests of the Salado Formation performed from August 1988 through December 1989. Analysis and interpretation of the test data are presented in a separate report. The report presents the results of the drilling and testing of six boreholes drilled from the WIPP underground facility 655 m below ground surface in the Salado Formation. Permeability tests were conducted using multipacker test tools with inflatable packers to isolate borehole intervals to allow formation pore-pressure buildup and subsequent pulse-withdrawal tests. Test data include pressures and temperatures in brine-filled, packer-isolated test intervals and borehole-closure and axial test-tool-movement measurements. Permeability tests were performed after installing multipacker test tools in test boreholes, inflating the packers, and allowing pressures to build up in the isolated intervals. Pulse-withdrawal tests were performed after buildup pressures approached the apparent formation pore pressure. Pulse injections were sometimes performed to increase the fluid pressures in isolated intervals. Compliance tests were conducted in lengths of steel and stainless-steel casing to evaluate the mechanical performance of the multipacker test tools. The stainless-steel compliance-test chamber was installed with externally mounted thermocouples in a downward-angled borehole in Experimental Room 4. Compliance tests included leak tests and simulated pulse-injection and pulse-withdrawal sequences. 9 refs., 143 figs., 2 tabs

  6. PASS: a component of Desk Top PA for the WIPP

    International Nuclear Information System (INIS)

    Crawford, M.B.; Wilmot, R.D.; Galson, D.A.; Swift, P.N.; Fewell, M.E.

    1998-01-01

    There is a growing recognition internationally of the need to demonstrate comprehensiveness in order to build confidence in performance assessments (PAs) for radioactive waste disposal projects. This has resulted in a number of methodologies being developed to formalize the process of defining and documenting the decision basis that underlies a PA. Such methodologies include process influence diagrams and the rock engineering system (RES) matrix. However, these methodologies focus mainly on the conceptualization of the disposal system and do not provide a ready framework to document the decisions behind the model development and parameterization of the PA system. The Performance Assessment Support System (PASS) is a flexible electronic tool designed to increase the transparency and traceability of decision making in the entire PA process. An application of PASS has been developed for the Waste Isolation Pilot Plant (WIPP) where it forms an important component of Desk Top PA, a PC-based PA computational environment under development at Sandia National Laboratories to document, plan, and support management decisions and to assess performance for the WIPP recertification process. This desk-top PA environment is also aimed at providing scientifically-based decision support for assessing the performance of nuclear and hazardous waste management and environmental clean-up systems

  7. Effects of clay-seam behavior on WIPP repository design

    International Nuclear Information System (INIS)

    Stone, C.M.; Krieg, R.D.; Branstetter, L.J.

    1981-07-01

    The geology at the southeastern New Mexico WIPP site consists of bedded layers of rock salt, anhydrite, polyhalite, mixtures of those materials, and thin clay seams. In spite of their very small (0.005 m to 0.05 m) thickness, clay seams are important to structural characterization of the WIPP stratigraphy since slip might possibly take place across them. Results of a study to determine the effects of clay seam frictional slip on the closure of a well-defined drift configuration are described. A Mohr-Coulomb dry friction model was used to model the active clay seams. The main thrust of the study was to determine the effects of friction coefficient variability on drift closure. Results show that the drift closure varies by a factor of 3.0 over the range of friction coefficients studied. The maximum slip observed along any clay seam was 0.12 m. For values of μ > .7, virtually no slip occurs along any clay seam

  8. WIPP Compliance Certification Application calculations parameters. Part 1: Parameter development

    International Nuclear Information System (INIS)

    Howarth, S.M.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed, which provided in-depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. Nearly 1,500 parameters were developed using information gathered from this program; the parameters were input to numerical models for WIPP Compliance Certification Application (CCA) Performance Assessment (PA) calculations. The CCA probabilistic codes frequently require input values that define a statistical distribution for each parameter. Developing parameter distributions begins with the assignment of an appropriate distribution type, which is dependent on the type, magnitude, and volume of data or information available. The development of the parameter distribution values may require interpretation or statistical analysis of raw data, combining raw data with literature values, scaling of lab or field data to fit code grid mesh sizes, or other transformation. Parameter development and documentation of the development process were very complicated, especially for those parameters based on empirical data; they required the integration of information from Sandia National Laboratories (SNL) code sponsors, parameter task leaders (PTLs), performance assessment analysts (PAAs), and experimental principal investigators (PIs). This paper, Part 1 of two parts, contains a discussion of the parameter development process, roles and responsibilities, and lessons learned. Part 2 will discuss parameter documentation, traceability and retrievability, and lessons learned from related audits and reviews

  9. Towards ensuring gender equity.

    Science.gov (United States)

    Basu, A

    1996-01-01

    All people should participate in the development process. Many, however, remain excluded from the benefits of development. For example, women are privy to only a small share of developmental opportunities. The goals of equality, development, and peace were stated during the Fourth World Conference on Women held in Beijing in September 1995. The author considers whether women truly have equitable access to literacy, education, food, nutrition, health, employment, and the political and economic decision making process. She stresses that the goals pronounced at the Fourth World Conference on Women must be backed up with the necessary resources, including institutions established at the local, state, and national levels to ensure that the objectives are implemented and the implementation is monitored. The author further argues that in order for women to achieve equality with men, all girls must have access to primary and secondary schools; basic literacy is inadequate. Moreover, gender stereotyping must be avoided and gender sensitization ensured at all levels.

  10. Duality ensures modular covariance

    International Nuclear Information System (INIS)

    Li Miao; Yu Ming

    1989-11-01

    We show that the modular transformations for one point functions on the torus, S(n), satisfy the polynomial equations derived by Moore and Seiberg, provided the duality property of the model is ensured. The formula for S(n) is derived by us previously and should be valid for any conformal field theory. As a consequence, the full consistency conditions for modular invariance at higher genus are completely guaranteed by duality of the theory on the sphere. (orig.)

  11. Nuclear waste repository transparency technology test bed demonstrations at WIPP

    International Nuclear Information System (INIS)

    Betsill J, David; Elkins, Ned Z.; Wu, Chuan-Fu; Mewhinney, James D.; Aamodt, Paul

    2000-01-01

    Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ''The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic

  12. Prospects for regional groundwater contamination due to karst landforms in Mescalero caliche at the WIPP site near Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    Phillips, R.H.

    1987-01-01

    Plutonium from nuclear weapons production will be permanently buried in Permian salt beds at the Waste Isolation Pilot Plant (WIPP), located in the Nash Draw watershed. Overlying the salt beds are cavernous Rustler dolomite aquifers, the most likely flow paths for contaminated water from WIPP to the biosphere. Overlying the Rustler are sandstones, siltstones, Mescalero caliche, and windblown sand. The WIPP site contains thousands of closed topographic depressions. If some are karst features, the ability of WIPP to isolate nuclear waste cannot be demonstrated. A water balance and geochemical analysis of the Nash Draw watershed and nearby brine springs were undertaken to determine: (1) which Rustler aquifers discharge where, and in what quantities; (2) the rates of evapotranspiration and natural groundwater recharge; (3) the most likely discharge point for contaminated water from WIPP. Laguna Grande, a natural salt lake in Nash Draw, is the outlet for the Rustler dolomite aquifers and for plutonium contaminations from WIPP. The recharge time for the Rustler may be only 6 to 8 years. WIPP is unsuitable for nuclear waste isolation because: (1) Rustler groundwater flow paths and travel times are inherently unpredictable; (2) caliche and sandstones allow rainwater recharge of the Rustler; (3) pressurized brine underneath WIPP can carry dissolved waste up the WIPP shafts to the Rustler; (4) geologic barriers between the brine and WIPP are unreliable; and (5) WIPP is vulnerable to human intrusion

  13. Mechanical Modeling of a WIPP Drum Under Pressure

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Jeffrey A. [Sandia National Laboratories, Albuquerque, NM (United States)

    2014-11-25

    Mechanical modeling was undertaken to support the Waste Isolation Pilot Plant (WIPP) technical assessment team (TAT) investigating the February 14th 2014 event where there was a radiological release at the WIPP. The initial goal of the modeling was to examine if a mechanical model could inform the team about the event. The intention was to have a model that could test scenarios with respect to the rate of pressurization. It was expected that the deformation and failure (inability of the drum to contain any pressure) would vary according to the pressurization rate. As the work progressed there was also interest in using the mechanical analysis of the drum to investigate what would happen if a drum pressurized when it was located under a standard waste package. Specifically, would the deformation be detectable from camera views within the room. A finite element model of a WIPP 55-gallon drum was developed that used all hex elements. Analyses were conducted using the explicit transient dynamics module of Sierra/SM to explore potential pressurization scenarios of the drum. Theses analysis show similar deformation patterns to documented pressurization tests of drums in the literature. The calculated failure pressures from previous tests documented in the literature vary from as little as 16 psi to 320 psi. In addition, previous testing documented in the literature shows drums bulging but not failing at pressures ranging from 69 to 138 psi. The analyses performed for this study found the drums failing at pressures ranging from 35 psi to 75 psi. When the drums are pressurized quickly (in 0.01 seconds) there is significant deformation to the lid. At lower pressurization rates the deformation of the lid is considerably less, yet the lids will still open from the pressure. The analyses demonstrate the influence of pressurization rate on deformation and opening pressure of the drums. Analyses conducted with a substantial mass on top of the closed drum demonstrate that the

  14. Scientific studies in support of the Waste Isolation Pilot Plant (WIPP) repository

    International Nuclear Information System (INIS)

    Chu, M.S.Y.; Weart, W.D.

    1996-01-01

    The DOE submitted a Compliance Certification Application for WIPP in october, 1996. A critical part of this application was a Performance Assessment which predicts the cumulative radioactive release to the accessible environment over a time period of 10,000 years. Comparison of this predicted release to the EPA standard shows a comfortable margin of compliance. The scientific understanding that was critical to developing this assessment spans a broad range of geotechnical disciplines, and required a thorough understanding of the site's geology and hydrology. Evaluation of the geologic processes which are active in the site region establishes that there will be no natural breach of site integrity for millions of years, far longer than the 10,000 year regulatory period. Inadvertent human intrusion is, therefore, the only credible scenario to lead to potential radioactive release to the accessible environment. To substantiate this conclusion and to quantify these potential releases from human intrusion, it has been necessary to develop an understanding of the following processes: salt creep and shaft seal efficacy; gas generation from organic decomposition of waste materials and anoxic corrosion of metals in the waste and waste packages; solubilities for actinides in brine; fluid flow in Salado formation rocks, and hydrologic transport of actinides in the overlying dolomite aquifers. Other issues which had to be evaluated to allow definition of breach scenarios were brine reservoir occurrences and their associated reservoir parameters, consequences of mining over the repository, and drilling for natural resources in the vicinity of the repository. Results of all these studies will be briefly summarized in this paper

  15. EPA eXcats

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EPA eXcats is an enterprise-level data tracking application that provides management complaint tracking information for the EPA's Office of Civil Rights (OCR)...

  16. EPA Web Taxonomy

    Data.gov (United States)

    U.S. Environmental Protection Agency — EPA's Web Taxonomy is a faceted hierarchical vocabulary used to tag web pages with terms from a controlled vocabulary. Tagging enables search and discovery of EPA's...

  17. Toward Ensuring Health Equity

    DEFF Research Database (Denmark)

    Petkovic, Jennifer; Epstein, Jonathan; Buchbinder, Rachelle

    2015-01-01

    , the Evaluative Linguistic Framework for Questionnaires, developed to assess text quality of questionnaires. We also considered a study assessing cross-cultural adaptation with/without back-translation and/or expert committee. The results of this preconference work were presented to the equity working group......OBJECTIVE: The goal of the Outcome Measures in Rheumatology (OMERACT) 12 (2014) equity working group was to determine whether and how comprehensibility of patient-reported outcome measures (PROM) should be assessed, to ensure suitability for people with low literacy and differing cultures. METHODS......: The English, Dutch, French, and Turkish Health Assessment Questionnaires and English and French Osteoarthritis Knee and Hip Quality of Life questionnaires were evaluated by applying 3 readability formulas: Flesch Reading Ease, Flesch-Kincaid grade level, and Simple Measure of Gobbledygook; and a new tool...

  18. The Brine Sampling and Evaluation Program (PSEP) at WIPP

    International Nuclear Information System (INIS)

    Deal, D.E.; Roggenthen, W.M.

    1989-01-01

    The Permian salt beds of the WIPP facility are virtually dry. The amount of water present in the rocks exposed in the excavations that is free to migrate under pressure gradients was estimated by heating salt samples to 95 degrees C and measuring weight loss. Clear balite contains about 0.22 weight percent water and the more argillaceous units average about 0.75 percent. Measurements made since 1984 as part of the Brine Sampling and Evaluation Program (BSEP) indicate that small amounts of this brine can migrate into the excavations and does accumulate in the underground environment. Brine seepage into drillholes monitored since thy were drilled show that brine seepage decreases with time and that many have dried up entirely. Weeping of brine from the walls of the repository excavations also decreases after two or more years. Chemical analyses of brines shows that they are sodium-chloride saturated and magnesium-rich

  19. QA lessons learned for parameter control from the WIPP Project

    International Nuclear Information System (INIS)

    Richards, R.R.

    1998-01-01

    This paper provides a summary of lessons learned from experiences on the Waste Isolation Pilot Plant (WJPP) Project in implementation of quality assurance controls surrounding inputs for performance assessment analysis. Since the performance assessment (PA) process is inherent in compliance determination for any waste repository, these lessons-learned are intended to be useful to investigators, analysts, and Quality Assurance (QA) practitioners working on high level waste disposal projects. On the WIPP Project, PA analyses for regulatory-compliance determination utilized several inter-related computer programs (codes) that mathematically modeled phenomena such as radionuclide release, retardation, and transport. The input information for those codes are the parameters that are the subject of this paper. Parameters were maintained in a computer database, which was then queried electronically by the PA codes whenever input was needed as the analyses were run

  20. WIPP Facility Work Plan for Solid Waste Management Units

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2001-02-25

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

  1. Mineralogy in the Waste Isolation Pilot Plant (WIPP) facility stratigraphic horizon

    International Nuclear Information System (INIS)

    Stein, C.L.

    1985-09-01

    Forty-six samples were selected for this study from two cores, one extending 50 ft up through the roof of the WIPP facility and the other penetrating 50 ft below the facility floor. These samples, selected from approximately every other foot of core length, represent the major lithologies present in the immediate vicinity of the WIPP facility horizon: ''clean'' halite, polyhalitic halite, argillaceous halite, and mixed polyhalitic-argillaceous halite. Samples were analyzed for non-NaCl mineralogy by determining weight percents of water- and EDTA-insoluble residues, which were then identified by x-ray diffraction. In general, WIPP halite contains at most 5 wt % non-NaCl residue. The major mineral constituents are quartz, magnesite, anhydrite, gypsum, polyhalite, and clays. Results of this study confirm that, in previous descriptions of WIPP core, trace mineral quantities have been visually overestimated by approximately an order of magnitude. 9 refs., 5 figs., 5 tabs

  2. Geotechnical evaluation of the proposed WIPP site in southeast New Mexico

    International Nuclear Information System (INIS)

    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. The present area being proposed for the WIPP is the second such location in the Delaware Basin for which new site data have been developed; the first site proved geologically unacceptable. Ecologic and socioeconomic aspects have been investigated and extensive geophysical, geological and hydrologic studies have been conducted to allow an evaluation of site acceptability. Geotechnical aspects of site characterization are examined. These studies are now sufficiently complete that the site can be recommended for further development of the WIPP

  3. Effects of microbial processes on gas generation under expected WIPP repository conditions: Annual report through 1992

    International Nuclear Information System (INIS)

    Francis, A.J.; Gillow, J.B.

    1993-09-01

    Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term ( 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and underground workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation

  4. WIPP conceptual design report. Addendum G. Accident analysis for Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Shefelbine, H.C.; Metcalf, J.H.

    1977-06-01

    The types of accidents or risks pertinent to the Waste Isolation Pilot Plant (WIPP) are presented. Design features addressing these risks are discussed. Also discussed are design features that protect the public

  5. Ensuring food security

    Directory of Open Access Journals (Sweden)

    Valeriy Valentinovich Patsiorkovskiy

    2011-12-01

    Full Text Available This paper is devoted to the questions of further development of agricultural and food policy in the Russian Federation. The subject of in-depth consideration is the problem related to ensuring food safety. A critical review and analysis of major regulations in the field of food safety is made, including in the implementation of sanitary and epidemiological surveillance. The necessity of the expansion of measures to improve the statistics of food poisoning is grounded. The basic reasons for the spread of management practices of production and sale of food products that pose a threat to human life are revealed. The factors of unhindered penetration of local markets in the cities and the surrounding countrysides with counterfeiting, smuggling and production of global junk food manufacturers and consumer goods are defined. A systematic view is put on the problems of food production in the private farms, ways to limit direct access to the market of food and food raw materials, which production was not controlled and who have not passed state registration, are suggested. One of these problems is creation of independent industrial structures that link production and sales of small-scale sector goods.

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

    International Nuclear Information System (INIS)

    1993-01-01

    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

  7. Recent developments in the conceptual geologic and hydrologic understanding of the WIPP site, Southeastern New Mexico

    International Nuclear Information System (INIS)

    Lappin, A.R.

    1987-01-01

    Hydrologic and geochemical characterization of the WIPP site has progressed significantly since the 1980 WIPP Final Environmental Impact Statement. In 1980, the entire Rustler Formation was modeled as a single hydrologic unit, assumed to be isotropic, single-porosity, and completely confined. Variability within the Rustler was evaluated only on the basis of testing at individual wells. In the 1983 WIPP Site and Preliminary Design Validation effort, the Salado Formation, in which the WIPP facility is being constructed, was assumed to be anhydrous, except for fluid inclusions and mineralogically bound water. Recent hydrologic and tracer testing at the WIPP indicates: 1) The local importance of dual-porosity behavior in hydraulic response and transport in parts of the Culebra Dolomite Member of the Rustler Formation; 2) the presence of distinct high- and low-transmissivity regions within the Culebra; and 3) the possible importance of vertical fluid flow within the Rustler. Recent analyses indicate that fluids encountered in the WIPP facility and in experimental brine-migration studies are grain-boundary fluids, chemically distinct from fluid inclusions. Fluid-inclination compositions appear to have been determined shortly after the halite deposition. Because of the times required for diagenetic reactions controlling their compositions, the grain-boundary fluids within the Salado probably have a residence time of several million years

  8. Actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP): FY94 results

    Energy Technology Data Exchange (ETDEWEB)

    Novak, C.F. [ed.

    1995-08-01

    This document contains six reports on actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP). These reports, completed in FY94, are relevant to the estimation of the potential dissolved actinide concentrations in WIPP brines under repository breach scenarios. Estimates of potential dissolved actinide concentrations are necessary for WIPP performance assessment calculations. The specific topics covered within this document are: the complexation of oxalate with Th(IV) and U(VI); the stability of Pu(VI) in one WIPP-specific brine environment both with and without carbonate present; the solubility of Nd(III) in a WIPP Salado brine surrogate as a function of hydrogen ion concentration; the steady-state dissolved plutonium concentrations in a synthetic WIPP Culebra brine surrogate; the development of a model for Nd(III) solubility and speciation in dilute to concentrated sodium carbonate and sodium bicarbonate solutions; and the development of a model for Np(V) solubility and speciation in dilute to concentrated sodium Perchlorate, sodium carbonate, and sodium chloride media.

  9. Actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP): FY94 results

    International Nuclear Information System (INIS)

    Novak, C.F.

    1995-08-01

    This document contains six reports on actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP). These reports, completed in FY94, are relevant to the estimation of the potential dissolved actinide concentrations in WIPP brines under repository breach scenarios. Estimates of potential dissolved actinide concentrations are necessary for WIPP performance assessment calculations. The specific topics covered within this document are: the complexation of oxalate with Th(IV) and U(VI); the stability of Pu(VI) in one WIPP-specific brine environment both with and without carbonate present; the solubility of Nd(III) in a WIPP Salado brine surrogate as a function of hydrogen ion concentration; the steady-state dissolved plutonium concentrations in a synthetic WIPP Culebra brine surrogate; the development of a model for Nd(III) solubility and speciation in dilute to concentrated sodium carbonate and sodium bicarbonate solutions; and the development of a model for Np(V) solubility and speciation in dilute to concentrated sodium Perchlorate, sodium carbonate, and sodium chloride media

  10. Status Report on the Microbial Characterization of Halite and Groundwater Samples from the WIPP

    International Nuclear Information System (INIS)

    Swanson, Juliet S.; Reed, Donald T.; Ams, David A.; Norden, Diana; Simmons, Karen A.

    2012-01-01

    This report summarizes the progress made in the ongoing task of characterizing the microbial community structures within the WIPP repository and in surrounding groundwaters. Through cultivation and DNA-based identification, the potential activity of these organisms is being inferred, thus leading to a better understanding of their impact on WIPP performance. Members of the three biological domains - Bacteria, Archaea, and Eukarya (in this case, Fungi) - that are associated with WIPP halite have been identified. Thus far, their activity has been limited to aerobic respiration; anaerobic incubations are underway. WIPP halite constitutes the near-field microbial environment. We expect that microbial activity in this setting will proceed from aerobic respiration, through nitrate reduction to focus on sulfate reduction. This is also the current WIPP performance assessment (PA) position. Sulfate reduction can occur at extremely high ionic strengths, and sulfate is available in WIPP brines and in the anhydrite interbeds. The role of methanogenesis in the WIPP remains unclear, due to both energetic constraints imposed by a high-salt environment and substrate selectivity, and it is no longer considered in PA. Archaea identified in WIPP halite thus far fall exclusively within the family Halobacteriaceae. These include Halobacterium noricense, cultivated from both low- and high-salt media, and a Halorubrum-like species. The former has also been detected in other salt mines worldwide; the latter likely constitutes a new species. Little is known of its function, but it was prevalent in experiments investigating the biodegradation of organic complexing agents in WIPP brines. Bacterial signatures associated with WIPP halite include members of the phylum Proteobacteria - Halomonas, Pelomonas, Limnobacter, and Chromohalobacter - but only the latter has been isolated. Also detected and cultivated were Salinicoccus and Nesterenkonia spp. Fungi were also isolated from halite. Although

  11. Status Report on the Microbial Characterization of Halite and Groundwater Samples from the WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, Juliet S. [Los Alamos National Laboratory; Reed, Donald T. [Los Alamos National Laboratory; Ams, David A. [Los Alamos National Laboratory; Norden, Diana [Ohio State University; Simmons, Karen A. [Los Alamos National Laboratory

    2012-07-10

    This report summarizes the progress made in the ongoing task of characterizing the microbial community structures within the WIPP repository and in surrounding groundwaters. Through cultivation and DNA-based identification, the potential activity of these organisms is being inferred, thus leading to a better understanding of their impact on WIPP performance. Members of the three biological domains - Bacteria, Archaea, and Eukarya (in this case, Fungi) - that are associated with WIPP halite have been identified. Thus far, their activity has been limited to aerobic respiration; anaerobic incubations are underway. WIPP halite constitutes the near-field microbial environment. We expect that microbial activity in this setting will proceed from aerobic respiration, through nitrate reduction to focus on sulfate reduction. This is also the current WIPP performance assessment (PA) position. Sulfate reduction can occur at extremely high ionic strengths, and sulfate is available in WIPP brines and in the anhydrite interbeds. The role of methanogenesis in the WIPP remains unclear, due to both energetic constraints imposed by a high-salt environment and substrate selectivity, and it is no longer considered in PA. Archaea identified in WIPP halite thus far fall exclusively within the family Halobacteriaceae. These include Halobacterium noricense, cultivated from both low- and high-salt media, and a Halorubrum-like species. The former has also been detected in other salt mines worldwide; the latter likely constitutes a new species. Little is known of its function, but it was prevalent in experiments investigating the biodegradation of organic complexing agents in WIPP brines. Bacterial signatures associated with WIPP halite include members of the phylum Proteobacteria - Halomonas, Pelomonas, Limnobacter, and Chromohalobacter - but only the latter has been isolated. Also detected and cultivated were Salinicoccus and Nesterenkonia spp. Fungi were also isolated from halite. Although

  12. Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

    International Nuclear Information System (INIS)

    1977-06-01

    The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems

  13. "Slicer" for EPA

    CERN Multimedia

    CERN PhotoLab

    1983-01-01

    During the design of the Electron-Positron-Accumulator (EPA), there was an apprehension about the stability-limit of positron bunch-intensity in the SPS. In case that EPA would be able to produce bunches with intensities exceeding what the SPS could digest, an electrostatic septum was to slice up the EPA beam over 2 or 4 turns, thus lowering the bunch intensity while maintaining fast filling of LEP. The "slicer" septum was built and installed, but thanks to the good appetite of the SPS its use never became necessary. The slicer was removed from EPA to lower the machine impedance.

  14. EPA Envirofacts API

    Data.gov (United States)

    U.S. Environmental Protection Agency — Envirofacts integrates information from a variety of EPA's environmental databases. Each of these databases contains information about facilities that are required...

  15. Performance in the WIPP nondestructive assay performance demonstration program

    Energy Technology Data Exchange (ETDEWEB)

    Marcinkiewicz, C.J. [Consolidated Technical Services, Inc., Frederick, MD (United States); Connolly, M.J.; Becker, G.K. [Lockheed Martin Idaho Technologies Company, Idaho Falls, ID (United States)

    1997-11-01

    Measurement facilities performing nondestructive assay (NDA) of wastes intended for disposal at the United States Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) are required to demonstrate their ability to meet specific Quality Assurance Objectives (QAOs). This demonstration is performed, in part, by participation in the NDA Performance Demonstration Program (PDP). The PDP is funded and managed by the Carlsbad Area Office (CAO) of DOE and is conducted by the Idaho National Engineering Laboratory. It tests the characteristics of precision, system bias and/or total uncertainty through the measurement of variable, blind combinations of simulated waste drums and certified radioactive standards. Each facility must successfully participate in the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP was completed in July 1996 and the second is scheduled for completion by December 1996. Seven sites reported data in cycle 1 for 11 different measurement systems. This paper describes the design and operation of the PDP and provides the performance data from cycle 1. It also describes the preliminary results from cycle 2 and updates the status and future plans for the NDA PDP. 4 refs., 9 figs., 11 tabs.

  16. WIPP waste package testing on simulated DHLW: emplacement

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1984-01-01

    Several series of simulated (nonradioactive) defense high-level waste (DHLW) package tests have been emplaced in the WIPP, a research and development facility authorized to demonstrate the safe disposal of defense-related wastes. The primary purpose of these 3-to-7 year duration tests is to evaluate the in situ materials performance of waste package barriers (canisters, overpacks, backfills, and nonradioactive DHLW glass waste form) for possible future application to a licensed waste repository in salt. This paper describes all test materials, instrumentation, and emplacement and testing techniques, and discusses progress of the various tests. These tests are intended to provide information on materials behavior (i.e., corrosion, metallurgical and geochemical alterations, waste form durability, surface interactions, etc.), as well as comparison between several waste package designs, fabrications details, and actual costs. These experiments involve 18 full-size simulated DHLW packages (approximately 3.0 m x 0.6 m diameter) emplaced in vertical boreholes in the salt drift floor. Six of the test packages contain internal electrical heaters (470 W/canister), and were emplace under approximately reference DHLW repository conditions. Twelve other simulated DHLW packages were emplaced under accelerated-aging or overtest conditions, including the artificial introduction of brine, and a thermal loading approximately three to four times higher than reference. Eight of these 12 test packages contain 1500 W/canister electrical heaters; the other four are filled with DHLW glass. 9 refs., 1 fig

  17. Geomechanical applications for the Waste Isolation Pilot Plant (WIPP) project

    International Nuclear Information System (INIS)

    Matalucci, R.V.; Hunter, T.O.

    1981-01-01

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility in bedded salt addressing the technical issues associated with the demonstration of disposal of radioactive waste from the defense programs of the USA. The geomechanical program includes laboratory experimentation, constitutive model and computer code development, and in-situ experimentation. Various material models, including creep for salt, and techniques for predicting room response under thermal and mechanical loads have been developed and are being applied to experiment and facility designs. A Benchmark II study has been conducted to compare the capabilities of nine structural codes to predict response of underground configuration under ambient temperature and with a thermal load of 7.5 W/m 2 . Parametric studies are being conducted to evaluate optimum room configurations. A series of in situ experiments is the next step towards validating models and predictive techniques. These experiments will be conducted in a facility in southeastern New Mexico mined at a depth of 659 m

  18. History of geophysical studies at the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    International Nuclear Information System (INIS)

    Borns, D.J.

    1997-01-01

    A variety of geophysical methods including the spectrum of seismic, electrical, electromagnetic and potential field techniques have supported characterization, monitoring and experimental studies at the Waste Isolation Pilot Plant (WIPP). The geophysical studies have provided significant understanding of the nature of site deformation, tectonics and stability. Geophysical methods have delineated possible brine reservoirs beneath the underground facility and have defined the disturbed rock zone that forms around underground excavations. The role of geophysics in the WIPP project has evolved with the project. The early uses were for site characterization to satisfy site selection criteria or factors. As the regulatory framework for WIPP grew since 1980, the geophysics program supported experimental and field programs such as Salado hydrogeology and underground room systems and excavations. In summary, the major types of issues that geophysical studies addressed for WIPP are: Site Characterization; Castile Brine Reservoirs; Rustler/Dewey Lake Hydrogeology; Salado Hydrogeology; and Excavation Effects. The nature of geophysics programs for WIPP has been to support investigation rather than being the principal investigation itself. The geophysics program has been used to define conceptual models (e.g., the Disturbed Rock Zone-DRZ) or to test conceptual models (e.g., high transmissivity zones in the Rustler Formation). The geophysics program primarily supported larger characterization and experimental programs. Funding was not available for the complete documentation and interpretation. Therefore, a great deal of the geophysics survey information resides in contractor reports

  19. Preliminary identification of interfaces for certification and transfer of TRU waste to WIPP

    International Nuclear Information System (INIS)

    Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.

    1982-02-01

    This study complements the national program to certify that newly generated and stored, unclassified defense transuranic (TRU) wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The objectives of this study were to identify (1) the existing organizational structure at each of the major waste-generating and shipping sites and (2) the necessary interfaces between the waste shippers and WIPP. The interface investigations considered existing waste management organizations at the shipping sites and the proposed WIPP organization. An effort was made to identify the potential waste-certifying authorities and the lines of communication within these organizations. The long-range goal of this effort is to develop practicable interfaces between waste shippers and WIPP to enable the continued generation, interim storage, and eventual shipment of certified TRU wastes to WIPP. Some specific needs identified in this study include: organizational responsibility for certification procedures and quality assurance (QA) program; simple QA procedures; and specification and standardization of reporting forms and procedures, waste containers, and container labeling, color coding, and code location

  20. Implications of the presence of petroleum resources on the integrity of the WIPP

    International Nuclear Information System (INIS)

    Silva, M.K.

    1994-06-01

    The Waste Isolation Pilot Plant (WIPP) is a facility of the US Department of Energy (DOE), designed and constructed for the permanent disposal of transuranic (TRU) defense waste. The WIPP is surrounded by reserves of potash, crude oil, and natural gas. These are attractive targets for exploratory drilling which could disrupt the integrity of the transuranic waste repository. The performance assessment calculations published to date have identified future drilling for oil and gas reserves as an event that may disrupt the repository and may release radionuclides in excess of the standards. Therefore, the probability of inadvertent human intrusion into the repository by drilling and its impact on the integrity of the repository must be carefully assessed. This report evaluates: (1) the studies funded by the DOE to examine the crude oil potential in the immediate vicinity of the WIPP; (2) the use of an elicitation exercise to predict future drilling rates for use in the calculation of the repository performance; and (3) the observed limitations of institutional controls. This report identifies the following issues that remain to be resolved: (1) the limited performance of blowout preventers after drilling into high pressure zones immediately adjacent to the WIPP Site Boundary; (2) reported problems with waterflooding operations in southeastern New Mexico; (3) reported water level rises in several wells completed in the Rustler Formation, south of the WIPP Site, possibly due to oil and gas wells or leaking injection wells; and (4) reports of inadequate well abandonment practices on BLM leases and the continued absence of enforceable regulations

  1. DOE responses to the State of New Mexico's comments on ''summary of the results of the evaluation of the WIPP site and preliminary design validation program'' (WIPP-DOE-161)

    International Nuclear Information System (INIS)

    1983-06-01

    During the 60-day period provided for comments on the ''Summary of the Results of the Evaluation of the WIPP Site and Preliminary Design Validation Program'' (WIPP-DOE-161), written submittals and hearing testimony from about 133 individuals, 7 citizens groups and 6 state agencies were received by the Department of Energy (DOE). Approximately 25% of the public comment submittals were positive statements supporting the WIPP, with the remaining 75% reflecting concern with one or more aspects of the project. A portion of the state's comment package (submitted by the Governor of New Mexico) contained concerns relevant to WIPP which were unrelated to site suitability. Supportive comments formed the majority of the submittals from the New Mexico Environmental Evaluation Group (EEG) which ''...is charged with the responsibility of evaluating the suitability of the site for carrying out the mission of WIPP by analyzing all the reports and other information which form the background to the DOE evaluation of the site''

  2. EPA Linked Open Data (Collection)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This is a collection item referencing the following EPA Linked Data resources: - EPA Facility Registry Service (FRS) - EPA Substance Registry Service (SRS) -...

  3. EPA Library Network Communication Strategies

    Science.gov (United States)

    To establish Agency-wide procedures for the EPA National Library Network libraries to communicate, using a range of established mechanisms, with other EPA libraries, EPA staff, organizations and the public.

  4. Analysis of Waste Isolation Pilot Plan (WIPP) Underground and MGO Samples by the Savannah River National Laboratory (SRNL)

    Energy Technology Data Exchange (ETDEWEB)

    Young, J. [Savannah River Site (SRS), Aiken, SC (United States); Ajo, H. [Savannah River Site (SRS), Aiken, SC (United States); Brown, L. [Savannah River Site (SRS), Aiken, SC (United States); Coleman, C. [Savannah River Site (SRS), Aiken, SC (United States); Crump, S. [Savannah River Site (SRS), Aiken, SC (United States); Diprete, C. [Savannah River Site (SRS), Aiken, SC (United States); Diprete, D. [Savannah River Site (SRS), Aiken, SC (United States); Ekechukwu, A. [Savannah River Site (SRS), Aiken, SC (United States); Gregory, C. [Savannah River Site (SRS), Aiken, SC (United States); Jones, M. [Savannah River Site (SRS), Aiken, SC (United States); Missimer, D. [Savannah River Site (SRS), Aiken, SC (United States); O' Rourke, P. [Savannah River Site (SRS), Aiken, SC (United States); White, T. [Savannah River Site (SRS), Aiken, SC (United States)

    2014-12-31

    Analysis of the recent WIPP samples are summarized in this report; WIPP Cam Filters 4, 6, 9 (3, 7, 11 were analyzed with FAS-118 in a separate campaign); WIPP Drum Lip R16 C4; WIPP Standard Waste Box R15 C5; WIPP MgO R16 C2; WIPP MgO R16 C4; WIPP MgO R16 C6; LANL swipes of parent drum; LANL parent drum debris; LANL parent drum; IAEA Swipe; Unused “undeployed” Swheat; Unused “undeployed” MgO; and Masselin cloth “smears”. Analysis showed that the MgO samples were very pure with low carbonate and water content. Other samples showed the expected dominant presence of Mg, Na and Pb. Parent drum debris sample was mildly acidic. Interpretation of results is not provided in this document, but rather to present and preserve the analytical work that was performed. The WIPP Technical Analysis Team is responsible for result interpretation which will be written separately.

  5. Salt impact studies at WIPP effects of surface storage of salt on microbial activity

    International Nuclear Information System (INIS)

    Rodriguez, A.L.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) currently under construction in southeastern New Mexico is a research and development facility to demonstrate the safe disposal of transuranic waste in a deep geological formation (bedded salt). The Ecological Monitoring Program at WIPP is designed to detect and measure changes in the local ecosystem which may be the result of WIPP construction activities. The primary factor which may affect the system prior to waste emplacement is windblown salt from discrete stockpiles. Both vegetation and soil microbial processes should reflect changes in soil chemistry due to salt importation. Control and experimental (potentially affected) plots have been established at the site, and several parameters are measured quarterly in each plot as part of the soil microbial sampling subprogram. This subprogram was designed to monitor a portion of the biological community which can be affected by changes in the chemical properties at the soil surface

  6. Modification of the ventilation system at Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Sethi, S.C.

    1987-01-01

    The WIPP (Waste Isolation Pilot Plant) Project near Carlsbad, New Mexico, is a research and development project sponsored by the US Department of Energy, designed to demonstrate the safe disposal of radioactive waste. A mine (repository) is being developed 2,150 feet below the surface in a thick salt bed, which will serve as the disposal medium. The underground ventilation system for the WIPP project was originally designed based on a fixed project scope. The design criteria and ventilation requirements were developed for the performance of various activities as then envisioned towards the achievement of this goal. However, in light of new information and actual site-specific experience at WIPP leading to a clearer definition of the scope-related programs and activities, it was realized that the existing ventilation system may need to be modified

  7. Rationale for the H-19 and H-11 tracer tests at the WIPP site

    International Nuclear Information System (INIS)

    Beauheim, R.L.; Meigs, L.C.; Davies, P.B.

    1996-01-01

    The Waste Isolation Pilot Plant (WIPP) is a repository for transuranic wastes constructed in bedded Permian-age halite in the Delaware Basin, a sedimentary basin in southeastern New Mexico, USA. A drilling scenario has been identified during performance assessment (PA) that could lead to the release of radionuclides to the Culebra Dolomite Member of the Rustler Formation, the most transmissive water-saturated unit above the repository horizon. Were this to occur, the radionuclides would need to be largely contained within the Culebra (or neighboring strata) within the WIPP-site boundary through the period lasting for 10,000 years after repository closure for WIPP to remain in compliance with applicable regulations on allowable releases. Thus, processes affecting transport of radionuclides within the Culebra are of importance to PA

  8. Cookoff Modeling of a WIPP waste drum (68660)

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, Michael L. [Sandia National Laboratories, Albuquerque, NM (United States)

    2014-11-24

    A waste drum located 2150 feet underground may have been the root cause of a radiation leak on February 14, 2014. Information provided to the WIPP Technical Assessment Team (TAT) was used to describe the approximate content of the drum, which included an organic cat litter (Swheat Scoop®, or Swheat) composed of 100% wheat products. The drum also contained various nitrate salts, oxalic acid, and a nitric acid solution that was neutralized with triethanolamine (TEA). CTH-TIGER was used with the approximate drum contents to specify the products for an exothermic reaction for the drum. If an inorganic adsorbent such as zeolite had been used in lieu of the kitty litter, the overall reaction would have been endothermic. Dilution with a zeolite adsorbent might be a useful method to remediate drums containing organic kitty litter. SIERRA THERMAL was used to calculate the pressurization and ignition of the drum. A baseline simulation of drum 68660 was performed by assuming a background heat source of 0.5-10 W of unknown origin. The 0.5 W source could be representative of heat generated by radioactive decay. The drum ignited after about 70 days. Gas generation at ignition was predicted to be 300-500 psig with a sealed drum (no vent). At ignition, the wall temperature increases modestly by about 1°C, demonstrating that heating would not be apparent prior to ignition. The ignition location was predicted to be about 0.43 meters above the bottom center portion of the drum. At ignition only 3-5 kg (out of 71.6 kg total) has been converted into gas, indicating that most of the material remained available for post-ignition reaction.

  9. Assessment of near-surface dissolution at and near the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    International Nuclear Information System (INIS)

    Bachman, G.O.

    1985-07-01

    The area at and near the WIPP site was examined for evidence of karst development on the geomorphic surface encompassing the site. Certain surficial depressions of initial concern were identified as blowouts in sand dune fields (shallow features unrelated to karstification). An ancient stream system active more than 500,000 yr ago contained more water than any system since. During that time (Gatuna, Middle Pleistocene), many karst features such as Clayton Basin and Nash Draw began to form in the region. Halite was probably dissolved from parts of the Rustler Formation at that time. Dissolution of halite and gypsum from intervals encountered in Borehole WIPP-33 west of the WIPP site occurred during later Pleistocene time (i.e., <450,000 yr ago). However, there is no evidence of active near-surface dissolution within a belt to the east of WIPP-33 in the vicinity of the WIPP shaft. 26 refs., 11 figs., 1 tab

  10. Hanford to WIPP - What a Trip: The Road from Hanford is now Open

    International Nuclear Information System (INIS)

    FRENCH, M.S.

    2001-01-01

    The road leading from Hanford's Waste Receiving and Processing (WRAP) Facility to the Waste Isolation Pilot Plant (WJPP) in New Mexico developed a few bumps and detours over the past year, but it has now been successfully traversed. There were challenges obtaining Carlsbad Area Office and New Mexico Department of Ecology certification of the Hanford characterization program. After months of work, when initial certification appeared imminent, the issuance of the WIPP Hazardous Waste Permit changed the Waste Analysis Plan (WAP) required for characterizing waste for acceptance at WIPP. After a ceremony dedicating the ''Washington'' room at WIPP, the inaugural shipment from WRAP to WIPP was scheduled for June 2000. This first shipment was planned based on shipping a number of containers that had been characterized before the issuance of the WIPP Mixed Waste Permit. However, the New Mexico Department of Ecology initially declined to accept the characterization data generated before the permit was issued, necessitating revision to the planned shipment. Because of the difficulties inherent in scheduling the TRUPACT-II transport and coordination with all of the states through which the shipment would pass, it was decided to proceed with the first shipment in early July with only the drums that had been characterized after Hanford compliance with the new WIPP WAP requirements had been certified. Following the initial shipment, previously certified containers were recertified using a process approved through negotiation with the New Mexico Environment Department, and additional full shipments have been successfully completed. This paper will present an overview of the challenges overcome and lessons learned in obtaining certification, coordination with the involved states, and eventual successful1 implementation of a routine shipping program

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

    International Nuclear Information System (INIS)

    1977-04-01

    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

  12. US EPA CARE Grants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This is a provisional dataset that contains point locations for the subset of Community Action for a Renewed Environment (CARE) grants given out by the US EPA. CARE...

  13. EPA User Personas

    Science.gov (United States)

    Learn how EPA's three web user personas (Information Consumer, Information Intermediary, and Information Interpreter) can help you identify appropriate top audiences and top tasks for a topic or web area.

  14. EPA's Efforts in Eurasia

    Science.gov (United States)

    EPA has been collaborating with Russia, Central Asia, the Caucasus and Ukraine for over 20 years and continues to work with their governments and non-governmental organizations on environment, science and technology issues.

  15. US EPA EJ Grants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This is a provisional dataset that contains point locations for all Environmental Justice (EJ) grants given out by the US EPA. There are many limitations to the data...

  16. EPA Nanorelease Dataset

    Data.gov (United States)

    U.S. Environmental Protection Agency — EPA Nanorelease Dataset. This dataset is associated with the following publication: Wohlleben, W., C. Kingston, J. Carter, E. Sahle-Demessie, S. Vazquez-Campos, B....

  17. Science Inventory | US EPA

    Science.gov (United States)

    The Science Inventory is a searchable database of research products primarily from EPA's Office of Research and Development. Science Inventory records provide descriptions of the product, contact information, and links to available printed material or websites.

  18. EPA Recovery Mapper

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EPA Recovery Mapper is an Internet interactive mapping application that allows users to discover information about every American Recovery and Reinvestment Act...

  19. EPA Environmental Chemistry Laboratory

    Science.gov (United States)

    1993-01-01

    The Environmental Protection Agency's (EPA) Chemistry Laboratory (ECL) is a national program laboratory specializing in residue chemistry analysis under the jurisdiction of the EPA's Office of Pesticide Programs in Washington, D.C. At Stennis Space Center, the laboratory's work supports many federal anti-pollution laws. The laboratory analyzes environmental and human samples to determine the presence and amount of agricultural chemicals and related substances. Pictured, ECL chemists analyze environmental and human samples for the presence of pesticides and other pollutants.

  20. Comments on EPA's LLW preproposal

    International Nuclear Information System (INIS)

    Littleton, B.K.; Weinstock, L.

    1995-01-01

    The Environmental Protection Agency (EPA) is currently developing standards for the management, storage, and disposal of Low-Level Radioactive Waste (LLW). The Atomic Energy Act delegated EPA, among other provisions, the authority to establish generally applicable standards for the disposal of radioactive waste to ensure that the public and the environment are adequately protected from potential radiation impacts. As an initial effort to open communications on a standard for LLW, the Agency developed a preproposal draft (Preproposal Draft of 40 CFR Part 193 - 30 Nov 94) and circulated it to interested parties for review and comment. The extended comment period ended April 12, 1995. A summary of the comments received and analyzed to date follows. After all comments have been analyzed, the rule will undergo an Agency clearance process and be sent to the Office of Management and Budget for review. After that review, the formal process of publication of the proposed rule in the Federal Register and the formal public comment period will begin

  1. EVALUATION OF RISKS AND WASTE CHARACTERIZATION REQUIREMENTS FOR THE TRANSURANIC WASTE EMPLACED IN WIPP DURING 1999

    International Nuclear Information System (INIS)

    Channell, J.K.; Walker, B.A.

    2000-01-01

    Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations

  2. Assessment of Contaminated Brine Fate and Transport in MB139 at WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlman, Kristopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Applied Systems Analysis and Research Dept.; Malama, Bwalya [Sandia National Lab., Carlsbad, NM (United States). Performance Assessment Dept.

    2014-07-01

    Following the radionuclide release event of February 14, 2014 at the Waste Isolation Pilot Plant (WIPP), actinide contamination has been found on the walls and floor in Panel 7 as a result of a release in Room 7 of Panel 7. It has been proposed to decontaminate Panel 7 at the WIPP by washing contaminated surfaces in the underground with fresh water. A cost-effective cleanup of this contamination would allow for a timely return to waste disposal operations at WIPP. It is expected that the fresh water used to decontaminate Panel 7 will flow as contaminated brine down into the porosity of the materials under the floor – the run-of-mine (ROM) salt above Marker Bed 139 (MB139) and MB139 itself – where its fate will be controlled by the hydraulic and transport properties of MB139. Due to the structural dip of MB139, it is unlikely that this brine would migrate northward towards the Waste-Handling Shaft sump. A few strategically placed shallow small-diameter observation boreholes straddling MB139 would allow for monitoring the flow and fate of this brine after decontamination. Additionally, given that flow through the compacted ROM salt floor and in MB139 would occur under unsaturated (or two-phase) conditions, there is a need to measure the unsaturated flow properties of crushed WIPP salt and salt from the disturbed rock zone (DRZ).

  3. Summary of research and development activities in support of waste acceptance criteria for WIPP

    International Nuclear Information System (INIS)

    Hunter, T.O.

    1979-11-01

    The development of waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP) is summarized. Specifications for acceptable waste forms are included. Nine program areas are discussed. They are: TRU characterization, HLW interactions, thermal/structural interactions, nuclide migration, permeability, brine migration, borehole plugging, operation/design support, and instrumentation development. Recommendations are included

  4. The development of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

    International Nuclear Information System (INIS)

    Walter, L.H.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) offers a perspective on the value of designing flexibility into a public affairs program to enable it to grow with and complement a project's evolution from construction through to operations. This paper discusses how the WIPP public affairs program progressed through several stages to its present scope. During the WIPP construction phase, the public affairs program laid a foundation for Project acceptance in the community. A speaker's bureau, a visitors program, and various community outreach and support programs emphasized the educational and socioeconomic benefits of having this controversial project in Carlsbad. Then, in this past year as the project entered a preoperational status, the public affairs program emphasis shifted to broaden the positive image that had been created locally. In this stage, the program promoted the project's positive elements with the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management and transportation program. Currently, an even broader, more aggressive public affairs program is planned. During this stage public affairs will be engaged in a comprehensive institutional and outreach program, explaining and supporting WIPP's mission in each of the communities and agencies affected by the operation of the country's first geologic repository

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

    International Nuclear Information System (INIS)

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

    1978-12-01

    Three seismic reflection (Vibroseis) surveys conducted from 1976 through 1978 by Sandia Laboratories to support investigations for the Waste Isolation Pilot Plant (WIPP) are described. Volume I describes the purpose, field parameters, and data processing parameters. Volume II contains uninterpreted processed lines and shotpoint maps. Data interpretations will be the subject of the subsequent reports. The data collected during these three surveys total 77 line miles; 72 line miles of this are on or very near the WIPP site. The first of the surveys (1976 SAN) covered 25 line miles and was conducted similarly to previous petroleum industry surveys in the area. 1976 SAN supplemented existing petroleum industry data. The two subsequent surveys (1977 X and 1978 Y) used shorter geophone spacings (110'), higher signal frequencies (up to 100 Hz), and higher data sampling rates (2 ms.) to better define the shallow zone (less than 4000') of primary interest. 1977 X contained 47 line miles on or near the WIPP site and over several structural features northwest of the site. 1978 Y contains 5 line miles over a one square mile area near the center of the WIPP site. These data show increasing discrimination of shallow reflectors as data collection parameters were modified. Data tables of recording and processing parameters are included. A fourth Vibroseis survey was conducted at the WIPP site in 1978 by Grant Geophysical Company for Bechtel; the data are not in final form and are not included. Petroleum industry data and an inconclusive weight-drop survey, conducted in 1976, are also not included in this report

  6. History of geophysical studies at the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico

    International Nuclear Information System (INIS)

    Borns, D.J.

    1997-01-01

    A variety of geophysical methods including the spectrum of seismic, electrical, electromagnetic and potential field techniques have used support characterization, monitoring and experimental studies at the Waste Isolation Pilot Plant (WIPP). The geophysical studies have provided significant understanding of the nature of site deformation, tectonics and stability. Geophysical methods have delineated possible brine reservoirs beneath the underground facility and have defined the disturbed rock zone that forms around underground excavations. The role of geophysics in the WIPP project has evolved with the project. The early uses were for site characterization to satisfy site selection criteria or factors. As the regulatory framework for WIPP grew since 1980, the geophysics program was focused on support of experimental and field programs such as Salado hydrogeology and underground room systems and excavations. In summary, the major types of issues that geophysical studies addressed for WIPP are: Issue 1: Site Characterization; Issue 2: Castile Brine Reservoirs; Issue 3: Rustler /Dewey Lake Hydrogeology; Issue 4: Salado Hydrogeology; and Issue 5: Excavation Effects. The nature of geophysics program for WIPP has been to support investigation rather than being the principal investigation itself. The geophysics program has been used to define conceptual models (e.g., the Disturbed Rock Zone-DRZ) or to test conceptual models (e.g., high transmissivity zones in the Rustler Formation). An effect of being a support program is that as new project priorities arose the funding for the geophysics program was limited and withdrawn. An outcome is that much of the geophysics survey information resides in contractor reports since final interpretation reports were not funded

  7. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2014-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 4 février de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org. * * * * * Carte de membre de l'Association du personnel du CERN Les membres GAC-EPA qui souhaitent recevoir une carte de membre AP en 2014 doivent  en faire la demande par email à secretariat@gac-epa.org, ou par lettre au secrétaire ...

  8. 76 FR 9780 - Notification of Deletion of System of Records; EPA Parking Control Office File (EPA-10) and EPA...

    Science.gov (United States)

    2011-02-22

    ... System of Records; EPA Parking Control Office File (EPA-10) and EPA Transit and Guaranteed Ride Home... Environmental Protection Agency (EPA) is deleting the systems of records for EPA Parking Control Office File... through the EPA Internet under the ``Federal Register'' listings at http://www.epa.gov/fedrgstr/ . Dated...

  9. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION and PLANNING FOR REVRIEVAL TREATMENT and EVENTUAL DISPOSAL AT WIPP

    International Nuclear Information System (INIS)

    KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

    2006-01-01

    The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP)

  10. Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    The US Department of Energy is currently constructing the Waste Isolation Pilot near Carlsbad, New Mexico. The full-scale pilot plant will demonstrate the feasibility of the safe disposal of defense-related nuclear waste in a bedded salt formation at a depth of 2160 feet below the surface. WIPP will provide for the permanent storage of 25,000 cu ft of remote-handled (RH) transuranic waste and 6,000,000 cu ft of contact-handled (CH) transuranic waste. This paper covers the major mechanical/structural design considerations for the waste hoist and its hoist tower structure. The design of the hoist system and safety features incorporates state-of-the-art technology developed in the hoist and mining industry to ensure safe operation for transporting nuclear waste underground. Also included are design specifications for VOC-10 monitoring system.

  11. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2015-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 3 mars de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 7 avril, 5 mai, 2 juin, 1er septembre, 6 octobre, 3 novembre et 1er décembre 2013. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  12. GAC-EPA

    CERN Document Server

    GAC-EPA

    2013-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 1er octobre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 5 novembre et 3 décembre 2013. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  13. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 5 avril de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 3 mai, 7 juin, 6 septembre, 4 octobre, 1er et 29 novembre décembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  14. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : le mardi 29 novembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  15. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : le mardi 1er novembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel. La permanence suivante aura lieu le mardi 29 novembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  16. GAC-EPA

    CERN Document Server

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 3 mai de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 7 juin, 6 septembre, 4 octobre, 1er et 29 novembre décembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  17. GAC-EPA

    CERN Document Server

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 5 avril de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 3 mai, 7 juin, 6 septembre, 4 octobre, 1er et 29 novembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  18. GAC-EPA

    CERN Document Server

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 4 octobre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 1er et 29 novembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  19. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2015-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 1er décembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  20. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 2 février de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 1er mars, 5 avril, 3 mai, 7 juin, 6 septembre, 4 octobre, 1er et 29 novembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  1. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 1er mars de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 5 avril, 3 mai, 7 juin, 6 septembre, 4 octobre, 1er et 29 novembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  2. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2015-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 3 novembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel La permanence suivante aura lieu le mardi 1er décembre 2015. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  3. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2013-01-01

    Carte de membre de l'Association du personnel du CERN Comme cela a été précisé dans le bulletin d'automne n° 43, les membres GAC-EPA qui souhaitent recevoir une carte de membre AP en 2013 devront en faire la demande, avant le 31 janvier, par email à secretariat@gac-epa.org, ou par lettre au secrétaire du GAC-EPA, p/a Association du personnel CERN, CH-1211 GENEVE 23. Il n'y a pas de tacite reconduction de ces cartes et par conséquent une demande doit être faite chaque année par l'intéressé(e).

  4. Report: Significant Data Quality Deficiencies Impede EPA’s Ability to Ensure Companies Can Pay for Cleanups

    Science.gov (United States)

    Report #16-P-0126, March 31, 2016. Management Alert. Environmental and extensive financial risks exist from the EPA's failure to have accurate and complete data to monitor and ensure compliance with RCRA and CERCLA financial assurance requirements.

  5. Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

    2006-01-01

    In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

  6. US EPA overview

    International Nuclear Information System (INIS)

    Rowe, W.D.

    1976-01-01

    EPA believes that effective and efficient solutions to problems in all radioactive waste disposal areas will require close coordination and cooperation among all agencies involved. In this regard, EPA already has participated in meetings with the Energy Research and Development Administration, the Nuclear Regulatory Commission, the Council on Environmental Quality, the U.S. Geological Survey, and the Office of Management and Budget to lay the groundwork for the development of a consolidated national radioactive waste disposal plan. The EPA program is directed first toward developing goals and requirements; and then, in cooperation with the public, industry, the States and Federal agencies, towards determining by what means these goals can be achieved for each waste management option. In addition, the program will develop criteria for determining when the goals of the waste management options have been achieved. In summary, EPA will provide fundamental environmental criteria and generally applicable environmental standards for permanent disposal of high level radwastes. Concurrently, ERDA will develop the necessary technology; and NRC will conduct necessary studies, develop waste-related regulations, and license specific sites and methods of control. Together, we will be able to manage the disposal of the Nation's radioactive waste in an environmentally adequate manner

  7. EPA Web Training Classes

    Science.gov (United States)

    Scheduled webinars can help you better manage EPA web content. Class topics include Drupal basics, creating different types of pages in the WebCMS such as document pages and forms, using Google Analytics, and best practices for metadata and accessibility.

  8. EPA's Green Roof Research

    Science.gov (United States)

    This is a presentation on the basics of green roof technology. The presentation highlights some of the recent ORD research projects on green roofs and provices insight for the end user as to the benefits for green roof technology. It provides links to currently available EPA re...

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

    International Nuclear Information System (INIS)

    Rempe, Norbert T.; Nelson, Roger A.

    2008-01-01

    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 m 3 containers inside disposal rooms to remotely inserting highly radioactive 0.89 m 3 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 m 3 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 km 2 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

  10. EPA Communications Stylebook: Writing Guide

    Science.gov (United States)

    For the most part, EPA follows the Associated Press (AP) Stylebook. Other requirements of basic punctuation and grammar and usage in EPA writing modify, supplement, or in some cases reiterate AP style.

  11. EPA Alternative Dispute Resolution Contacts

    Science.gov (United States)

    The success of EPA's ADR efforts depends on a network of talented and experienced professionals in Headquarters offices and EPA Regions. For Agency-wide ADR information, please contact the Conflict Prevention and Resolution Center.

  12. Assessment of the potential for karst in the Rustler Formation at the WIPP site

    International Nuclear Information System (INIS)

    Lorenz, John Clay

    2006-01-01

    This report is an independent assessment of the potential for karst dissolution in evaporitic strata of the Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site. Review of the available data suggests that the Rustler strata thicken and thin across the area in depositional patterns related to lateral variations in sedimentary accommodation space and normal facies changes. Most of the evidence that has been offered for the presence of karst in the subsurface has been used out of context, and the different pieces are not mutually supporting. Outside of Nash Draw, definitive evidence for the development of karst in the Rustler Formation near the WIPP site is limited to the horizon of the Magenta Member in drillhole WIPP-33. Most of the other evidence cited by the proponents of karst is more easily interpreted as primary sedimentary structures and the localized dissolution of evaporitic strata adjacent to the Magenta and Culebra water-bearing units. Some of the cited evidence is invalid, an inherited baggage from studies made prior to the widespread knowledge of modern evaporite depositional environments and prior to the existence of definitive exposures of the Rustler Formation in the WIPP shafts. Some of the evidence is spurious, has been taken out of context, or is misquoted. Lateral lithologic variations from halite to mudstone within the Rustler Formation under the WIPP site have been taken as evidence for the dissolution of halite such as that seen in Nash Draw, but are more rationally explained as sedimentary facies changes. Extrapolation of the known karst features in Nash Draw eastward to the WIPP site, where conditions are and have been significantly different for half a million years, is unwarranted. The volumes of insoluble material that would remain after dissolution of halite would be significantly less than the observed bed thicknesses, thus dissolution is an unlikely explanation for the lateral variations from halite to mudstone and siltstone

  13. Assessment of the potential for karst in the Rustler Formation at the WIPP site.

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz, John Clay

    2006-01-01

    This report is an independent assessment of the potential for karst dissolution in evaporitic strata of the Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site. Review of the available data suggests that the Rustler strata thicken and thin across the area in depositional patterns related to lateral variations in sedimentary accommodation space and normal facies changes. Most of the evidence that has been offered for the presence of karst in the subsurface has been used out of context, and the different pieces are not mutually supporting. Outside of Nash Draw, definitive evidence for the development of karst in the Rustler Formation near the WIPP site is limited to the horizon of the Magenta Member in drillhole WIPP-33. Most of the other evidence cited by the proponents of karst is more easily interpreted as primary sedimentary structures and the localized dissolution of evaporitic strata adjacent to the Magenta and Culebra water-bearing units. Some of the cited evidence is invalid, an inherited baggage from studies made prior to the widespread knowledge of modern evaporite depositional environments and prior to the existence of definitive exposures of the Rustler Formation in the WIPP shafts. Some of the evidence is spurious, has been taken out of context, or is misquoted. Lateral lithologic variations from halite to mudstone within the Rustler Formation under the WIPP site have been taken as evidence for the dissolution of halite such as that seen in Nash Draw, but are more rationally explained as sedimentary facies changes. Extrapolation of the known karst features in Nash Draw eastward to the WIPP site, where conditions are and have been significantly different for half a million years, is unwarranted. The volumes of insoluble material that would remain after dissolution of halite would be significantly less than the observed bed thicknesses, thus dissolution is an unlikely explanation for the lateral variations from halite to mudstone and siltstone

  14. Ensuring a Safe Technological Revolution

    Science.gov (United States)

    2016-12-01

    much lower, and the performance gained can dramatically reduce life -cycle costs. Validated cost data are scarce, and accurate AM cost models need to be...reduce costs, minimize obsolescence issues and improve both capability and readi- ness across the entire life cycle of naval systems—including both the...of naval weapon systems. The Navy is actively engaging its various communi- ties to align needs and ensure that AM can be safely acceler- ated and

  15. Comparison between disign criteria and observed structural performance of underground openings at WIPP

    International Nuclear Information System (INIS)

    Cook, R.F.; Francke, C.

    1989-01-01

    This paper discusses the observed structural performance of the underground excavations at the Waste Isolation Pilot Plant (WIPP) in relation to design criteria. The criteria were established at an early stage of the project to define the functional and structural requirements that were to be addressed in the design of the facility. For the underground structural response, the criteria defined the requirements for the shaft and shaft liner design, mine design, waste emplacement, retrievability and instrumentation. The observed structural performance of the underground is determined by the field data that have been collected since excavations were started at the WIPP site. The observations include field measurements of rock and water conditions, as well as maintenance records. The data provide input to design confirmation, performance assessment and form the basis for the design of new underground structures. For this paper, the field data have been compared with the design criteria applicable to ground control to demonstrate that the requirements of the design are met

  16. Plutonium interaction with a bacterial strain isolated from the waste isolation pilot plant (WIPP) environment

    International Nuclear Information System (INIS)

    Strietelmeier, B.A.; Kraus, S.M.; Leonard, P.A.; Triay, I.R.

    1996-01-01

    This work was conducted as part of a series of experiments to determine the association and interaction of various actinides with bacteria isolated from the WIPP site. The majority of bacteria that exist at the site are expected to be halophiles, or extreme halophiles, due to the high concentration of salt minerals at the location. Experiments were conducted to determine the toxicity of plutonium-n-239, neptunium-237 and americium-243 to several species of these halophiles and the results were reported elsewhere. As an extension of these experiments, we report an investigation of the type of association that occurs between 239 Pu and the isolate WIPP-1A, isolated by staff at Brookhaven National Laboratory, when grown in a high-salt, defined medium. Using scanning electron microscopy (SEM) techniques, we demonstrate a surface association of the 239 Pu with the bacterial cells

  17. Comparative analysis of nine structural codes used in the second WIPP benchmark problem

    International Nuclear Information System (INIS)

    Morgan, H.S.; Krieg, R.D.; Matalucci, R.V.

    1981-11-01

    In the Waste Isolation Pilot Plant (WIPP) Benchmark II study, various computer codes were compared on the basis of their capabilities for calculating the response of hypothetical drift configurations for nuclear waste experiments and storage demonstration. The codes used by participants in the study were ANSALT, DAPROK, JAC, REM, SANCHO, SPECTROM, STEALTH, and two different implementations of MARC. Errors were found in the preliminary results, and several calculations were revised. Revised solutions were in reasonable agreement except for the REM solution. The Benchmark II study allowed significant advances in understanding the relative behavior of computer codes available for WIPP calculations. The study also pointed out the possible need for performing critical design calculations with more than one code. Lastly, it indicated the magnitude of the code-to-code spread in results which is to be expected even when a model has been explicitly defined

  18. Basic data report for drillhole WIPP 27 (Waste Isolation Pilot Plant)

    International Nuclear Information System (INIS)

    1979-10-01

    WIPP 27 was drilled in Eddy County, New Mexico (NM 1/4 sec. 21, T21S, R30E) to investigate evaporite dissolution features and to determine the stratigraphy of surface and near-surface formations. The borehole encountered, from top to bottom, 79 feet of Quaternary deposits, 73 feet of the Rustler Formation, and 171 feet of the upper portion of the Salado Formation. Consecutive cores were obtained for the entire depth of WIPP 27. Geophysical logs measure acoustic velocities, density, radioactivity, and formation resistivity. An interpretive report on dissolution in Nash Draw will be based on combined borehole data, surface mapping and laboratory analyses of Nash Draw rocks and fluids

  19. The influence of salt aerosol on alpha radiation detection by WIPP continuous air monitors

    Energy Technology Data Exchange (ETDEWEB)

    Bartlett, W.T.; Walker, B.A. [Environmental Evaluation Group, Albuquerque, NM (United States)

    1997-08-01

    Waste Isolation Pilot Plant (WIPP) alpha continuous air monitor (CAM) performance was evaluated to determine if CAMs could detect accidental releases of transuranic radioactivity from the underground repository. Anomalous alpha spectra and poor background subtraction were observed and attributed to salt deposits on the CAM sampling filters. Microscopic examination of salt laden sampling filters revealed that aerosol particles were forming dendritic structures on the surface of the sampling filters. Alpha CAM detection efficiency decreased exponentially as salt deposits increased on the sampling filters, suggesting that sampling-filter salt was performing like a fibrous filter rather than a membrane filter. Aerosol particles appeared to penetrate the sampling-filter salt deposits and alpha particle energy was reduced. These findings indicate that alpha CAMs may not be able to detect acute releases of radioactivity, and consequently CAMs are not used as part of the WIPP dynamic confinement system. 12 refs., 12 figs., 1 tab.

  20. Contamination control aspects of attaching waste drums to the WIPP Waste Characterization Chamber

    International Nuclear Information System (INIS)

    Rubick, L.M.; Burke, L.L.

    1998-01-01

    Argonne National Laboratory West (ANL-W) is verifying the characterization and repackaging of contact-handled transuranic (CH-TRU) mixed waste in support of the Waste Isolation Pilot Program (WIPP) project located in Carlsbad, New Mexico. The WIPP Waste Characterization Chamber (WCC) was designed to allow opening of transuranic waste drums for this process. The WCC became operational in March of 1994 and has characterized approximately 240 drums of transuranic waste. The waste drums are internally contaminated with high levels of transuranic radionuclides. Attaching and detaching drums to the glove box posed serious contamination control problems. Prior to characterizing waste, several drum attachment techniques and materials were evaluated. An inexpensive HEPA filter molded into the bagging material helps with venting during detachment. The current techniques and procedures used to attach and detach transuranic waste drums to the WCC are described

  1. Summary of 1988 WIPP [Waste Isolation Pilot Plant] Facility horizon gas flow measurements

    International Nuclear Information System (INIS)

    Stormont, J.C.

    1990-11-01

    Numerous gas flow measurements have been made at the Waste Isolation Pilot Plant (WIPP) Facility horizon during 1988. All tests have been pressure decay or constant pressure tests from single boreholes drilled from the underground excavations. The test fluid has been nitrogen. The data have been interpreted as permeabilities and porosities by means of a transient numerical solution method. A closed-form steady-state approximation provides a reasonable order-of-magnitude permeability estimate. The effective resolution of the measurement system is less than 10 -20 m 2 . Results indicate that beyond 1 to 5 m from an excavation, the gas flow is very small and the corresponding permeability is below the system resolution. Within the first meter of an excavation, the interpreted permeabilities can be 5 orders of magnitude greater than the undisturbed or far-field permeability. The interpreted permeabilities in the region between the undisturbed region and the first meter from an excavation are in the range of 10 -16 to 10 -20 m 2 . Measurable gas flow occurs to a greater depth into the roof above WIPP excavations of different sizes and ages than into the ribs and floor. The gas flows into the formation surrounding the smallest excavation tested are consistently lower than those at similar locations surrounding larger excavations of comparable age. Gas flow measured in the interbed layers near the WIPP excavations is highly variable. Generally, immediately above and below excavations, relatively large gas flow is measured in the interbed layers. These results are consistent with previous measurements and indicate a limited disturbed zone surrounding WIPP excavations. 31 refs., 99 figs., 5 tabs

  2. Joint state of Colorado-US Department of Energy WIPP Shipment Exercise Program: TRANSAX '90

    International Nuclear Information System (INIS)

    1990-01-01

    In July 1990, the United States Secretary of Energy requested the DOE conduct a transportation emergency exercise before the end of CY 1990. The tasking was subsequently directed to the Director of DOE's Office of Environmental Restoration and Waste Management (EM) to plan and conduct an exercise, based on a Waste Isolation Pilot Plant (WIPP) shipment scenario. The state of Colorado was asked to participate. Colorado, in turn, invited the DOE to integrate the exercise into its own series of WIPP-related tabletop and field exercises for which the state had already begun planning. The result was a joint USDOE/Colorado full-scale (orientation) exercise called Transportation Accident Exercise 1990 (TRANSAX '90). The state of Colorado's exercise program was a follow-on to previously conducted classroom training. The program would serve to identify and resolve outstanding issues concerning inspections of the WIPP shipment transporter as it entered and passed through the state on the designated Interstate 25 transportation corridor; criteria for movement under various adverse weather and road conditions; and emergency response to accidents occurring in an urban or rural environment. The USDOE designed its participation in the exercise program to test selected aspects of the DOE Emergency Management System relating to response to and management of DOE off-site transportation emergencies involving assistance to state and local emergency response personnel. While a number of issues remain under study for ultimate resolution, others have been resolved and will become the basis for emergency operations plans, SOPs, mutual aid agreements, and checklist upgrades. Concurrently, the concentrated efforts at local, state, and federal levels in dealing with WIPP- related activities during this exercise program development have given renewed impetus to all parties as the beginning of actual shipments draws nearer. Three tabletop scenarios are discussed in this report

  3. The influence of salt aerosol on alpha radiation detection by WIPP continuous air monitors

    International Nuclear Information System (INIS)

    Bartlett, W.T.; Walker, B.A.

    1996-01-01

    Alpha continuous air monitors (CAMs) will be used at the Waste Isolation Pilot Plant (WIPP) to measure airborne transuranic radioactivity that might be present in air exhaust or in work-place areas. WIPP CAMs are important to health and safety because they are used to alert workers to airborne radioactivity, to actuate air-effluent filtration systems, and to detect airborne radioactivity so that the radioactivity can be confined in a limited area. In 1993, the Environmental Evaluation Group (EEG) reported that CAM operational performance was affected by salt aerosol, and subsequently, the WIPP CAM design and usage were modified. In this report, operational data and current theories on aerosol collection were reviewed to determine CAM quantitative performance limitations. Since 1993, the overall CAM performance appears to have improved, but anomalous alpha spectra are present when sampling-filter salt deposits are at normal to high levels. This report shows that sampling-filter salt deposits directly affect radon-thoron daughter alpha spectra and overall monitor efficiency. Previously it was assumed that aerosol was mechanically collected on the surface of CAM sampling filters, but this review suggests that electrostatic and other particle collection mechanisms are more important than previously thought. The mechanism of sampling-filter particle collection is critical to measurement of acute releases of radioactivity. 41 refs

  4. Hydraulic fracturing tests in anhydrite interbeds in the WIPP, Marker Beds 139 and 140

    Energy Technology Data Exchange (ETDEWEB)

    Howard, C L [RE/SPEC Inc., Albuquerque, NM (United States); Wawersik, W. R.; Carlson, L. V.; Henfling, J. A.; Borns, D. J.; Beauheim, R. L.; Roberts, R. M.

    1997-05-01

    Hydraulic fracturing tests were integrated with hydrologic tests to estimate the conditions under which gas pressure in the disposal rooms in the Waste Isolation Pilot Plant, Carlsbad, NM (WIPP) will initiate and advance fracturing in nearby anhydrite interbeds. The measurements were made in two marker beds in the Salado formation, MB139 and MB140, to explore the consequences of existing excavations for the extrapolation of results to undisturbed ground. The interpretation of these measurements is based on the pressure-time records in two injection boreholes and several nearby hydrologic observation holes. Data interpretations were aided by post-test borehole video surveys of fracture traces that were made visible by ultraviolet illumination of fluorescent dye in the hydraulic fracturing fluid. The conclusions of this report relate to the upper- and lower-bound gas pressures in the WIPP, the paths of hydraulically and gas-driven fractures in MB139 and MB140, the stress states in MB139 and MB140, and the probable in situ stress states in these interbeds in undisturbed ground far away from the WIPP.

  5. Champion for radioactive waste disposal host of the WIPP: Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    Rempe, N.T.

    1995-01-01

    The city of Carlsbad, New Mexico, volunteered to host the United States' first final repository for radioactive waste. Carlsbad citizens and their leaders understood that after decades of accumulating waste, the time had come to close the nuclear cycle. They therefore agreed to support the Waste Isolation Pilot Plant (WIPP), provided the project would not endanger its neighbors or the environment. The southeastern New Mexico area offers several advantages for deep geologic waste disposal: The regional geology is well understood. Massive salt beds are an excellent repository medium. Decades of potash mining experience inspired confidence in that concept. In underground nuclear test in the salt had caused no harm. And the city was seeking opportunities to diversify its economic base. Through the growth of the project, beginning in 1971, Carlsbad has demonstrated unwavering commitment, patience, and persistence. Without these attitudes, the WIPP would certainly not be where it is today and most likely would not exist at all. Civic leaders made the critical difference as the project weathered repeated challenges. With the support of their constituents, they foiled anti-nuclear obstructionism and advanced the project at every turn, frequently on their own time and at their own expense. The WIPP is now scheduled to start disposal in 1998, after a ten-year delay from its originally intended opening date. If it still has a realistic chance to start operations before the end of the century, the credit must in no small measure go to the city and the citizens of Carlsbad, New Mexico

  6. Position paper on flammability concerns associated with TRU waste destined for WIPP

    International Nuclear Information System (INIS)

    1991-04-01

    The Waste Isolation Pilot Plant (WIPP), in southeastern New Mexico,is an underground repository, designed for the safe geologic disposal of transuranic (TRU) wastes generated from defense-related activities of the US Department of Energy (DOE). The WIPP storage rooms are mined in a bedded salt (halite) formation, and are located 2150 feet below the surface. After the disposal of waste in the storage rooms, closure of the repository is expected to occur by creep (plastic flow) of the salt formation, with the waste being permanently isolated from the surrounding environment. This paper has evaluated the issue of flammability concerns associated with TRU waste to be shipped to WIPP, including a review of possible scenarios that can potentially contribute to the flammability. The paper discusses existing regulations that address potential flammability concerns, presents an analysis of previous flammability-related incidents at DOE sites with respect to the current regulations, and finally, examines the degree of assurance these regulations provide in safeguarding against flammability concerns during transportation and waste handling. 50 refs., 7 figs., 7 tabs

  7. Technical evaluation of WIPP by the New Mexico environmental evaluation group

    International Nuclear Information System (INIS)

    Neill, R.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) is a repository under construction in southeastern New Mexico for the disposal of 14.1 million curies of defense transuranic (TRU) waste. The US Department of Energy (DOE) plans to start storing waste in the underground facility in October 1988 for a 5-yr research and demonstration period. Since the State of New Mexico had a number of concerns in 1978 regarding the impact on health and safety of the proposed WIPP facility for disposal of radioactive waste, the DOE agreed to fund an independent technical review and evaluation of the planned repository, resulting in the creation of the Environmental Evaluation Group (EEG). This full-time multidisciplinary group has published 39 major reports to date, testified before the New Mexico Legislature and the US Congress, and has disseminated the results of analyses to DOE, the governor, the legislature, the Congress, the scientific community, and the general public. While the disposal of radioactive defense mill tailings and defense high-level wastes are both subject to US Nuclear Regulatory Commission (NRC) licensing, Congress specifically chose not to have defense TRU waste disposal licensed by the NRC. This has placed a heavy burden on EEG as the only full-time technical review agency on WIPP, but without regulatory authority

  8. Politics and technology in repository siting: military versus commercial nuclear wastes at WIPP 1972-1985

    International Nuclear Information System (INIS)

    Downey, G.L.

    1985-01-01

    During the 1970s, attempts by the federal government to develop a comprehensive system for disposing of nuclear wastes in geologic repositories were plagued by two related political problems; (1) whether or not military and commercial wastes should be buried together in the same repository, and (2) how to define the host state's role in the repository siting mechanism. This article explains why these two problems were connected by showing how they proved to be of decisive importance in the development of the Waste Isolation Pilot Plant (WIPP) project in Carlsbad, New Mexico. Although WIPP was initially conceived as a wholly military facility, The Department of Energy triggered a three-year dispute over the project's scope by proposing in 1978 to include commercial wastes in the repository. The key issue in the dispute concerned the political legitimacy of decision-making mechanisms for repository siting, which depend upon the extent to which they both adequately represent the interests of affected groups and meet an indistinct technical/political criterion of acceptable safety. DOE's ill-fated proposal to mix military and commercial disposal at WIPP demonstrated that the two rely on somewhat different conditions for their legitimacy. The agency overlapped the legitimate authorities of the federal and state governments and gave itself the hopeless task of negotiating a new boundary between them. 50 references, 3 figures

  9. Analysis of the potential formation of a Breccia chimney beneath the WIPP repository

    International Nuclear Information System (INIS)

    Spiegler, P.

    1982-05-01

    This report evaluates the potential formation of a Breccia pipe beginning at the Bell Canyon aquifer beneath the WIPP repository and the resulting release of radioactivity to the surface. Rock mechanics considerations indicate that the formation of a Breccia pipe by collapse of a cavern is not reasonable. Even if rock mechanics is ignored, the overlying strata act as a barrier and would prevent the release of radioactivity to the biosphere. Gradual formation of a Breccia pipe is so slow that the plutonium-239 in the waste (one of the most important long-lived components) would decay during formation. If Bell Lake and San Simon Sinks are the surface manifestation of a regional deep dissolution wedge, such a wedge is too far removed to represent pipe forming activity near the WIPP site. The formation of a Breccia pipe under the WIPP repository is highly unlikely. If it did occur, the concentration of plutonium-239 in brine reaching the surface would be less than the maximum permissible concentration in water specified in the Code of Federal Regulation Title 10, part 20

  10. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2016-01-01

    Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 1er novembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel La permanence suivante aura lieu le mardi 29 novembre 2016. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/ Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php  

  11. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 31 octobre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel La permanence suivante aura lieu le mardi 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/ Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  12. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 29 août de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/ Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php  

  13. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 28 novembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/ Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  14. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 30 mai de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/ Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  15. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 26 septembre de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 31 octobre et 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/ Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  16. EPA's Radioactive Source Program

    International Nuclear Information System (INIS)

    Kopsick, D.

    2004-01-01

    The US EPA is the lead Federal agency for emergency responses to unknown radiological materials, not licensed, owned or operated by a Federal agency or an Agreement state (Federal Radiological Emergency Response Plan, 1996). The purpose of EPA's clean materials programme is to keep unwanted and unregulated radioactive material out of the public domain. This is achieved by finding and securing lost sources, maintaining control of existing sources and preventing future losses. The focus is on both, domestic and international fronts. The domestic program concentrates on securing lost sources, preventing future losses, alternative technologies like tagging of radioactive sources in commerce, pilot radioactive source roundup, training programs, scrap metal and metal processing facilities, the demolition industry, product stewardship and alternatives to radioactive devices (fewer radioactive source devices means fewer orphan sources). The international program consists of securing lost sources, preventing future losses, radiation monitoring of scrap metal at ports and the international scrap metal monitoring protocol

  17. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 31 janvier de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 28 février, 28 mars, 25 avril, 30 mai, 29 août, 26 septembre, 31 octobre et 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. e-mail : gac-epa@gac-epa.org.

  18. EPA Team Helps Water Systems Comply with New Bacteria Monitoring Rule

    Science.gov (United States)

    An EPA team issued nearly 200 Administrative Orders in support of Pennsylvania and Virginia to ensure that small public water systems followed new requirements for more frequent bacteria monitoring of their water supplies.

  19. Guidance for Incorporating Environmental Justice Concerns in EPA's National Environmental Policy Act (NEPA) Compliance Analyses

    Science.gov (United States)

    The document defines the approaches by which EPA will ensure that disproportionately high and adverse human health or environmental effects on minority communities and low-income communities are identified and addressed.

  20. Communication equipment radiation resistance ensurance

    International Nuclear Information System (INIS)

    Myrova, L.O.; Chelizhenko, A.Z.

    1983-01-01

    A review of works on radiation resistance of electronic equipment (epsilon epsilon) for 15 years is presented. The effect of ionizing radiation appearing as a result of nuclear explosions in nuclear facilities and in outerspace on epsilon epsilon has been considered. Types of radiation effects in epsilon epsilon, radiation effect on semiconductor devices and integrated circUits, types of epsilon epsilon failures, as well as the procass of radiation-resistant epsilon epsilon designing and selection of its main parameters have been described. The methods of epsilon epsilon flowsheet optimization, application of mathematical simulation and peculiarities of ensurance of epsilon epsilon radiation resistance of communication systems are considered. Peculiarities of designing of radiation-resistant quartz generators, secondary power supply sources and amplifiers are discussed

  1. Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA

    International Nuclear Information System (INIS)

    Thakur, P.

    2016-01-01

    After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m 3 for 241 Am and 10.2 μBq/m 3 for 239+240 Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m 3 of 241 Am and 5.8 μBq/m 3 of 239+240 Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and

  2. Systems analysis, long-term radionuclide transport, and dose assessments, Waste Isolation Pilot Plant (WIPP), southeastern New Mexico, September 1989

    International Nuclear Information System (INIS)

    Lappin, A.R.; Hunter, R.L.; Davies, P.B.; Borns, D.J.; Reeves, M.; Pickens, J.; Iuzzolino, H.J.

    1990-12-01

    This study supports the Waste Isolation Pilot Plant (WIPP) Final Supplemental Environmental Impact Statement and has two main objectives. First, it describes current ideas about the characteristics and potential impacts of the disturbed-rock zone (DRZ) known to develop with time around excavations at the WIPP horizon. Second, it presents new calculations of radionuclide migration within and from the WIPP repository for steady-state undisturbed conditions and for two cases that consider human intrusion into the repository. At the WIPP, the presence of a DRZ has been confirmed by geophysical studies, gas-flow tests, and direct observations. The DRZ will allow gas or brine from waste-emplacement panels to bypass panel seals and flow into adjacent portions of the underground workings unless preventive measures are taken. Revised calculations of the undisturbed performance of the repository indicate that no radionuclides will be released into the Culebra Dolomite within the regulatory period of 10,000 years. The human-intrusion calculations included here assume a connection between the WIPP repository, an occurrence of pressurized brine within the underlying Castile Formation, and the overlying Culebra Dolomite. 61 refs., 40 figs., 16 tabs

  3. US EPA Region 4 Brownfields

    Science.gov (United States)

    To improve public health and the environment, the United States Environmental Protection Agency (USEPA) collects information about facilities, sites, or places subject to environmental regulation or of environmental interest. Through the Geospatial Data Download Service, the public is now able to download the EPA Geodata shapefile containing facility and site information from EPA's national program systems. The file is Internet accessible from the Envirofacts Web site (https://www3.epa.gov/enviro/). The data may be used with geospatial mapping applications. (Note: The shapefile omits facilities without latitude/longitude coordinates.) The EPA Geospatial Data contains the name, location (latitude/longitude), and EPA program information about specific facilities and sites. In addition, the file contains a Uniform Resource Locator (URL), which allows mapping applications to present an option to users to access additional EPA data resources on a specific facility or site. This dataset shows Brownfields listed in the 2012 Facility Registry System.

  4. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 25 avril de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 30 mai, 29 août, 26 septembre, 31 octobre et 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  5. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 28 février de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 28 mars, 25 avril, 30 mai, 29 août, 26 septembre, 31 octobre et 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  6. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 28 mars de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 25 avril, 30 mai, 29 août, 26 septembre, 31 octobre et 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  7. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2017-01-01

    Le GAC organise des permanences avec entretiens individuels qui se tiennent le dernier mardi de chaque mois, sauf en juin, juillet et décembre. La prochaine permanence se tiendra le : Mardi 30 mai de 13 h 30 à 16 h 00 Salle de réunion de l’Association du personnel Les permanences suivantes auront lieu les mardis 29 août, 26 septembre, 31 octobre et 28 novembre 2017. Les permanences du Groupement des Anciens sont ouvertes aux bénéficiaires de la Caisse de pensions (y compris les conjoints survivants) et à tous ceux qui approchent de la retraite. Nous invitons vivement ces derniers à s’associer à notre groupement en se procurant, auprès de l’Association du personnel, les documents nécessaires. Informations : http://gac-epa.org/. Formulaire de contact : http://gac-epa.org/Organization/ContactForm/ContactForm-fr.php

  8. Electrostatic Plasma Accelerator (EPA)

    Science.gov (United States)

    Brophy, John R.; Aston, Graeme

    1995-01-01

    The application of electric propulsion to communications satellites, however, has been limited to the use of hydrazine thrusters with electric heaters for thrust and specific impulse augmentation. These electrothermal thrusters operate at specific impulse levels of approximately 300 s with heater powers of about 500 W. Low power arcjets (1-3 kW) are currently being investigated as a way to increase specific impulse levels to approximately 500 s. Ion propulsion systems can easily produce specific impulses of 3000 s or greater, but have yet to be applied to communications satellites. The reasons most often given for not using ion propulsion systems are their high level of overall complexity, low thrust with long burn times, and the difficulty of integrating the propulsion system into existing commercial spacecraft busses. The Electrostatic Plasma Accelerator (EPA) is a thruster concept which promises specific impulse levels between low power arcjets and those of the ion engine while retaining the relative simplicity of the arcjet. The EPA thruster produces thrust through the electrostatic acceleration of a moderately dense plasma. No accelerating electrodes are used and the specific impulse is a direct function of the applied discharge voltage and the propellant atomic mass.

  9. Summary of site-characterization studies conducted from 1983 through 1987 at the Waste Isolation Pilot Plant (WIPP) site, southeastern New Mexico

    International Nuclear Information System (INIS)

    Lappin, A.R.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) is being excavated at a depth of approximately 655 m in bedded halites. Site-characterization activities at the WIPP site began in 1976. Characterization activities since 1983 have had the objective of updating the conceptual model for the geologic and hydrologic behavior of the WIPP site and vicinity. This paper discusses aspects of the general conceptual model significant to both site characterization and performance assessment. The geological and hydrologic behavior of the WIPP site and vicinity is transient, and has been transient since at least deposition of the Permian Salado Formation containing the underground workings of the WIPP facility. The Salado Formation deforms regionally in response to gravity, but is very low in permeability, except within approximately two meters of the WIPP facility. The Culebra Dolomite Member of the Rustler Formation dominates the hydrology at the WIPP site. Hydrologic measurements, geologic studies, major-element and minor-element distributions in Culebra fluids, and the results of isotopic studies (stable-isotope, radiocarbon, uranium-disequilibrium, and 87 Sr/ 86 Sr) are consistent with the interpretations that, although the Culebra dominates flow within the Rustler at the WIPP site and Rustler karst is not present, there has been limited vertical fluid movement within the Rustler and between the Rustler and the overlying Dewey Lake Red Beds

  10. Expert (Peer) Reviews at the Waste Isolation Pilot Plant (WIPP): Making Complex Information and Decision Making Transparent

    International Nuclear Information System (INIS)

    Eriksson, Leif G.

    2001-01-01

    On the 18th of May 1998, based on the information provided by the United Sates Department of Energy (DOE) in support of the 1996 Waste Isolation Pilot Plant (WIPP) Compliance Certification Application, the U.S. Environmental Protection Agency certified the proposed deep geological repository for disposal of long-lived, defense-generated, transuranic radioactive waste at the WIPP site in New Mexico, United States of America, was compliant with all applicable radioactive waste disposal regulations. Seven domestic and one joint international peer reviews commissioned by the DOE were instrumental in making complex scientific and engineering information, as well as the related WIPP decision-making process, both credible and transparent to the majority of affected and interested parties and, ultimately, to the regulator

  11. Construction of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Munson, D.E.; Matalucci, R.V. [Sandia National Lab., Albuquerque, NM (United States); Hoag, D.L.; Blankenship D.A. [RE/SPEC Inc., Albuquerque, NM (United States)] [and others

    1997-02-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories has the responsibility for experimental activities at the WIPP and has emplaced several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The construction of the tests relied heavily on earlier excavations at the WIPP site to provide a basis for selecting excavation, surveying, and instrumentation methods, and achievable construction tolerances. The tests were constructed within close tolerances to provide consistent room dimensions and accurate placement of gages. This accuracy has contributed to the high quality of data generated which in turn has facilitated the comparison of test results to numerical predictions. The purpose of this report is to detail the construction activities of the TSI tests.

  12. Construction of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Munson, D.E.; Matalucci, R.V.; Hoag, D.L.; Blankenship D.A.

    1997-02-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories has the responsibility for experimental activities at the WIPP and has emplaced several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The construction of the tests relied heavily on earlier excavations at the WIPP site to provide a basis for selecting excavation, surveying, and instrumentation methods, and achievable construction tolerances. The tests were constructed within close tolerances to provide consistent room dimensions and accurate placement of gages. This accuracy has contributed to the high quality of data generated which in turn has facilitated the comparison of test results to numerical predictions. The purpose of this report is to detail the construction activities of the TSI tests

  13. The WIPP PC based data collection program for real time data capture from the Eberline Alpha Air Monitor

    International Nuclear Information System (INIS)

    Hofer, D.A.; Clayton, S.G.

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) needed the capability to evaluate the performance of the Eberline Alpha Continuous Air Monitors (CAMs). An additional goal was to characterize and document the Radon background activity at various locations above and below ground at the WIPP. A PC based data collection system was developed to continuously collect information used to evaluate the CAMs' performance and document the operability of the Alpha monitoring program at the WIPP. To accomplish the stated objectives, Westinghouse Radiation Monitoring Systems Engineering modified an existing Eberline CAM supervision and control program to include real time data collection. The paper will address the specific hardware requirements for program usage, the functional structure of the program, and the actions required for an operator to generate graphical output. The utilization of the information generated and the future plans for the expansion and networking of the data collection system also be presented

  14. Expert (Peer) Reviews at the Waste Isolation Pilot Plant (WIPP): Making Complex Information and Decision Making Transparent

    Energy Technology Data Exchange (ETDEWEB)

    Eriksson, Leif G. [GRAM, Inc., Albuquerque, NM (United States)

    2001-07-01

    On the 18th of May 1998, based on the information provided by the United Sates Department of Energy (DOE) in support of the 1996 Waste Isolation Pilot Plant (WIPP) Compliance Certification Application, the U.S. Environmental Protection Agency certified the proposed deep geological repository for disposal of long-lived, defense-generated, transuranic radioactive waste at the WIPP site in New Mexico, United States of America, was compliant with all applicable radioactive waste disposal regulations. Seven domestic and one joint international peer reviews commissioned by the DOE were instrumental in making complex scientific and engineering information, as well as the related WIPP decision-making process, both credible and transparent to the majority of affected and interested parties and, ultimately, to the regulator.

  15. Department of Energy Operation Quality Assurance Program for the Waste Isolation Pilot Plant (WIPP) Project (Carlsbad, New Mexico)

    International Nuclear Information System (INIS)

    1987-12-01

    The purpose of this plan is to describe the Quality Assurance (QA)reverse arrow Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Project Participants: the Scientific Advisor (Sandia National Laboratory) and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the Pre-Operational and Operational phases of the WIPP Project not addressed under the construction phase. This plan also requires the QA Programs for DOE and Project Participants to be structured so as to comply with this plan and ANSI-ASME NQA-1. The prime responsibility for Operational Quality Assurance rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Scientific Advisor and the Management and Operating Contractor. Overviews of selected operational and testing activities will be are conducted in accordance with prescribed requirements and that adequate documentation of these activities is maintained. 4 figs

  16. Regional water balance for the Waste Isolation Pilot Plant (WIPP) site and surrounding area

    International Nuclear Information System (INIS)

    Hunter, R.L.

    1985-12-01

    The WIPP water-balance study area defined here comprises approx.2000 mi 2 in Eddy and Lea Counties, southeastern New Mexico. Inflows to the study area are precipitation (roughly 1.47 x 10 6 ac-ft/y), surface water (roughly 1.1 x 10 5 ac-ft/y), water imported by municipalities and industries (roughly 3 x 10 4 ac-ft/y), and ground water (volume not estimated). Outflows from the area are evapotranspiration (roughly 1.5 x 10 6 ac-ft/y), surface water (roughly 1.2 x 10 5 ac-ft/y), and possibly some ground water. The volume of surface and ground water in storage in Nash Draw has increased since the beginning of potash refining. Regional ground-water flow in aquifers above the Salado Formation is from the northeast to the southwest, although this pattern is interrupted by Clayton Basin, Nash Draw, and San Simon Swale. The Pecos River is the only important perennial stream. Most of the area has no integrated surface-water drainage. The available data suggest that approx.1600 mi 2 of the study area are hydrologically separate from Nash Draw and the WIPP site. Ground water north of Highway 180 apparently discharges into Clayton Basin and evaporates. Water in San Simon Swale apparently percolates downward and flows to the southeast. Data are inadequate to create a water budget for the Nash Draw-WIPP site hydrologic system alone, although an attempt to do so can provide guidance for further study

  17. Entrustable professional activity (EPA) reshapes the practice of specialist training.

    Science.gov (United States)

    Niemi-Murola, Leila

    In addition to medical expertise, competence-based medical training comprises communication and collaboration skills, professionalism, and leadership skills. Continuous feedback is essential for learning and development, and feedback only from the medical specialist examination taken in the end of training does not ensure thorough specialist training. Entrustable professional activity (EPA) is a unit of professional practice, defined as tasks or responsibilities typical of the specialty. EPA translates competence-based training into manageable and meaningful entities and provides tools for the evaluation of medical competence.

  18. Brine transport studies in the bedded salt of the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    McTigue, D.F.; Nowak, E.J.

    1987-01-01

    Brine flow has been measured to unheated boreholes for periods of a few days and to heated holes for two years in the WIPP facility. It is suggested that Darcy flow may dominate the observed influx of brine. Exact solutions to a linearized model for one-dimensional, radial flow are evaluated for conditions approximating the field experiments. Flow rates of the correct order of magnitude are calculated for permeabilities in the range 10 -21 to 10 -20 m 2 (1 to 10 nanodarcy) for both the unheated and heated cases. 20 refs., 3 figs., 1 tab

  19. NMT-7 plan for producing certifiable TRU debris waste for WIPP

    International Nuclear Information System (INIS)

    Montoya, A.J.

    1997-12-01

    Analysis of waste characterization data for debris items generated during a recent six month period indicates that the certifiability of TRUPACT II payload containers packaged at the Los Alamos National Laboratory Plutonium Facility (TA-55) can be increased from approximately 52% of solid waste payload containers to 78% by applying the simple strategies of screening out high decay heat items and sorting remaining items to maintain nuclear material loading at levels below WIPP waste acceptance limits. Implementation of these strategies will have negative impacts on waste minimization and waste management operations that must also be considered

  20. Basic data report for drillhole H-12 (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    Mercer, J.W.; Snyder, R.P.

    1990-01-01

    Drillhole H-12 was drilled where hydraulic data were needed to better establish flow characteristics existing south-southeast of the WIPP site. The fluid-bearing zones of interest are the Magenta and Culebra dolomite units of the Rustler Formation. Dissolution of halite in the Rustler Formation has occurred in the uppermost member, but has not yet begun in the lower halite-bearing members. Cuttings and cores were taken at selected intervals and geophysical logs were run over the entire depth of the hole. 3 refs., 2 figs., 3 tabs

  1. Potential problems from shipment of high-curie content contact-handled transuranic (CH-TRU) waste to WIPP

    International Nuclear Information System (INIS)

    Neill, R.H.; Channell, J.K.

    1983-08-01

    There are about 1000 drums of contact-handled transuranic (CH-TRU) wastes containing more than 100 Ci/drum of Pu-238 that are stored at the Savannah River Plant and at the Los Alamos National Laboratory. Studies performed at DOE laboratories have shown that large quantities of gases are generated in stored drums containing 100 Ci of 238 Pu. Concentrations of hydrogen gas in the void space of the drums are often found to be high enough to be explosive. None of the analyses in the DOE WIPP Final Environmental Impact Statement, Safety Analysis Report, and Preliminary Transportation Analysis have considered the possibility that the generation of hydrogen gas by radiolysis may create an explosive or flammable hazard that could increase the frequency and severity of accidental releases of radionuclides during transportation or handling. These high 238 Pu concentration containers would also increase the estimated doses received by individuals and populations from transportation, WIPP site operations, and human intrusion scenarios even if the possibility of gas-enhanced releases is ignored. The WIPP Project Office has evaluated this effect on WIPP site operations and is suggesting a maximum limit of 140 239 Pu equivalent curies (P-Ci) per drum so that postulated accidental off-site doses will not be larger than those listed in the FEIS. The TRUPACT container, which is being designed for the transportation of CH-TRU wastes to WIPP, does not appear to meet the Nuclear Regulatory Commission regulations requiring double containment for the transportation of plutonium in quantities >20 Ci. A 20 alpha Ci/shipment limit would require about 200,000 shipments for the 4 million curies of alpha emitters slated for WIPP

  2. EPA's radon study results

    International Nuclear Information System (INIS)

    Dowd, R.M.

    1988-01-01

    Last winter, in cooperation with agencies in 10 states and two metropolitan area counties, EPA measured the indoor air radon concentrations of 14,000 houses, some chosen statistically at random and some by request of the homeowner. Passive measurement methodologies were used, such as exposing a charcoal canister to the air for a few days and allowing the air to migrate in to the charcoal naturally. To reduce dilution of radon by the outside air, the protocol required that the house be shut up; therefore, the study was conducted during winter. The measuring device was placed in the lowest livable area (usually the basement) of each house to maximize potential concentration. It should be noted that these procedures are generally considered to be screening tests because they result in a worst-case measurement rather than a best value. The results of these findings are presented

  3. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Chapter D, Appendix D1 (beginning), Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Lappin, A. R.

    1993-03-01

    The Waste Isolation Pilot Plant (WIPP), which is designed for receipt, handling, storage, and permanent isolation of defense-generated transuranic wastes, is being excavated at a depth of approximately 655 m in bedded halites of the Permian Salado Formation of southeastern New Mexico. Site-characterization activities at the present WIPP site began in 1976. Full construction of the facility began in 1983, after completion of ``Site and Preliminary Design Validation`` (SPDV) activities and reporting. Site-characterization activities since 1983 have had the objectives of updating or refining the overall conceptual model of the geologic, hydrologic, and structural behavior of the WIPP site and providing data adequate for use in WIPP performance assessment. This report has four main objectives: 1. Summarize the results of WIPP site-characterization studies carried out since the spring of 1983 as a result of specific agreements between the US Department of Energy and the State of New Mexico. 2. Summarize the results and status of site-characterization and facility-characterization studies carried out since 1983, but not specifically included in mandated agreements. 3. Compile the results of WIPP site-characterization studies into an internally consistent conceptual model for the geologic, hydrologic, geochemical, and structural behavior of the WIPP site. This model includes some consideration of the effects of the WIPP facility and shafts on the local characteristics of the Salado and Rustler Formations. 4. Discuss the present limitations and/or uncertainties in the conceptual geologic model of the WIPP site and facility. The objectives of this report are limited in scope, and do not include determination of whether or not the WIPP Project will comply with repository-performance criteria developed by the US Environmental Protection Agency (40CFR191).

  4. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 3, Model parameters: Sandia WIPP Project

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-29

    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.

  5. Groundwater flow in the Rustler Formation, Waste Isolation Pilot Plant (WIPP), southeast New Mexico (SENM). Interim report

    International Nuclear Information System (INIS)

    Gonzalez, D.D.

    1983-03-01

    In hypothetical breach scenarios for the WIPP, the Culebra Dolomite in the Rustler Formation has historically been considered the aquifer most likely to play a significant role in transporting radioisotopes to the biosphere. Recently, it was determined that breach scenarios involving connection of aquifers above and below the Salado Formation where waste emplacement is planned would not result in an upward flow of water into the Rustler aquifers. Considerable hydrologic investigation has focused on the Culebra, since some scenarios might result in contamination of this aquifer. In such events the Culebra would provide more rapid transport of radioisotopes from the WIPP than any of the other aquifers in the WIPP area. Hydrologic tests conducted in three-well arrays at four different locations near the WIPP are described. Tracer tests at the H-6 wells northwest of the WIPP indicated an effective porosity of 0.007 in the principal direction of flow and a dispersivity of 33 ft. At the H-2 wells, 1-1/4 mi W-SW of the center of the WIPP site, the effective porosity in the principal flow direction is 0.18 and the dispersivity is 17 ft. Anisotropy of transmissivity was determined from pumping tests at the H-4, H-5, and H-6 wells. The principal direction of transmissivity is roughly NW-SE at all three locations. The ratio of the major-to-minor transmissivity components varies only from 2.1 to 2.7, even though the transmissivity itself varies three orders of magnitude among the three locations. This information, coupled with transmissivity and head potential data, indicates that flow patterns near the WIPP site are toward the southeast. Present estimates for flow rates are 1 to 10 ft/y. Values of transmissivity for the Culebra vary six orders of magnitude over the extent of the study area, decreasing monotonically from 10 3 ft 2 /d in Nash Draw to 10 - 3 ft 2 /d on the east side of the WIPP site

  6. EPA Research in Alaska

    Science.gov (United States)

    EPA’s collaboration with the DEC and the Air Force on PFAS sampling and analytical methods is key to ensuring valid, defensible data are collected on these emerging contaminants that are being found in soil, groundwater and drinking water in Alaska.

  7. EPA's Information Architecture and Web Taxonomy

    Science.gov (United States)

    EPA's Information Architecture creates a topical organization of our website, instead of an ownership-based organization. The EPA Web Taxonomy allows audiences easy access to relevant information from EPA programs, by using a common vocabulary.

  8. The WIPP research and development program: providing the technical basis for defense waste disposal

    International Nuclear Information System (INIS)

    Hunter, Th.O.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

  9. WIPP Sampling and Analysis Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2000-01-01

    This Sampling and Analysis Plan (SAP) has been prepared to fulfill requirements of Module VII, Section VII.M.2 and Table VII.1, requirement 4 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED [New Mexico Environment Department], 1999a). This SAP describes the approach for investigation of the Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. This SAP addresses the current Permit requirements for a RCRA Facility Investigation(RFI) investigation of SWMUs and AOCs. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the RFI specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI work plan and report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can beentered either before or after a RFI work plan. According to NMED's guidance, a facility can prepare a RFI work plan or SAP for any SWMU or AOC (NMED, 1998).

  10. A sensitivity analysis of the WIPP disposal room model: Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Labreche, D.A.; Beikmann, M.A. [RE/SPEC, Inc., Albuquerque, NM (United States); Osnes, J.D. [RE/SPEC, Inc., Rapid City, SD (United States); Butcher, B.M. [Sandia National Labs., Albuquerque, NM (United States)

    1995-07-01

    The WIPP Disposal Room Model (DRM) is a numerical model with three major components constitutive models of TRU waste, crushed salt backfill, and intact halite -- and several secondary components, including air gap elements, slidelines, and assumptions on symmetry and geometry. A sensitivity analysis of the Disposal Room Model was initiated on two of the three major components (waste and backfill models) and on several secondary components as a group. The immediate goal of this component sensitivity analysis (Phase I) was to sort (rank) model parameters in terms of their relative importance to model response so that a Monte Carlo analysis on a reduced set of DRM parameters could be performed under Phase II. The goal of the Phase II analysis will be to develop a probabilistic definition of a disposal room porosity surface (porosity, gas volume, time) that could be used in WIPP Performance Assessment analyses. This report documents a literature survey which quantifies the relative importance of the secondary room components to room closure, a differential analysis of the creep consolidation model and definition of a follow-up Monte Carlo analysis of the model, and an analysis and refitting of the waste component data on which a volumetric plasticity model of TRU drum waste is based. A summary, evaluation of progress, and recommendations for future work conclude the report.

  11. Petrographic study of evaporite deformation near the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Borns, D.J.

    1983-06-01

    The Delaware Basin of southeastern New Mexico contains about 1000 m of layered evaporites. Areas in the northern Delaware Basin, bordering the Capitan reef, have anomalous seismic reflection characteristics, such as loss in reflector continuity. Core from holes within this zone exhibits complex mesoscopic folds and extension structures. On a larger scale, anticlines and synclines are indicated by structure contours based on boreholes. The deformation is probably gravity-driven. Such a process is initiated by basin tilting during either a Mesozoic or Cenozoic period of uplift. Small-scale structures suggest that deformation was episodic with an early, syndepositional stage of isoclinal folding. Later, open-to-tight asymmetric folding is more penetrative and exhibits a sense of asymmetry opposite to that of the earlier isoclinal folding. The younger folds are associated with development of zonal crenulation cleavage and microboundinage of more competent carbonate layers. At the same time, halite beds developed dimensional fabrics and convolute folds in anhydrite stringers. Late-stage, near-vertical fractures formed in competent anhydrite layers. Microscopic textures exhibit rotated anhydrite porphyroblasts, stress shadow growth, and microboundinage. Except during late-stage deformation, anhydrite and halite recrystallized synkinematically. Drastic strength reduction in anhydrites through dynamic recrystallization occurs experimentally near 200 0 C. However, evaporites of the WIPP site never experienced temperatures > 40 0 C. Microscopic fabrics and P, T history of the evaporites suggest that pressure solution was the active mechanism during deformation of evaporites at the WIPP site

  12. Test plan: Gas-threshold-pressure testing of the Salado Formation in the WIPP underground facility

    International Nuclear Information System (INIS)

    Saulnier, G.J. Jr.

    1992-03-01

    Performance assessment for the disposal of radioactive waste from the United States defense program in the WIPP underground facility must assess the role of post-closure was generation by waste degradation and the subsequent pressurization of the facility. be assimilated by the host formation will Whether or not the generated gas can be assimilated by the host formation will determine the ability of the gas to reach or exceed lithostatic pressure within the repository. The purpose of this test plan is (1) to present a test design to obtain realistic estimates of gas-threshold pressure for the Salado Formation WIPP underground facility including parts of the formation disturbed by the underground of the Salado, and (2) to provide a excavations and in the far-field or undisturbed part framework for changes and amendments to test objectives, practices, and procedures. Because in situ determinations of gas-threshold pressure in low-permeability media are not standard practice, the methods recommended in this testplan are adapted from permeability-testing and hydrofracture procedures. Therefore, as the gas-threshold-pressure testing program progresses, personnel assigned to the program and outside observers and reviewers will be asked for comments regarding the testing procedures. New and/or improved test procedures will be documented as amendments to this test plan, and subject to similar review procedures

  13. Basic data report for Drillhole AEC 7 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1983-01-01

    AEC 7 is a borehole drilled in western Lea County, New Mexico, in section 31, T.21S.,R.32E. AEC 7 was drilled to 3918 feet in 1974 by Oak Ridge National Laboratory; Sandia deepened the hole to 4732 ft in 1979. The borehole provided stratigraphic and lithologic information in the initial and final drilling. The borehole was used extensively for tests of borehole plugs and plugging operations. AEC 7 penetrated, in descending order, Holocene sands and Mescalero caliche (8 ft), Santa Rosa Sandstone (109 ft), Dewey Lake Red Beds (542 ft), Rustler Formation (325 ft), Salado Formation (2014 ft), Castile Formation (1521 ft), and the upper Bell Canyon Formation (197 ft). Cores were obtained from much of the borehole. An extensive suite of geophysical logs provides information on stratigraphy, lithology, and structure. Beds were in normal stratigraphic sequence and without structural deformation except in the lower Castile. Anhydrite II and Halite II appear to be repeated in the borehole. This section was penetrated during deepening by Sandia; the structural complication is consistent with deformation found nearby in ERDA 6. The potential site on which AEC 7 is located was abandoned in 1976 after ERDA 6 was drilled. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  14. Geochemistry of Salado Formation brines recovered from the Waste Isolation Pilot Plant (WIPP) repository

    International Nuclear Information System (INIS)

    Abitz, R.; Myers, J.; Drez, P.; Deal, D.

    1990-01-01

    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

  15. Geochemistry of Salado formation brines recovered from the Waste Isolation Pilot Plant (WIPP) repository

    International Nuclear Information System (INIS)

    Abitz, R.; Myers, J.; Drez, P.; Deal, D.

    1990-01-01

    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 heterogeneous 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

  16. Conclusions from working group 2 - the analyses of the WIPP-2 experiments

    International Nuclear Information System (INIS)

    Jackson, C.P.

    1995-01-01

    The INTRAVAL WIPP-2 test case is based on data from site investigations carried out at the Waste Isolation Pilot Plant (WIPP) in New Mexico, USA. The site has been chosen as a potential location for a radioactive waste repository. Extensive investigations have been carried out, focused mainly on groundwater flow and transport in the Culebra Dolomite, the main pathway for transport of radionuclides off the site by groundwater in the case of an accidental borehole intrusion into the repository. Five teams studied the test case. Two teams addressed issues involved in the treatment of heterogeneity. Stochastic models and a Monte Carlo approach were used. One team quantified the increased uncertainty resulting from fewer data and explored the issues involved in validation of stochastic models. A second team developed a new method for conditioning stochastic models on head data. Two other teams examined issues relating to the choice of conceptual models. Two-dimensional vertical cross-section models were used to explore the importance of vertical flow. The fifth team advocate the use of a variety of models to highlight the most important processes and parameters. Conclusions from each team experiment are analysed. (J.S.). 4 refs., 11 figs

  17. Basic data report for drillhole AEC 8 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1983-01-01

    AEC 8 was originally drilled in 1974 to a depth of 3028 ft by Oak Ridge National Laboratory as part of the initial investigations of a site for radioactive waste disposal. In 1976, Sandia National Laboratories deepened the borehole from the top of the Castile Formation into the Bell Canyon Formation to test the hydraulic properties of the Bell Canyon. The borehole encountered in descending order Holocene sands (20 ft), Mescalero caliche (6 ft), Santa Rosa Sandstone (143 ft), Dewey Lake Redbeds (491 ft), Rustler Formation (322 ft), Salado Formation (1990 ft), Castile Formation (1335 ft), and the upper Bell Canyon Formation (603 ft). The borehole stratigraphy is in normal order and there is no significant deformation. An extensive suite of geophysical logs provides information on the lithology and stratigraphy. The potentiometric surfaces of Bell Canyon fluid-bearing zones are 550 ft (for the zone at 4821 ft to 4827 ft) and 565 ft below land surface (for the zone at 4844 to 4860 ft). The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  18. WIPP Sampling and Analysis Plan for Solid Waste Management Units and Areas of Concern

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2000-05-23

    This Sampling and Analysis Plan (SAP) has been prepared to fulfill requirements of Module VII, Section VII.M.2 and Table VII.1, requirement 4 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED [New Mexico Environment Department], 1999a). This SAP describes the approach for investigation of the Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. This SAP addresses the current Permit requirements for a RCRA Facility Investigation(RFI) investigation of SWMUs and AOCs. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the RFI specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI work plan and report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can beentered either before or after a RFI work plan. According to NMED's guidance, a facility can prepare a RFI work plan or SAP for any SWMU or AOC (NMED, 1998).

  19. Evaporite dissolution relevant to the WIPP site, northern Delaware Basin, southeastern New Mexico

    International Nuclear Information System (INIS)

    Lambert, S.J.

    1982-01-01

    Evaluation of the threat of natural dissolution of host evaporites to the integrity of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico has taken into consideration (1) the volume of missing rock salt, (2) the occurrence (or not) of characteristic dissolution brines, (3) geomorphic features, some of which are unrelated to dissolution, and (4) the time intervals over which dissolution may have been active. Even under the assumption that all missing halite was originally present and has been removed by dissolution, there is no evidence of active preferential removal of the lower Salado Formation halite by any geologically reasonable process. The geologic record contains evidence of dissolution in the Triassic and Jurassic; to constrain all removal of basinal halite to the late Cenozoic yields an unrealistically high rate of removal. Application to the lower Salado of a stratabound mechanism known to be active in Nash Draw, a near-surface feature within the Basin, allows a minimum survival time of 2,500,000 years to be predicted for the subsurface facility for storage of radioactive waste at WIPP. This calculation is based on an analysis of all known dissolution features in the Delaware Basin, and takes into account the wetter (pluvial) climate during the past 600,000 years. 2 figures, 1 table

  20. The WIPP decision plan: Charting the course for openness in the decision making process

    International Nuclear Information System (INIS)

    Hagers, J.

    1992-01-01

    In June of 1989, the Secretary of Energy requested that a plan be developed that would clearly outline the prerequisites to opening the Waste Isolation Pilot Plant (WIPP). It was to provide the basis for a decision making process that was not only visible to the public, but one which included public participation. It must also be dynamic enough to effectively deal with the changing legislative, regulatory, and technical environments. Based on a recognized need for openness, the Secretary's Draft Decision Plan was developed. The plan charted the course for ultimately making the decision to declare WIPP ready to receive waste for the start of test phase operations. It outlined to critics and supporters alike the rigorous and thorough process by which the internal decisions were made. The plan identified all internal prerequisites to the decision; charted the review cycles, and targeted the completion dates. It also outlined the processes outside the control of the Department, institutional issues, such as legislative land withdrawal, issuance of permits, and designation of transportation routes

  1. Potential release scenario and radiological consequence evaluation of mineral resources at WIPP

    International Nuclear Information System (INIS)

    Little, M.S.

    1982-05-01

    This report has reviewed certain of the natural resources which may be found at the site of the nuclear waste repository being considered for southeastern New Mexico, and discussed the scenarios which have been used to estimate the radiological consequences from the mining of these resources several hundred years after the radioactive waste has been emplaced. It has been concluded that the radiological consequences of the mining of potash or hydrocarbons (mostly natural gas) are probably bounded by the consequences of hydrologic breach scenarios already considered by the US Department of Energy, and by reports of EEG. These studies conclude that the resultant doses would not constitute a significant threat to public health. This report also evaluates the radiological consequences of solution mining of halite at the WIPP site. Although such mining in the Delaware Basin and particularly at the WIPP site, is not likely at the present time, significant economic, social or climatic changes a few hundred years after emplacement may make these resources more attractive. The DOE did not consider such mining at the site credible

  2. EPA Metadata Style Guide Keywords and EPA Organization Names

    Science.gov (United States)

    The following keywords and EPA organization names listed below, along with EPA’s Metadata Style Guide, are intended to provide suggestions and guidance to assist with the standardization of metadata records.

  3. EPA Office Points, Tutuila AS, 2009, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EPA office location in Tutila Island in American Samoa. American Samoa is an unincorporated and unorganized territory of the United States, and administered by...

  4. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2013-01-01

    Dear GAC-EPA members, This year, owing to works in the main Auditorium, we have to hold our General assembly in the auditorium of the Globe on 27 March 2013 and we really hope that you can be present. We wish to give you some preliminary practical recommendations: Do not forget your CERN access card, the guards may carry out checks. As far as possible, use public transport because there is very limited parking. If you come by car, park your vehicle on the car parks inside CERN because the outside car park cannot be used by visitors. Refreshments cannot be organized in the Globe; they will be held in cafeteria n°1, which will force us to move by using CERN entrances A or B or via building 33 (access cards required here too). We thank you for your attention and hope to see you soon. Le GAC organise chaque mois des permanences avec entretiens individuels. La prochaine permanence se tiendra le : Mardi 2 avril de 13 h 30 à 16 h 00 Salle de réunion de l&rsquo...

  5. GAC-EPA

    CERN Multimedia

    GAC-EPA

    2013-01-01

    En tant que Président du GAC-EPA, je porte à votre connaissance ce communiqué émanant de la Direction du CERN. Le 2 juin 2013, le CERN inaugure le projet Passeport Big Bang, un parcours touristique et scientifique formé de dix plates-formes d'exposition devant dix sites du CERN dans le Pays de Gex et le Canton de Genève. Les plateformes sont reliées par des itinéraires balisés et par un jeu de piste. C'est un projet est mené en collaboration avec les communes du Pays de Gex, Meyrin et Genève Tourisme dans un souci de renforcer notre dialogue avec nos voisins : http://passeport-big-bang.web.cern.ch/fr. A l’occasion de cette inauguration, nous organisons un événement populaire et festif : le matin, les familles pourront participer à des randonnées à vélo tandis que les sportifs pourront tester les 5...

  6. Numerical simulation of ground-water flow in the Culebra dolomite at the Waste Isolation Pilot Plant (WIPP) site: Second interim report

    International Nuclear Information System (INIS)

    LaVenue, A.M.; Haug, A.; Kelley, V.A.

    1988-03-01

    This hydrogeologic modeling study has been performed as part of the regional hydrologic characterization of the Waste Isolation Pilot Plant (WIPP) Site in southeastern New Mexico. The study resulted in an estimation of the transmissivity distrubution, hydraulic potentials, flow field, and fluid densities in the Culebra Dolomite Member of the Permian Rustler Formation at the WIPP site. The three-dimensional finite-difference code SWIFT-II was employed for the numerical modeling, using variable-fluid-density and a single-porosity formulation. The modeled area includes and extends beyond the WIPP controlled zone (Zone 3). The work performed consisted of modeling the hydrogeology of the Culebra using two approaches: (1) steady-state modeling to develop the best estimate of the undisturbed head distribution, i.e., of the situation before sinking if the WIPP shafts, which began in 1981; and (2) superimposed transient modeling of local hydrologic responses to excavation of the three WIPP shafts at the center of the WIPP site, as well as to various well tests. Boundary conditions (prescribed constant fluid pressures and densities) were estimated using hydraulic-head and fluid-density data obtained from about 40 wells at and near the WIPP site. The transient modeling used the calculated steady-state freshwater heads as initial conditions. 107 refs., 112 figs., 22 tabs

  7. Numerical simulation of ground-water flow in the Culebra dolomite at the Waste Isolation Pilot Plant (WIPP) site: Second interim report

    Energy Technology Data Exchange (ETDEWEB)

    LaVenue, A.M.; Haug, A.; Kelley, V.A.

    1988-03-01

    This hydrogeologic modeling study has been performed as part of the regional hydrologic characterization of the Waste Isolation Pilot Plant (WIPP) Site in southeastern New Mexico. The study resulted in an estimation of the transmissivity distrubution, hydraulic potentials, flow field, and fluid densities in the Culebra Dolomite Member of the Permian Rustler Formation at the WIPP site. The three-dimensional finite-difference code SWIFT-II was employed for the numerical modeling, using variable-fluid-density and a single-porosity formulation. The modeled area includes and extends beyond the WIPP controlled zone (Zone 3). The work performed consisted of modeling the hydrogeology of the Culebra using two approaches: (1) steady-state modeling to develop the best estimate of the undisturbed head distribution, i.e., of the situation before sinking if the WIPP shafts, which began in 1981; and (2) superimposed transient modeling of local hydrologic responses to excavation of the three WIPP shafts at the center of the WIPP site, as well as to various well tests. Boundary conditions (prescribed constant fluid pressures and densities) were estimated using hydraulic-head and fluid-density data obtained from about 40 wells at and near the WIPP site. The transient modeling used the calculated steady-state freshwater heads as initial conditions. 107 refs., 112 figs., 22 tabs.

  8. Meteorological and air quality data quarterly report WIPP site: Eddy County, New Mexico. Winter quarter, December 1976-February 1977

    International Nuclear Information System (INIS)

    Pocalujka, L.P.; Babij, E.; Church, H.W.

    1979-08-01

    The Wipp meteorological, air quality, and radiological measurements program was implemented to support the environmental effort for the evaluations of the site selection suitability. This data report is the third of a series of seasonal quarterly data summaries to be issued for the southeastern New Mexico site

  9. Approach to first principles model prediction of measured WIPP [Waste Isolation Pilot Plant] in situ room closure in salt

    International Nuclear Information System (INIS)

    Munson, D.E.; Fossum, A.F.; Senseny, P.E.

    1989-01-01

    The discrepancies between predicted and measured WIPP in situ Room D closures are markedly reduced through the use of a Tresca flow potential, an improved small strain constitutive model, an improved set of material parameters, and a modified stratigraphy. 17 refs., 8 figs., 1 tab

  10. EPA-Registered Repellents for Mosquitoes Transmitting Emerging Viral Disease.

    Science.gov (United States)

    Patel, Radha V; Shaeer, Kristy M; Patel, Pooja; Garmaza, Aleksey; Wiangkham, Kornwalee; Franks, Rachel B; Pane, Olivia; Carris, Nicholas W

    2016-12-01

    In many parts of the United States, mosquitoes were previously nuisance pests. However, they now represent a potential threat in the spread of viral diseases. The Aedes aegypti, Aedes albopictus, and Culex species mosquitoes are endemic to the United States and together may transmit a variety of viral diseases of growing concern, including West Nile virus, chikungunya, dengue fever, and Zika virus. The Centers for Disease Control and Prevention and the Environmental Protection Agency (EPA) recommend N,N-diethyl-meta-toluamide (DEET) as a first-line mosquito repellent, but for patients refusing to use DEET or other conventional repellents, guidance is limited to any EPA-registered product. Therefore, we conducted a systematic review of the literature to identify which EPA-registered personal mosquito repellent provides the best protection from A. aegypti, A. albopictus, and Culex spp. mosquitoes. We abstracted data from 62 published reports of EPA-registered mosquito repellents. The conventional repellent picaridin has the strongest data to support its use as a second-line agent, while IR3535 and oil of lemon eucalyptus are reasonably effective natural products. Citronella, catnip, and 2-undecanone offer limited protection or have limited data. These results can be used by pharmacists and other health care professionals to advise patients on the selection of an EPA-registered mosquito repellent. Regardless of the repellent chosen, it is vital for patients to follow all instructions/precautions in the product labeling to ensure safe and effective use. © 2016 Pharmacotherapy Publications, Inc.

  11. EPA Collaboration with South Korea

    Science.gov (United States)

    EPA, the Ministry of Environment of Korea, and partner agencies in both countries cooperate to strengthen environmental governance, improve air and water quality, and reduce exposure to toxic chemicals.

  12. EPA scientific integrity policy draft

    Science.gov (United States)

    Showstack, Randy

    2011-08-01

    The U.S. Environmental Protection Agency (EPA) issued its draft scientific integrity policy on 5 August. The draft policy addresses scientific ethical standards, communications with the public, the use of advisory committees and peer review, and professional development. The draft policy was developed by an ad hoc group of EPA senior staff and scientists in response to a December 2010 memorandum on scientific integrity from the White House Office of Science and Technology Policy. The agency is accepting public comments on the draft through 6 September; comments should be sent to osa.staff@epa.gov. For more information, see http://www.epa.gov/stpc/pdfs/draft-scientific-integrity-policy-aug2011.pdf.

  13. EPA Nonregulatory Nonroad Duty Cycles

    Science.gov (United States)

    EPA nonregulatory, nonroad duty cycles for equipment such as agricultural tractors, backhoe loaders,crawlers tractors, excavators, arc welding skid steer loaders, and wheel loaders. Also,test procedures, laboratory methods, and emissions for this equipmen

  14. Request from the Phthalate Esters Panel of the American Chemistry Council for correction of EPA's Action Plan for Phthalate Esters

    Science.gov (United States)

    The Phthalate Esters Panel (Panel) of the American Chemistry Council submits this Request for Correction to EPA under the Guidelines for Ensuring and Maximizing the Quality, Objectivity, Utility, and Integrity, of Information Disseminated by the Environmental Protection Agency

  15. WIPP conceptual design report. Addendum D. A report to Holmes and Narver, Inc., Anaheim, California on alternative energy sources for Waste Isolation Pilot Plant, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    1977-03-01

    This report presents the results of a technical and economic analysis of alternative methods of meeting the energy needs of a proposed Waste Isolation Pilot Plant (WIPP) to be located in southeastern New Mexico. The WIPP is a facility for underground storage of radioactive wastes in a deep salt bed. The report analyzes a total of sixteen possible methods for meeting WIPP energy requirements, consisting of purchased electricity and on-site generation in various combinations from full purchased to full on-site

  16. Memorandum of Understanding Between U.S. EPA Superfund and U.S. NRC

    International Nuclear Information System (INIS)

    Walker, Stuart

    2008-01-01

    The Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation (OSRTI) and the Nuclear Regulatory Commission (NRC) are responsible for implementing the 'Memorandum of Understanding Between the Environmental Protection Agency and the Nuclear Regulatory Commission: Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites'. This paper provides a brief overview of the origin of the Memorandum of Understanding (MOU), the major features of the MOU, and how the MOU has been implemented site specifically. EPA and NRC developed the MOU in response to direction from the House Committee on Appropriations to EPA and NRC to work together to address the potential for dual regulation. The MOU was signed by EPA on September 30, 2002 and NRC on October 9, 2002. The two agencies had worked on the MOU since March 2000. While both EPA and NRC have statutory authority to clean up these sites, the MOU provides consultation procedures between EPA and NRC to eliminate dual regulation. Under the MOU, EPA and NRC identified the interactions of the two agencies for the decommissioning and decontamination of NRC-licensed sites and the ways in which those responsibilities will be exercised. Except for Section VI, which addresses corrective action under the Resource Conservation and Recovery Act (RCRA), this MOU is limited to the coordination between EPA, when acting under its CERCLA authority, and NRC, when a facility licensed by the NRC is undergoing decommissioning, or when a facility has completed decommissioning, and the NRC has terminated its license. EPA believes that implementation of the MOU between the two agencies will ensure that future confusion about dual regulation does not occur regarding the cleanup and reuse of NRC-licensed sites. NRC and EPA have so far exchanged MOU consultation letters on eight NRC-licensed sites. EPA has responded to each consultation request with a letter expressing its views on actions

  17. EPA for Businesses and Non-Profits

    Science.gov (United States)

    Information and links to EPA web pages that are meant to help businesses and non-profits adhere to EPA regulations and otherwise protect the environment, take advantage of opportunities to collaborate with the EPA, and find training EPA training programs.

  18. Hanford Tank Waste to WIPP - Maximizing the Value of our National Repository Asset

    International Nuclear Information System (INIS)

    Tedeschi, Allan R.; Wheeler, Martin

    2013-01-01

    Preplanning scope for the Hanford tank transuranic (TRU) waste project was authorized in 2013 by the Department of Energy (DOE) Office of River Protection (ORP) after a project standby period of eight years. Significant changes in DOE orders, Hanford contracts, and requirements at the Waste Isolation Pilot Plant (WIPP) have occurred during this time period, in addition to newly implemented regulatory permitting, re-evaluated waste management strategies, and new commercial applications. Preplanning has identified the following key approaches for reactivating the project: qualification of tank inventory designations and completion of all environmental regulatory permitting; identifying program options to accelerate retrieval of key leaking tank T-111; planning fully compliant implementation of DOE Order 413.3B, and DOE Standard 1189 for potential on-site treatment; and re-evaluation of commercial retrieval and treatment technologies for better strategic bundling of permanent waste disposal options

  19. Tracer tests performed in the field for WIPP in southeastern New Mexico

    International Nuclear Information System (INIS)

    Gonzalez, D.D.; Hill, L.R.

    1979-01-01

    A two-well recirculating tracer test began in October, 1979, to define as accurately as possible the hydraulic character of a fractured carbonate aquifer, the Culebra dolomite member of the Rustler Formation at the WIPP site in Eddy and Lee Counties, New Mexico. The Culebra dolomite overlies a zone planned for isolation of transuranic contaminated waste generated by the United States defense programs. The storage zone of the proposed facility is in nearly pure halite and about 1400 feet (427 meters) below the Culebra dolomite, the most likely pathway for the migration of radionuclides to the biosphere in the event the repository is breached by groundwater. Included in the definition of the hydraulic character of the Culebra aquifer are natural groundwater velocities, aquifer porosity and components of dispersivity. The proposed tracer test using sodium benzoate, a homologous series of chlorofluoromethanes and pentafluorobenzoic acid as tracers is described. Results of the test will be reported at a later date

  20. Reference stratigraphy and rock properties for the Waste Isolation Pilot Plant (WIPP) project

    International Nuclear Information System (INIS)

    Krieg, R.D.

    1984-01-01

    A stratigraphic description of the country rock near the working horizon at the Waste Isolation Pilot Plant (WIPP) is presented along with a set of mechanical and thermal properties of materials involved. Data from 41 cores and shafts are examined. The entire stratigraphic section is found to vary in elevation in a regular manner, but individual layer thicknesses and relative separation between layers are found to have no statistically significant variation over the one mile north to south extent of the working horizon. The stratigraphic description is taken to be relative to the local elevation of Anhydrite b. The material properties have been updated slightly from those in the July 1981 Reference Stratigraphy. This reference stratigraphy/properties document is intended primarily for use in thermal/structural analyses. This document supercedes the July 1981 stratigraphy/properties document. 31 references, 7 figures

  1. Hanford Tank Waste to WIPP - Maximizing the Value of our National Repository Asset

    Energy Technology Data Exchange (ETDEWEB)

    Tedeschi, Allan R.; Wheeler, Martin

    2013-11-11

    Preplanning scope for the Hanford tank transuranic (TRU) waste project was authorized in 2013 by the Department of Energy (DOE) Office of River Protection (ORP) after a project standby period of eight years. Significant changes in DOE orders, Hanford contracts, and requirements at the Waste Isolation Pilot Plant (WIPP) have occurred during this time period, in addition to newly implemented regulatory permitting, re-evaluated waste management strategies, and new commercial applications. Preplanning has identified the following key approaches for reactivating the project: qualification of tank inventory designations and completion of all environmental regulatory permitting; identifying program options to accelerate retrieval of key leaking tank T-111; planning fully compliant implementation of DOE Order 413.3B, and DOE Standard 1189 for potential on-site treatment; and re-evaluation of commercial retrieval and treatment technologies for better strategic bundling of permanent waste disposal options.

  2. WIPP [Waste Isolation Pilot Plant] intermediate scale borehole test: A pretest analysis

    International Nuclear Information System (INIS)

    Argueello, J.G.

    1991-01-01

    A three-dimensional finite element structural analysis of the Intermediate Scale Borehole Test at the Waste Isolation Pilot Plant (WIPP) has been performed. The analysis provides insight into how a relatively new excavation in a creeping medium responds when introduced into an existing pillar which has been undergoing stress redistribution for 5.7 years. The stress field of the volume of material in the immediate vicinity of the borehole changes significantly when the hole is drilled. Closure of the hole is predicted to be larger in the vertical direction than in the horizontal direction, leading to an ovaling of the hole. The relatively high stresses near the hole persist even at the end of the simulation, 2 years after the hole is drilled. 12 ref., 10 figs

  3. A probabilistic analysis of a catastrophic transuranic waste hoist accident at the WIPP

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.; Stanford Univ., CA

    1993-06-01

    This report builds upon the extensive and careful analyses made by the DOE of the probability of failure of the waste hoist, and more particularly on the probability of failure of a major component, the hydraulic brake system. The extensive fault tree analysis prepared by the DOE was the starting point of the present report. A key element of this work is the use of probability distributions rather than so-called point estimates to describe the probability of failure of an element. One of the authors (MAG) developed the expressions for the probability of failure of the brake system. The second author (TJS) executed the calculations of the final expressions for failure probabilities. The authors hope that this work will be of use to the DOE in its evaluation of the safety of the waste hoist, a key element at the WIPP

  4. The evolution of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

    International Nuclear Information System (INIS)

    Walter, L.H.

    1988-01-01

    As a first-of-a-kind facility, the Waste Isolation Pilot Plant (WIPP) presents a unique perspective on the value of designing a public affairs program that grown with and complements a project's evolution from construction to operations. Like the project itself, the public affairs programs progressed through several stages to its present scope. During the construction phase, foundations were laid in the community. Then, in this past year as the project entered a preoperational status, emphasis shifted to broaden the positive image that had been created locally. In this stage, public affairs presented the project's positive elements to the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management program. Most recently, and continuing until receipt of the first shipment of waste in October 1988, an even broader, more aggressive public affairs program is planned

  5. In situ testing of titanium and mild steel nuclear waste containers at the WIPP site

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1990-01-01

    An overview of the Waste Isolation Pilot Plant (WIPP) in situ tests on the corrosion of titanium and mild steel for high level waste containers is presented. The tests at Sandia have moved out of the laboratory into a test underground facility in order to evaluate the performance of the waste package material. The tests are being performed under both near-reference and accelerated salt repository conditions. Some containers are filled with high level waste glass (non-radioactive); others contain electric heaters. Backfill material is either bentonite/sand or crushed salt. In other tests metals and glasses are exposed directly to brine. The tests are designed to study the corrosion and metallurgy of the canister and overpack materials; the feasibility and performance of backfill materials; and near-field effects such as brine migration

  6. On the road to WIPP: Or remote packaging of transuranic waste

    International Nuclear Information System (INIS)

    Ledbetter, J.M.; Field, L.R.

    1994-01-01

    At the Los Alamos National Laboratory (LANL) Hot Cell facility, highly productive programs in reactor research spanning three decades have generated appreciable quantities of legacy waste. Hot cell capability had become virtually useless due to the storage of this waste. As a result of concentrated efforts by LANL staff, in cooperation with Westinghouse Waste Isolation Pilot Plant (WIPP), a solution was arrived at that allowed the facility to become productive once again. Equipment has been designed and fabricated to remotely handle 55-gal. waste drums, load waste canisters, perform canister weld closure, leak test welds, grapple the waste canister and transport the canister to an interim storage site. It is our contention that the technology and acquired equipment produced from this effort should be used to further benefit other DOE sites

  7. Basic data report for drillhole ERDA 6 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1983-01-01

    ERDA 6 was drilled in eastern Eddy County, New Mexico, to investigate a candidate site for a nuclear waste repository. The site was subsequently rejected on the basis of geological data. ERDA 6 was drilled in the NE 1/4 SE 1/4, section 35, T21S,R31E. The borehole encountered, from top to bottom, 17 ft of Quaternary deposits, 55 ft of the Triassic Santa Rosa Sandstone, 466 ft of the Dewey Lake Red Beds, 273 ft of the Rustler Formation, 1785.5 ft of the Salado Formation and 374.5 ft of the upper Castile Formation, all of Permian age. Cores or drill cuttings were taken throughout the hole. A suite of wireline geophysical logs was run to a depth of 883 ft to facilitate the recognition and correlation of rock units, to assure identification of major lithologies and to provide depth determinations independent of drill-pipe measurements. The site at ERDA 6 was rejected because the structure of the lower Salado and the Castile is too severe to develop a repository along a single set of beds. The borehole also intersected a reservoir of pressurized brine and gas at about 2710'. The pore volume for the reservoir was estimated to be in the range from about 200,000 to about 2 million barrels. ERDA 6 was re-entered in 1981 by the Department of Energy (DOE) for the purpose of further testing the brine reservoir. Those tests are described in separate reports by the DOE and its contractors. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  8. Experimental plan for tracer testing in the Culebra Dolomite at the WIPP site

    International Nuclear Information System (INIS)

    Beauheim, R.L.; Davies, P.B.

    1992-01-01

    This Experimental Plan provides a conceptual description of a proposed series of tracer tests to be conducted in the Culebra Dolomite Member of the Rustler Formation at the WIPP site. The new tracer tests are intended to address deficiencies that have been identified both in the performance and interpretation of previously conducted tracer tests' Tracer tests were conducted at the H-2 hydropad in 1980, at the H-6 hydropad in 1981, 1982, and 1983, at the H-4 hydropad from 1982 to 1984, at the H-3 hydropad in 1984, and at the H-11 hydropad in 1988. These tests were all performed over the entire 7-m thickness of the Culebra and, therefore, provided no information on the effects of vertical heterogeneity within the Culebra on transport. In addition, each of the previous tracer tests provided data only from 1 to 3 flow paths, allowing calibration of interpretive models but not validation of those models. The tracer tests at the H-3, H-6, and H-11 hydropads have been interpreted using a double-porosity continuum model (SWIFT 11) in which advective transport occurs through a uniform network of fractures while diffusion of tracer from the fractures to the porosity in the rock matrix causes a physical retardation of the transport. External reviewers, particularly participants in the international INTRAVAL program, have suggested that alternative mechanisms, such as fracture channeling, could explain the observed physical retardation and have recommended that additional tracer tests be designed and performed to distinguish among these mechanisms. The previous tracer tests also provided no information on chemical-retardation processes within the Culebra, which have been shown through performance-assessment calculations to have a large impact on cumulative releases of radionuclides from the WIPP to the accessible environment

  9. WIPP Hydrology Program Waste Isolation Pilot Plant southeastern New Mexico. Hydrologic data report No. 2

    International Nuclear Information System (INIS)

    1985-12-01

    This report contains basic hydrologic data for aquifer tests and water-level measurements conducted at the Waste Isolation Pilot Plant (WIPP) site over the period 1983 through November 1985. Part A summarizes data collected during a series of pumping and slug tests conducted during 1983 and 1984 in wells at the H-2 and H-9 hydropads, and in well H-12. Water-level data collected in 1983 and 1984 at the H-2 hydropads and Appendixes tabulate water-level, drawdown, millivolt, and pressure data collected with automated Data Acquisition Systems (DAS's) during the aquifer tests for both the test wells and the observation wells, and water-level data collected with electric water-level sounders. Part B is a detailed presentation of pumping tests conducted at the H-11 hydropad in May and June, 1985. Part B discusses the automated DAS, water-level measurement devices, the discharge measurement system, well and equipment configurations, and provides plots of pressure or water-level response in both the pumping and observation wells. Pressure data collected with the DAS, depth to water collected with the water-level sounders in observation wells, and measured pumping rate data are tabulated. Part C presents January through November, 1985 water-level data collected from wells in the observation-well network at and near the WIPP site. The types of devices utilized are discussed and the water-level plots obtained from the water-level data for the Magenta, the Culebra, the Rustler-Salado contact zone, the Bell Canyon Formation, and the Salado/Castile Formations are presented. Water levels are tabulated

  10. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2001-01-01

    This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.

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

    International Nuclear Information System (INIS)

    Johnson, J.E.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.; Stanford Univ., CA

    1998-01-01

    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

  13. Structural evaluation of WIPP disposal room raised to clay seam G

    International Nuclear Information System (INIS)

    Park, Byoung Yoon; Holland, John F.

    2007-01-01

    An error was discovered in the ALGEBBRA script used to calculate the disturbed rock zone around the disposal room and the shear failure zone in the anhydrite layers in the original version. To correct the error, a memorandum of correction was submitted according to the Waste Isolation Pilot Plant (WIPP) Quality Assurance program. The recommended course of action was to correct the error, to repeat the post-process, and to rewrite Section 7.4, 7.5, 8, and Appendix B in the original report. The sections and appendix revised by the post-process using the corrected ALGEBRA scripts are provided in this revision. The original report summarizes a series of structural calculations that examine effects of raising the WIPP repository horizon from the original design level upward 2.43 meters. Calculations were then repeated for grid changes appropriate for the new horizon raised to Clay Seam G. Results are presented in three main areas: (1) Disposal room porosity, (2) Disturbed rock zone characteristics, and (3) Anhydrite marker bed failure. No change to the porosity surface for the compliance re-certification application is necessary to account for raising the repository horizon, because the new porosity surface is essentially identical. The disturbed rock zone evolution and devolution are charted in terms of a stress invariant criterion over the regulatory period. This model shows that the propagation of the DRZ into the surrounding rock salt does not penetrate through MB 139 in the case of both the original horizon and the raised room. Damaged salt would be expected to heal in nominally 150 years. The shear failure does not occur in either the upper or lower anhydrite layers at the moment of excavation, but appears above and below the middle of the pillar one day after the excavation. The damaged anhydrite is not expected to heal as the salt in the DRZ is expected to

  14. Basic data report for drillhole ERDA 6 (Waste Isolation Pilot Plant - WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    ERDA 6 was drilled in eastern Eddy County, New Mexico, to investigate a candidate site for a nuclear waste repository. The site was subsequently rejected on the basis of geological data. ERDA 6 was drilled in the NE 1/4 SE 1/4, section 35, T21S,R31E. The borehole encountered, from top to bottom, 17 ft of Quaternary deposits, 55 ft of the Triassic Santa Rosa Sandstone, 466 ft of the Dewey Lake Red Beds, 273 ft of the Rustler Formation, 1785.5 ft of the Salado Formation and 374.5 ft of the upper Castile Formation, all of Permian age. Cores or drill cuttings were taken throughout the hole. A suite of wireline geophysical logs was run to a depth of 883 ft to facilitate the recognition and correlation of rock units, to assure identification of major lithologies and to provide depth determinations independent of drill-pipe measurements. The site at ERDA 6 was rejected because the structure of the lower Salado and the Castile is too severe to develop a repository along a single set of beds. The borehole also intersected a reservoir of pressurized brine and gas at about 2710'. The pore volume for the reservoir was estimated to be in the range from about 200,000 to about 2 million barrels. ERDA 6 was re-entered in 1981 by the Department of Energy (DOE) for the purpose of further testing the brine reservoir. Those tests are described in separate reports by the DOE and its contractors. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes.

  15. Basic data report for drillhole ERDA 9 (Waste Isolation Pilot Plant WIPP)

    International Nuclear Information System (INIS)

    1983-01-01

    ERDA 9 was drilled in eastern Eddy County, New Mexico, to investigate and test salt beds for the disposal of nuclear wastes. The hole was placed near the SE corner of section 20, T22S,R31E. It was drilled between April 28 and June 4, 1976, to a depth of 2889 ft (measured from a kelly bushing altitude of 3,420.4 ft MSL). The borehole encountered, from top to bottom, Holocene deposits (including artificial fill) of 22 ft, the Pleistocene Mescalero Caliche (5 ft) and Gatuna Formation (27 ft), 9 ft of the Triassic Santa Rosa Sandstone, and 487 ft of the Dewey Lake Red Beds, 290 ft of the Rustler Formation, 1976 ft of the Salado Formation and 53 ft of the Castile Formation, all of Permian age. Cuttings were collected at 5-ft intervals for the land surface to a depth of 1090 ft, and consecutive cores were taken to a depth of 2876.6 ft. A suite of wireline geophysical logs was run the full length of the borehole to measure distribution of radioactive elements and hydrogen, and variations in rock density and elastic velocity. On the basis of the borehole findings and related hydrological and geophysical programs, the site was judged suitable to pursue the extensive geological characterization program which followed. The core from ERDA 9 provided a suite of samples extensively tested for rock mechanics, physical properties, and mineralogy. Drill-stem tests in ERDA 9 indicated no significant fluids or permeability in the Salado beds of interest. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level wastes

  16. Resource Conservation and Recovery Act Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 7: Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    This permit application (Vol. 7) for the WIPP facility contains appendices related to the following information: Ground water protection; personnel; solid waste management; and memorandums concerning environmental protection standards.

  17. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Chapter D, Appendix D1 (conclusion): Volume 3, Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1992-06-01

    This report, Part B (Vol. 3) of the permit application for the WIPP facility, contains information related to the site characterization of the facility, including geology, design, rock salt evaluations, maps, drawings, and shaft excavations. (CBS)

  18. Resource Conservation and Recovery Act: Part B, Permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 1, Revison 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1992-03-01

    This report contains information related to the permit application for the WIPP facility. Information is presented on solid waste management; personnel safety; emergency plans; site characterization; applicable regulations; decommissioning; and ground water monitoring requirements.

  19. Internal factors influencing the knowledge continuity ensuring

    Directory of Open Access Journals (Sweden)

    Hana Urbancová

    2012-01-01

    Full Text Available The aim of the systematic ensuring of knowledge continuity is the continuity of an organisation’s development, the quality of managerial positions and the continuity of decision-making. By ensuring knowledge continuity, organisations may gain a performance-enhancing factor. The objective of the article is to identify the level of impact of decisive internal factors determining knowledge continuity ensuring and contributing to the efficiency of the organisations. Knowledge continuity ensuring as an internal force, however, can together with the right employees, help adapt more quickly to external conditions that organisations can hardly control. Monitoring and ensuring knowledge continuity can contribute to a higher quality of processes in general, in particular processes exploiting knowledge, and thus help improve the level of management. The first part of the article presents theoretical views on the aspects of knowledge continuity ensuring in organisations while the second part analyses the findings of the surveys carried out among managers in organisations in the Czech Republic. Based on the summary of the outcomes obtained it is possible to say that internal factors influence knowledge continuity ensuring in organisations, however, the level of impact of individual factors is determined by their size. The findings regarding the impact of each of the factors show that the most significant barriers to knowledge continuity ensuring are those associated with the human factor.

  20. Electron-Positron Accumulator (EPA)

    CERN Multimedia

    Photographic Service

    1986-01-01

    After acceleration in the low-current linac LIL-W, the electrons and positrons are accumulated in EPA to obtain a sufficient intensity and a suitable time-structure, before being passed on to the PS for further acceleration to 3.5 GeV. Electrons circulate from right to left, positrons in the other direction. Dipole bending magnets are red, focusing quadrupoles blue, sextupoles for chromaticity-control orange. The vertical tube at the left of the picture belongs to an optical transport system carrying the synchrotron radiation to detectors for beam size measurement. Construction of EPA was completed in spring 1986. LIL-W and EPA were conceived for an energy of 600 MeV, but operation was limited to 500 MeV.

  1. Fluid injection for salt water disposal and enhanced oil recovery as a potential problem for the WIPP: Proceedings of a June 1995 workshop and analysis

    International Nuclear Information System (INIS)

    Silva, M.K.

    1996-08-01

    The Waste Isolation Pilot Plant (WIPP) is a facility of the U.S. Department of Energy (DOE), designed and constructed for the permanent disposal of transuranic (TRU) defense waste. The repository is sited in the New Mexico portion of the Delaware Basin, at a depth of 655 meters, in the salt beds of the Salado Formation. The WIPP is surrounded by reserves and production of potash, crude oil and natural gas. In selecting a repository site, concerns about extensive oil field development eliminated the Mescalero Plains site in Chaves County and concerns about future waterflooding in nearby oil fields helped eliminate the Alternate II site in Lea County. Ultimately, the Los Medanos site in Eddy County was selected, relying in part on the conclusion that there were no oil reserves at the site. For oil field operations, the problem of water migrating from the injection zone, through other formations such as the Salado, and onto adjacent property has long been recognized. In 1980, the DOE intended to prohibit secondary recovery by waterflooding in one mile buffer surrounding the WIPP Site. However, the DOE relinquished the right to restrict waterflooding based on a natural resources report which maintained that there was a minimal amount of crude oil likely to exist at the WIPP site, hence waterflooding adjacent to the WIPP would be unlikely. This document presents the workshop presentations and analyses for the fluid injection for salt water disposal and enhanced oil recovery utilizing fluid injection and their potential effects on the WIPP facility

  2. Analysis of borehole inclusion stress measurement concepts proposed for use in the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Morgan, H.S.

    1984-01-01

    The Waste Isolation Pilot Plant (WIPP) is being developed in southeastern New Mexico by the United States Department of Energy as a research and development (RandD) facility to demonstrate the safe disposal in salt of radioactive wastes resulting from defense activities. As part of the WIPP RandD program, a series of in situ tests will be performed to determine the behavior of drifts and storage rooms in the creeping salt medium. Data obtained in these tests will be used to evaluate and improve numerical models used to compute the structural response of these drifts and rooms. Stress has been proposed as one of the parameters to be measured in the tests, and borehole inclusion stressmeters have been included in the instrumentation package

  3. Instrumentation of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States). Repository Isolation Systems Div.; Hoag, D.L.; Blankenship, D.A.; DeYonge, W.F.; Schiermeister, D.M. [RE/SPEC, Inc., Albuquerque, NM (United States); Jones, R.L.; Baird, G.T. [Tech Reps, Inc., Albuquerque, NM (United States)

    1997-04-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories had the responsibility for the experimental activities at the WIPP and fielded several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The instrumentation of these tests involved the placement of over 4,200 gages including room closure gages, borehole extensometers, stress gages, borehole inclinometers, fixed reference gages, borehole strain gages, thermocouples, thermal flux meters, heater power gages, environmental gages, and ventilation gages. Most of the gages were remotely read instruments that were monitored by an automated data acquisition system, but manually read instruments were also used to provide early deformation information and to provide a redundancy of measurement for the remote gages. Instruments were selected that could operate in the harsh environment of the test rooms and that could accommodate the ranges of test room responses predicted by pretest calculations. Instruments were tested in the field prior to installation at the WIPP site and were modified to improve their performance. Other modifications were made to gages as the TSI tests progressed using knowledge gained from test maintenance. Quality assurance procedures were developed for all aspects of instrumentation including calibration, installation, and maintenance. The instrumentation performed exceptionally well and has produced a large quantity of quality information.

  4. Summary report for the WIPP [Waste Isolation Pilot Plant] technology development program for isolation of radioactive waste

    International Nuclear Information System (INIS)

    Tyler, L.D.; Matalucci, R.V.; Molecke, M.A.; Munson, D.E.; Nowak, E.J.; Stormont, J.C.

    1988-04-01

    The technology experiments have been managed in three broad categories: Thermal/Structural Interactions (TSI), Plugging and Sealing Performance and Design (PandS), and Waste Package Performance (WPP). The history and major progress in each of these areas is summarized in this report. The TSI program has established the fact that the WIPP salt creep rate, and therefore closure of WIPP rooms, is about three times more rapid than our best models predicted prior to the tests. Studies to resolve this discrepancy are well advanced; in the interim, good agreement between predicitions and observation is obtained by empirical adjustment of the elastic constants. The closure of backfilled waste room to about five percent void volume is predicted to take less than 100 years, the time during which active controls may be assumed to prevent human intrusion. The waste package program has revealed that migration of interstitial brine to excavations in the WIPP salt occurs at a significantly greater rate than assumed by earlier investigations. A satisfactory model to explain the data utilizes darcy flow in very low permeability salt which is driven by a pore pressure gradient caused when the excavation creates an atmospheric pressure boundary. This model, coupled with room closure predictions and backfill design using a salt/bentonite clay mixture, indicates that the rate of brine seepage will not result in a fluid or slurry state in the room, but rather in a compacted solid. 373 refs., 20 figs., 9 tabs

  5. Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

    Energy Technology Data Exchange (ETDEWEB)

    Dwight, C.C.; McClellan, G.C.; Guay, K.P. [Argonne National Lab., Idaho Falls, ID (United States); Courtney, J.C. [Louisiana State Univ., Baton Rouge, LA (United States); Duff, M.J. [Consolidated Technical Services, Inc., Walkersville, MD (United States)

    1992-02-01

    Argonne National Laboratory is participating in the Department of Energy`s Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m{sup 3} (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein.

  6. Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

    Energy Technology Data Exchange (ETDEWEB)

    Dwight, C.C.; McClellan, G.C.; Guay, K.P. (Argonne National Lab., Idaho Falls, ID (United States)); Courtney, J.C. (Louisiana State Univ., Baton Rouge, LA (United States)); Duff, M.J. (Consolidated Technical Services, Inc., Walkersville, MD (United States))

    1992-01-01

    Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m{sup 3} (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein.

  7. Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

    International Nuclear Information System (INIS)

    Dwight, C.C.; McClellan, G.C.; Guay, K.P.; Courtney, J.C.; Duff, M.J.

    1992-01-01

    Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m 3 (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein

  8. Instrumentation of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Munson, D.E.; Jones, R.L.; Baird, G.T.

    1997-04-01

    The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories had the responsibility for the experimental activities at the WIPP and fielded several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The instrumentation of these tests involved the placement of over 4,200 gages including room closure gages, borehole extensometers, stress gages, borehole inclinometers, fixed reference gages, borehole strain gages, thermocouples, thermal flux meters, heater power gages, environmental gages, and ventilation gages. Most of the gages were remotely read instruments that were monitored by an automated data acquisition system, but manually read instruments were also used to provide early deformation information and to provide a redundancy of measurement for the remote gages. Instruments were selected that could operate in the harsh environment of the test rooms and that could accommodate the ranges of test room responses predicted by pretest calculations. Instruments were tested in the field prior to installation at the WIPP site and were modified to improve their performance. Other modifications were made to gages as the TSI tests progressed using knowledge gained from test maintenance. Quality assurance procedures were developed for all aspects of instrumentation including calibration, installation, and maintenance. The instrumentation performed exceptionally well and has produced a large quantity of quality information

  9. Comparison between predicted and measured south drift closures at the WIPP using a transient creep model for salt

    International Nuclear Information System (INIS)

    Munson, D.E.; Fossum, A.F.

    1986-01-01

    The US Department of Energy is constructing and operating the Waste Isolation Pilot Plant (WIPP), a research and development facility near Carlsbad, New Mexico, to determine whether or not defense-generated high-level radioactive waste can be stored safely in bedded salt. The goal of the WIPP modeling program is to develop the capability to predict room responses from one site to another without a priori knowledge of the actual room responses. Data from one of the early WIPP excavations, called the South Drift, have already been used to form an initial evaluation of computational models for predicting room closures as a result of salt creep. In that study, a significant unresolved discrepancy existed between predicted and measured room closures. It was suggested that future studies address alternate forms of the constitutive law. In this paper, an alternate form of the creep model for salt is used that is founded upon the deformation-mechanism map for the micromechanical deformation processes. This model embodies both steady-state and transient creep. Also, quasi-static plasticity is incorporated into the complete constitutive model for salt. The conclusion is drawn that the combination of the mechanistic creep model, plasticity, and flow potential can approximate the late time South Drift deformation. Further improvement of the model fit of plasticity in the future is expected to further improve the simulation

  10. Review of the draft supplement to the WIPP environmental impact statement DOE/EIS-0026-S-2

    International Nuclear Information System (INIS)

    Neill, R.H.; Channell, J.K.; Spiegler, P.; Chaturvedi, L.

    1997-04-01

    New Mexico Environmental Evaluation Group's (EEG) review of the WIPP Disposal Phase Draft Supplemental Environmental Impact Statement (SEIS-II) concentrated on the radiological aspects of the Proposed Action, including transportation. The alternatives were reviewed in less detail. Some calculations were checked, mostly for the Proposed Action. Because of time constraints, there was little review of Hazardous Chemicals, Economics, or other Environmental Assessments. SEIS-II was written as a pre-decision document with the Alternatives all plausible and eligible to be selected. Also, the inventory of TRU waste for disposal went well beyond that portion of TRU waste that has been historically considered to be the WIPP inventory. This broadened scope is probably appropriate for an EIS but it is confusing to the reviewer who is aware of the statutory limits of wastes that are allowed to come to WIPP at the present time. EEG has attempted to keep the broadened scope of SEIS-II in mind during their review. The more important issues discussed within are: alternatives; related documents; transportation; questionable assumptions; use of the 75th percentile values; family farm scenario and inhalation doses; modification of BRAGFLO volumes; emplacement of remotely handled TRU wastes; conversion error; and remotely handled TRU casks

  11. EPA Principles for Greener Cleanups

    Science.gov (United States)

    A goal of the U.S. Environmental Protection Agency (EPA) Office and Land and Emergency Management (OLEM) and its many partners is to preserve and restore land by promoting and using protective waste management practices and by assessing and cleaning..

  12. GET SMART: EPA'S SMARTE INITIATIVE

    Science.gov (United States)

    The EPA's Office of Research and Development with the assistance of the U.S.-German Bilateral Working Group and the Interstate Technology Regulatory Council (ITRC), is developing Site-specific Management Approaches and Revitalization Tools (SMART) that will help stakeholders over...

  13. EPA's Benchmark Dose Modeling Software

    Science.gov (United States)

    The EPA developed the Benchmark Dose Software (BMDS) as a tool to help Agency risk assessors facilitate applying benchmark dose (BMD) method’s to EPA’s human health risk assessment (HHRA) documents. The application of BMD methods overcomes many well know limitations ...

  14. (indigenous) education ensure effective gender mainstreaming in ...

    African Journals Online (AJOL)

    Leaving no one behind: can (indigenous) education ensure effective gender ... in the distribution of socio-economic and political benefits, depict that additional ... of gender equality and equity and explores in different ways the relationships ...

  15. WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern

    International Nuclear Information System (INIS)

    2002-01-01

    This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable

  16. PROBABILITY OF FAILURE OF THE TRUDOCK CRANE SYSTEM AT THE WASTE ISOLATION PILOT PLANT (WIPP)

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.

    2000-01-01

    This probabilistic analysis of WIPP TRUDOCK crane failure is based on two sources of failure data. The source for operator errors is the report by Swain and Guttman, NUREG/CR-1278-F, August 1983. The source for crane cable hook breaks was initially made by WIPP/WID-96- 2196, Rev. O by using relatively old (1970s) U.S. Navy data (NUREG-0612). However, a helpful analysis by R.K. Deremer of PLG guided the authors to values that were more realistic and more conservative, with the recommendation that the crane cable/hook failure rate should be 2.5 x 10-6 per demand. This value was adopted and used. Based on these choices a mean failure rate of 9.70 x 10-3(1/yr) was calculated. However, a mean rate by itself does not reveal the level of confidence to be associated with this number. Guidance to making confidence calculations came from the report by Swain and Guttman, who stated that failure data could be described by lognormal distributions. This is in agreement with the widely use d reports (by DOE and others) NPRD-95 and NPRD-91, on failure data. The calculations of confidence levels showed that the mean failure rate of 9.70x 10-3(1/yr) corresponded to a percentile value of approximately 71; i.e. there is a 71% likelihood that the failure rate is less than 9.70x 10-3(1/yr). One also calculated that there is a 95% likelihood that the failure rate is less than 29.6x 10-3(1/yr). Or, as stated previously, there is a 71% likelihood that not more than one dropped load will occur in 103 years. Also, there is a 95% likelihood that not more than one dropped load will occur in approximately 34 years. It is the responsibility of DOE to select the confidence level at which it desires to operate

  17. Basic Data Report for Drillholes on the H-19 Hydropad (Waste Isolation Pilot Plant--WIPP)

    International Nuclear Information System (INIS)

    Mercer, J.W.; Cole, D.L.; Holt, R.M.

    1998-01-01

    Seven holes were drilled and wells (H-19b0, H-19b2, H-19b3, H-19b4, H-19b5, H-19b6, and H-19b7) were constructed on the H-19 hydropad to conduct field activities in support of the Culebra Transport Program. These wells were drilled and completed on the Waste Isolation Pilot Plant (WIPP) site during February to September 1995. An eighth hole, H-19b1, was drilled but had to be abandoned before the target depth was reached because of adverse hole conditions. The geologic units penetrated at the H-19 location include surficial deposits of Holocene age, rocks from the Dockum Group of Upper Triassic age, the Dewey Lake Redbeds, and Rustler Formation of the Permian age. The Rustler Formation has been further divided into five informal members which include the Forty-niner Member, Magenta Member, Tamarisk Member, Culebra Dolomite Member, and an unnamed lower member. The Rustler Formation, particularly the Culebra Dolomite Member, is considered critical for hydrologic site characterization. The Culebra is the most transmissive saturated unit above the WIPP repository and, as such, is considered to be the most likely pathway for radionuclide transport to the accessible environment in the unlikely event the repository is breached. Seven cores from the Culebra were recovered during drilling activities at the H-19 hydropad and detailed descriptions of these cores were made. On the basis of geologic descriptions, four hydrostratigraphic units were identified in the Culebra cores and were correlated with the mapping units from the WFP air intake shaft. The entire length of H-19b1 was cored and was described in detail. During coring of H-19b1, moisture was encountered in the upper part of the Dewey Lake Redbeds. A 41-ft-thick section of this core was selected for detailed description to qualify the geologic conditions related to perched water in the upper Dewey Lake. In addition to cuttings and core, a suite of geophysical logs run on the drillholes was used to identify and

  18. Basic Data Report for Drillholes on the H-19 Hydropad (Waste Isolation Pilot Plant--WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Mercer, J.W.; Cole, D.L.; Holt, R.M.

    1998-10-09

    Seven holes were drilled and wells (H-19b0, H-19b2, H-19b3, H-19b4, H-19b5, H-19b6, and H-19b7) were constructed on the H-19 hydropad to conduct field activities in support of the Culebra Transport Program. These wells were drilled and completed on the Waste Isolation Pilot Plant (WIPP) site during February to September 1995. An eighth hole, H-19b1, was drilled but had to be abandoned before the target depth was reached because of adverse hole conditions. The geologic units penetrated at the H-19 location include surficial deposits of Holocene age, rocks from the Dockum Group of Upper Triassic age, the Dewey Lake Redbeds, and Rustler Formation of the Permian age. The Rustler Formation has been further divided into five informal members which include the Forty-niner Member, Magenta Member, Tamarisk Member, Culebra Dolomite Member, and an unnamed lower member. The Rustler Formation, particularly the Culebra Dolomite Member, is considered critical for hydrologic site characterization. The Culebra is the most transmissive saturated unit above the WIPP repository and, as such, is considered to be the most likely pathway for radionuclide transport to the accessible environment in the unlikely event the repository is breached. Seven cores from the Culebra were recovered during drilling activities at the H-19 hydropad and detailed descriptions of these cores were made. On the basis of geologic descriptions, four hydrostratigraphic units were identified in the Culebra cores and were correlated with the mapping units from the WFP air intake shaft. The entire length of H-19b1 was cored and was described in detail. During coring of H-19b1, moisture was encountered in the upper part of the Dewey Lake Redbeds. A 41-ft-thick section of this core was selected for detailed description to qualify the geologic conditions related to perched water in the upper Dewey Lake. In addition to cuttings and core, a suite of geophysical logs run on the drillholes was used to identify and

  19. EPA Region 1 Environmentally Sensitive Areas

    Data.gov (United States)

    U.S. Environmental Protection Agency — This coverage represents polygon equivalents of environmentally sensitive areas (ESA) in EPA Region I. ESAs were developed as part of an EPA headquarters initiative...

  20. U.S. EPA Metadata Editor (EME)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EPA Metadata Editor (EME) allows users to create geospatial metadata that meets EPA's requirements. The tool has been developed as a desktop application that...

  1. EPA Linked Open Data: Substance Registry Service

    Data.gov (United States)

    U.S. Environmental Protection Agency — Substance Registry Services (SRS) is the Environmental Protection Agency's (EPA) central system for information about substances that are tracked or regulated by EPA...

  2. 2011 EPA Pesticide General Permit (PGP)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The 2011 EPA Pesticide General Permit (PGP) covers discharges of biological pesticides, and chemical pesticides that leave a residue, in areas where EPA is the NPDES...

  3. EPA's role in uranium mining and milling

    International Nuclear Information System (INIS)

    Smith, P.B.

    1980-01-01

    EPA's role and actions in regulating uranium mining and milling are reviewed and updated. Special emphasis is given to EPA's current activities under the Uranium Mill Tailings Radiation Control Act of 1978

  4. WIPP Hydrology Program: Waste Isolation Pilot Plant, southeastern New Mexico, Hydrologic Data Report No. 5: Parts, A-WIPP-13 multipad test; B-H-4c, P-17, ERDA-9, and Cabin Baby-1 slug tests; C-Engle and Carper well pumping tests; D-WIPP-12, H-14, and H-15 drill-stem tests; E-Water-level data

    International Nuclear Information System (INIS)

    Stensrud, W.A.; Bame, M.A.; Lantz, K.D.; LaVenue, A.M.; Palmer, J.B.; Saulnier, G.J. Jr.

    1987-01-01

    Part A of this report describes the objectives, scope, design, equipment, and methodology for a long-term pumping test conducted at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The test was conducted to provide technical assistance as part of the ongoing hydrologic characterization of the WIPP site. The test is referred to as the northern multipad pumping test, because it was designed to create a hydraulic stress over a wide area of the northern half of the WIPP site. The fluid-pressure and water-level recovery in both pumping and observation wells were monitored for a minimum of 72 days. The test interval was the Culebra Dolomite Member of the Rustler Formation. Twenty-three observation wells completed in the Culebra dolomite were monitored at least once a month as part of the regional water-level monitoring program. Severl wells completed in the Magenta Dolomite Member of the Rustler Formation were monitored during the test to assess the possibility of Magenta-Culebra communication in the expected area of influence of this test. The succeeding sections of this part of Hydrologic Data Report No. 5 present detailed descriptions of the test objectives, pretest data collection, test equipment and test-well configuration, the observation-well network, and test results. 3 refs., 147 figs., 107 tabs

  5. Plan for implementing EPA standards for UMTRA sites

    International Nuclear Information System (INIS)

    1984-01-01

    This plan is designed to be a generic presentation on methodology that will be followed in implementing the EPA standards. Its applicability covers 24 inactive uranium mill tailings sites and approximately 8000 vicinity properties, no two of which are alike. This diversity dictates the more general approach of this plan. In practice, however, site-specific application will be implemented and will require extensive consultation with the appropriate state or tribe and the NRC. In addition, information concerning relevant Federal, state, or tribal standards and regulations will be considered along with any data that may assist in the evaluations. Throughout this process, DOE will encourage state and tribal participation to ensure that compliance with the EPA standards will be achieved

  6. First year evaluation of EPA's radon contractor proficiency (RCP) program

    International Nuclear Information System (INIS)

    Salmon, G.L.

    1990-01-01

    This paper reports that the Environmental Protection Agency (EPA) has developed a voluntary program to evaluate radon reduction contractors and provide this information to the public, as part of activities mandated by the Indoor Radon Abatement Act (IRAA) of 1988. The Radon Contractor Proficiency Program consists of several elements that collectively help to ensure the proficiency of radon mitigators and give the public greater confidence in their capability. Contractors who participate in the program must pass a written examination, adhere to mitigation guidelines, keep records of work, meet continuing education requirements and pass a re-examination every two years. Upon meeting the program's requirements, mitigators are listed in EPA's National RCP Proficiency Report. The first Report released on May 15, 1990 listed 636 contractors. The second Report, to be release in August, will list 895 contractors, representing an increase of 40 per cent

  7. Pretest parametric calculations for the heated pillar experiment in the WIPP In-Situ Experimental Area

    International Nuclear Information System (INIS)

    Branstetter, L.J.

    1983-03-01

    Results are presented for a pretest parametric study of several configurations and heat loads for the heated pillar experiment (Room H) in the Waste Isolation Pilot Plant (WIPP) In Situ Experimental Area. The purpose of this study is to serve as a basis for selection of a final experiment geometry and heat load. The experiment consists of a pillar of undisturbed rock salt surrounded by an excavated annular room. The pillar surface is covered by a blanket heat source which is externally insulated. A total of five thermal and ten structural calculations are described in a four to five year experimental time frame. Results are presented which include relevant temperature-time histories, deformations, rock salt stress component and effective stress profiles, and maximum stresses in anhydrite layers which are in close proximity to the room. Also included are predicted contours of a conservative post-processed measure of potential salt failure. Observed displacement histories are seen to be highly dependent on pillar and room height, but insensitive to other geometrical variations. The use of a tensile cutoff across slidelines is seen to produce more accurate predictions of anhydrite maximum stress, but to have little effect on rock salt stresses. The potential for salt failure is seen to be small in each case for the time frame of interest, and is only seen at longer times in the center of the room floor

  8. Review comments on Environmental Analysis Cost Reduction Proposals (WIPP-DOE-136), July 1982

    International Nuclear Information System (INIS)

    Channell, J.K.

    1982-11-01

    The cost reduction proposals have the laudable goal of significantly reducing the total capital And operating cost connected with WIPP. Furthermore, since the proposed changes would reduce the size and operating rate of the project, they would be expected to have decreased environmental And socioeconomic impacts. However, some of these cost reduction proposals do decrease factors of safety in various components of the project or trade off one type of environmental detriment for another. The report does not contain sufficient detail to justify all of the conclusions reached; more discussion and quantitative information (including costs) is necessary in some cases. Also, there are places where the report is unclear or contradictory. Without a more detailed evaluation, EEG is unable to conclude that each of these cost reduction proposals either has a net environmental/health and safety benefit or a cost savings that justifies a net detriment. A revised Environmental Analysis (EA) should either include additional information or specifically reference backup documents where these conclusions have been justified. In addition, the EA needs to be revised to include the effect of the recently announced (11/18/82) decision by DOE to relocate the underground waste storage areas of the repository to the south

  9. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1984-01-01

    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

  10. Evaluation of the WIPP site for the supernova neutrino burst observatory

    International Nuclear Information System (INIS)

    Balbes, M.J.; Boyd, R.N.; Kalen, J.D.; Mitchell, C.A.; Hencheck, M.; Sugarbaker, E.R.; Vandegriff, J.D.; Lieberwirth, S.D.

    1997-01-01

    Measurements of the neutron background in a potential underground site for the supernova neutrino burst observatory (SNBO) have been made. The SNBO will ultimately be capable of detecting μ and τ neutrinos from a supernova. Furthermore, masses of the μ and τ neutrinos might be measurable in the range of 10-50 eV. SNBO operates by detecting the neutrons caused by interaction of the supernova neutrinos with rock. It will consist of order ten thousand neutron detectors located in an underground environment having a very low intrinsic radiation level. The limit to the size, hence sensitivity, of SNBO is thus the neutron signal-to-noise ratio, which depends on the neutron background in the environment of SNBO. Thus we have made neutron background measurements at the department of energy waste isolation pilot plant (WIPP) located near Carlsbad, NM. The value of the ambient neutron flux we determined, 332±148 neutrons m -2 d -1 , shows that the background levels in this facility are sufficiently low to warrant construction of a galactic supernova neutrino detector. (orig.)

  11. Basic data report for drillholes at the H-11 complex (Waste Isolation Pilot Plant-WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Mercer, J.W. (Sandia National Labs., Albuquerque, NM (USA)); Snyder, R.P. (Geological Survey, Denver, CO (USA))

    1990-05-01

    Drillholes H-11b1, H-11b2, and H-11b3 were drilled from August to December 1983 for site characterization and hydrologic studies of the Culebra Dolomite Member of the Upper Permian Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. In October 1984, the three wells were subjected to a series of pumping tests designed to develop the wells, provide information on hydraulic communication between the wells, provide hydraulic properties information, and to obtain water samples for quality of water measurements. Based on these tests, it was determined that this location would provide an excellent pad to conduct a convergent-flow non-sorbing tracer test in the Culebra dolomite. In 1988, a fourth hole (H-11b4) was drilled at this complex to provide a tracer-injection hole for the H-11 convergent-flow tracer test and to provide an additional point at which the hydraulic response of the Culebra H-11 multipad pumping test could be monitored. A suite of geophysical logs was run on the drillholes and was used to identify different lithologies and aided in interpretation of the hydraulic tests. 4 refs., 6 figs., 6 tabs.

  12. Basic data report for drillholes at the H-11 complex (Waste Isolation Pilot Plant-WIPP)

    International Nuclear Information System (INIS)

    Mercer, J.W.; Snyder, R.P.

    1990-05-01

    Drillholes H-11b1, H-11b2, and H-11b3 were drilled from August to December 1983 for site characterization and hydrologic studies of the Culebra Dolomite Member of the Upper Permian Rustler Formation at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. In October 1984, the three wells were subjected to a series of pumping tests designed to develop the wells, provide information on hydraulic communication between the wells, provide hydraulic properties information, and to obtain water samples for quality of water measurements. Based on these tests, it was determined that this location would provide an excellent pad to conduct a convergent-flow non-sorbing tracer test in the Culebra dolomite. In 1988, a fourth hole (H-11b4) was drilled at this complex to provide a tracer-injection hole for the H-11 convergent-flow tracer test and to provide an additional point at which the hydraulic response of the Culebra H-11 multipad pumping test could be monitored. A suite of geophysical logs was run on the drillholes and was used to identify different lithologies and aided in interpretation of the hydraulic tests. 4 refs., 6 figs., 6 tabs

  13. Pretest 3D finite element analysis of the WIPP Intermediate Scale Borehole Test

    International Nuclear Information System (INIS)

    Arguello, J.G.

    1991-11-01

    A three dimensional pretest finite element analysis of the Intermediate Scale Borehole Test has been performed. In the analysis, the 7.7 years simulation period includes the mining of Rooms C1 and C2, and the N1420 cross drift, at time zero; drilling of the borehole between the two rooms at 5.7 years; and 2 years of post-drilling response. An all salt configuration was used in the calculation. The 1984 Waste Isolation Pilot Plant (WIPP) reference elastic-secondary creep law, with reduced elastic moduli, was used to model the creeping response of the salt. Results show that after mining of the rooms and cross drift a relatively high von Mises stress state exists around the perimeter of the pillar. However, by 5.7 years, or immediately prior to drilling of the borehole, the pillar has relaxed to an almost uniform von Mises stress of about 7--8 MPa. After the borehole is drilled, a relatively high von Mises stress field is once again set up in the immediate vicinity of the hole. This drives the creep closure of the borehole. The hole closes more in the vertical direction than in the horizontal direction, resulting in ovalling of the hole. At the end of the simulation, the von Mises stress around the borehole is still higher than that in the remained of the pillar. Thus, the closure rates are relatively high at the end of the simulation time

  14. Intergranular fluid compositions from the Waste Isolation Pilot Plant (WIPP) southeastern New Mexico

    International Nuclear Information System (INIS)

    Krumhansl, J.L.; Kimball, K.M.; Stein, C.L.

    1991-01-01

    The objective of this study was to perform a systematic sampling of the intergranular brines that slowly ''weep'' from four of the main stratigraphic units exposed in the WIPP. This information was added to the data base on brine compositions used in performance assessment and also employed in characterizing Salado Formation hydrology at the repository horizon. Concentrations of Na, K, Mg, Ca, Cl, SO 4 , and Br were all highly variable. It was also established that this variability reflects neither post-excavation evaporation nor imprecision in the analytical techniques. Compositional variability on the length scale of a few tens of centimeters is as large as that found over several hundreds of meters. Stratigraphy did not appear to exert any control over weep brine compositions. Programmatically relevant applications of these results are: (1) a valid performance assessment must consider the possibility of a wide range of brines, rather than carry out evaluations using a single ''best'' average brine, and (2) the Salado appears not to function as a continuous aquifer since brines originating millions of years ago have failed to homogenize though separated by only short distances. 10 refs., 19 figs., 11 tabs

  15. Arthropod and decomposition studies at the WIPP site, October-November, 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    These studies were conducted to address topics related to potential environmental impacts resulting from WIPP construction at the Los Medanos site. Studies include the effect of salt piles on soil microarthropod faunas and soil community respiration, quantities of soil moved from deep in the soil column to the surface by termites and ants, and development and testing of a multiple regression model for predicting decomposition. Soil cores were taken at increasing distances from the twenty-year-old salt dump at the Nash Draw Potash facility and examined for microarthropod content and tested for other biological activity. Although there were some reductions in densities of most taxa at the base of the salt pile and at 100 m from the base, all of the dominant soil taxa from the area were found at the base of the pile. If a substantial adverse impact occurred soon after emplacement of the salt, recovery has been relatively complete. Substantial changes in these baseline population densities during or after construction could be indicators of impact to the ecology of the Los Medanos site. A model was developed to predict rates of decomposition of shinnery oak litter based on evapotranspiration and lignin content. The model was less successful in predicting the decomposition rate of creosotebush litter, as removal of litter by termites produced large variances in apparent decomposition rates

  16. Background radiation measurements at the Waste Isolation Pilot Plant (WIPP) Site, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    Minnema, D.M.; Brewer, L.W.

    1983-09-01

    A series of background radiation measurements was performed at the Waste Isolation Pilot Plant (WIPP) Site, Carlsbad, New Mexico. The survey consisted of gross gamma and gamma spectral measurements of the radiation fields, soil and salt grab sample gamma analysis, and radon and working level measurements. The survey included locations at the surface and also within the mine itself. Background radiation levels on the surface were measured to average 7.65 microR/hour, and 0.7 microR/hour within the mine. Radon and working levels were at or below detection levels at all locations, and the radon concentration was estimated to be about 0.01 pCi/liter on the surface based on spectral measurements. The spectral measurements were performed using an intrinsic germanium spectrometer, and calculations from the spectra indicated that potassium-40 contributed about 28% to the surface level dose rates, natural uranium daughters contributed about 64%, and cesium-137 from weapons testing fallout contributed about 8%. In the mine potassium-40 was the only identifiable contributor to the dose rate

  17. WIPP/SRL in-situ tests: MIIT program--The effects of metal package components

    International Nuclear Information System (INIS)

    Covington, J.A.; Wicks, G.G.; Molecke, M.A.

    1991-01-01

    The Materials Interface Interactions Tests or MIIT is the largest in-situ testing program in progress, involving burial of many simulated nuclear waste systems and accompanying package components. In MIIT, waste glass samples were fabricated into the shape of 'pineapple slices', polished on one side. Proposed package components were also made into a similar configuration and the various glasses, metals, and geologic samples were than stacked onto heater elements within Teflon assemblies. This produced interactions of interest by creating glass/glass, glass/salt, and glass/metal interfaces. Since the outer diameter of the metal was smaller than the outer diameter of the glass, a lip was created which was also produced a glass/liquid interface, which was also studied. Overall, a total of 50 stacks or assemblies of pineapple slices were created in seven different stacking arrangements. Each individual assembly was then installed in an instrumented borehole at WIPP. Brine was then added to most of boreholes and the assemblies heated and maintained at 90 degrees C. This was achieved by energizing the central heating and rod that traversed through the middle opening of each of the pineapple slices in each assembly. Due to the design of these units, glass, metal and geologic samples could be removed at time intervals of 6 mos., 1 year, 2 years, and 5 years. Currently, all but the 5 year samples have been removed from test and are being evaluated in laboratories of MIIT participants

  18. Strategy for investigation of fluid migration in evaporites (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    Lambert, S.J.; Shefelbine, H.C.

    1980-03-01

    The proposed strategy for WIPP project investigations of fluid migration in evaporites focuses upon a quantitative evaluation of each of several processes. Potential short- and long-term problems arising from fluid migration are complication of waste retrieval and mobilization of waste nuclides. The strategy will attempt to determine the degree to which these potentials are realized with respect to five hypothetical types of waste-rock interactions: movement of waste containers, migration of nuclides, formation of radioactive brine pocket, radiolytic generation of gas, and degradation of waste container. Of eight identified processes whose combinations could lead to the five types of interactions, only five are to be quantitatively investigated by the studies of fluid migration per se: presence of fluids, fluid mobilization toward heat-producing and contact-handled waste, encounter of fluids with influence of waste form, reversal of direction of fluid mobilization, and entrainment of nuclides in fluids. Methods of investigation entail an iterative combination of laboratory experimentation and mathematical modeling

  19. Custom Search | ECHO | US EPA

    Science.gov (United States)

    ECHO, Enforcement and Compliance History Online, provides compliance and enforcement information for approximately 800,000 EPA-regulated facilities nationwide. ECHO includes permit, inspection, violation, enforcement action, and penalty information about facilities regulated under the Clean Air Act (CAA) Stationary Source Program, Clean Water Act (CWA) National Pollutant Elimination Discharge System (NPDES), and/or Resource Conservation and Recovery Act (RCRA). Information also is provided on surrounding demographics when available.

  20. Watershed Statistics | ECHO | US EPA

    Science.gov (United States)

    ECHO, Enforcement and Compliance History Online, provides compliance and enforcement information for approximately 800,000 EPA-regulated facilities nationwide. ECHO includes permit, inspection, violation, enforcement action, and penalty information about facilities regulated under the Clean Air Act (CAA) Stationary Source Program, Clean Water Act (CWA) National Pollutant Elimination Discharge System (NPDES), and/or Resource Conservation and Recovery Act (RCRA). Information also is provided on surrounding demographics when available.

  1. An HVAC [heating, ventilation, and air-conditioning] fault-tree analysis for WIPP [Waste Isolation Pilot Plant] integrated risk assessment

    International Nuclear Information System (INIS)

    Kirby, P.N.; Iacovino, J.M.

    1990-01-01

    In order to evaluate the public health risk of potential radioactive releases from operation of the Waste Isolation Pilot Plant (WIPP), a probabilistic risk assessment of waste-handling operations was conducted. One major aspect of this risk assessment involved fault-tree analysis of the plant heating, ventilation, and air-conditioning (HVAC) systems, which constitute the final barrier between waste-handling operations and the environment. The WIPP site is designed to receive and store two types of waste: contact-handled transuranic (CH TRU) wastes to be shipped in 208-ell drums and remote-handled (RH) TRU wastes to be shipped in shielded casks. The identification of accident sequences for CH waste operations revealed no identified accidents that could release significant radioactive particulates to the environment without a failure in the HVAC systems. When the HVAC fault-tree results were combined with other critical system fault trees and the analysis of waste-handling accident sequences, the approximation of the overall WIPP plant risk due to airborne releases was determined to be 2.6 x 10 -7 fatalities per year for the population within a 50-mile radius of the WIPP site. This risk was demonstrated to be well below the risk of fatality from other voluntary and involuntary activities for the population within the vicinity of the WIPP

  2. Ensuring Academic Standards in US Higher Education

    Science.gov (United States)

    Dill, David D.

    2014-01-01

    The most recent research on college-student learning in the US by respected scholars such as Richard Arum, Josipa Roksa, and Ernest Pascarella suggests that the nation's means of ensuring academic standards in US colleges and universities are not working effectively. Like US K-12 education and health care, the US higher education system is…

  3. Ensuring Peace and Reconciliation while Holding Leaders ...

    African Journals Online (AJOL)

    need to be adopted to ensure that both organizations fulfil their mandate to address impunity on the ... international law; international relations and political studies. ...... 'not any other consideration', which was an attempt to assuage any fears that she ... system, which should play into the hands of the AU – in theory. Yet this.

  4. EPA`s program for risk assessment guidelines: Quantification issues

    Energy Technology Data Exchange (ETDEWEB)

    Dourson, M.L. [Environmental Protection Agency, Washington, DC (United States)

    1990-12-31

    The quantitative procedures associated with noncancer risk assessment include reference dose (RfD), benchmark dose, and severity modeling. The RfD, which is part of the EPA risk assessment guidelines, is an estimation of a level that is likely to be without any health risk to sensitive individuals. The RfD requires two major judgments: the first is choice of a critical effect(s) and its No Observed Adverse Effect Level (NOAEL); the second judgment is choice of an uncertainty factor. This paper discusses major assumptions and limitations of the RfD model.

  5. The Rustler Formation at the WIPP [Waste Isolations Pilot Plant] site: Report of a workshop on the geology and hydrology of the Rustler Formation as it relates to the WIPP Project

    International Nuclear Information System (INIS)

    Chaturvedi, L.

    1987-02-01

    This workshop contained eight papers characterizing the Rustler Formation at the WIPP site in New Mexico. Four of these reports were processed separately for the data bases. Information contained in the four remaining papers is available in journal articles or in the reports of other conferences and included discussions of ground water flow through the Rustler Formation, the potential migration of leached radionuclides in this rock, the effects of mineral dissolution on the removal of underlying salt deposits, and a possible pathway for radionuclide migration into the biosphere

  6. Densities and species composition of the avifauna of the Los Medanos WIPP site, southeastern New Mexico

    International Nuclear Information System (INIS)

    Ligon, J.D.; Haydock, J.

    1981-01-01

    Data were gathered in various habitat types to determine annual fluctuations in species diversity and relative abundance, breeding densities, reproductive success of White-necked Ravens and Harris Hawks, fall and spring migrant species and to collect voucher specimens for the site. Four Emlen transects were surveyed in four habitat types during the summer of 1980. These transects were used monthly in May, June and July to determine densities of breeding and non-breeding birds. Active White-necked Raven and Harris Hawk nests were located by checking all conspicuous nests. The nests were checked several times during the nesting stage to determine nest success. During 1980, eleven new species and two new families were added to the list of birds seen on or near the WIPP site. The list now totals 133 species representing 38 families. White-necked Raven nesting success was slightly lower in 1980 than in 1979. Average clutch size in 1980 was 5.5, which is 3.5% less than in 1979 and 19% greater than in 1978. The average number of birds fledged per nest was surprisingly similar over the past three years despite fairly large climatic differences. Success of Harris Hawk nesting was very low in the autumn of 1980 due principally to bad weather. The overall density of breeding birds was lower in 1980 than in 1979 in all habitat types. The overall density was also lower in 1980 than in 1978 in all habitat types except mesquite-grassland. Many species showed larger year-to-year fluctuations in numbers. Mourning Dove density, for example, dropped from 76.9 to 11.2 individuals per square kilometer in the hummock-mesquite habitat. Voucher specimens have been collected for 69 of the 133 species seen on the Los Medanos site

  7. Geochemistry of the Waste Isolation Pilot Plant (WIPP) site, southeastern New Mexico, U.S.A

    International Nuclear Information System (INIS)

    Lambert, S.J.

    1992-01-01

    An extensive geochemical data base, including analyses of major and minor solutes, mineralogical studies of core samples, and isotopic studies of waters, carbonates and sulfates, has been assembled for evaporites and related rocks in the northern Delaware Basin of southeastern New Mexico. These data were compiled for the geological and hydrological characterization of the Waste Isolation Pilot Plant (WIPP), which is excavated in the evaporites of the Salado Formation. These data were evaluated in order:(1) to determine the stability of the evaporite mineralogy over geological time; (2) to compare the aqueous geochemistry with host rock mineralogy; (3) to delineate the nature and timing of water-rock interactions, such as dissolution and recrystallization; and (4) to determine the geological and climatic conditions that have governed groundwater recharge. The resulting synthesis of data and current hypotheses concerning the origin, composition and history of waters in the evaporite rocks and related units of the Delaware Basin provides a tentative conceptual model for the behavior of the water-rock system since the deposition of the evaporites in the Permian. Essential components of this model include: (1) widespread Late Triassic/Early Jurassic evaporite recrystallization; (2) accumulation of deep-basin brines isolated from meteoric recharge; (3) evaporite dissolution by meteoric waters flowing in carbonates and sulfates interbedded in the uppermost Permian section and at the basin margin; (4) lateral rather than vertical infiltration of pre-Holocene meteoric waters in the uppermost Permian section; and (5) climatic conditions presently less conductive to recharge than in the Late Pleistocene. (author)

  8. Waste Isolation Pilot Plant (WIPP) research and development program: in situ testing plan, March 1982

    International Nuclear Information System (INIS)

    Matalucci, R.V.; Christensen, C.L.; Hunter, T.O.; Molecke, M.A.; Munson, D.E.

    1982-12-01

    The WIPP in southeast New Mexico is being developed as an R and D facility to demonstrate the safe disposal of radioactive defense wastes in bedded salt. The tests are done first without radioactive materials and then with transuranic (TRU) waste and Defense High-Level Waste (DHLW). The thermal/structural itneraction experiments include (a) geomechanical evaluations of access drifts, vertical shafts, and isothermal TRU disposal rooms during the Site and Preliminary Validation Program, (b) tests that represent the reference DHLW room configuraton (5.5 m x 5.5 m) and areal thermal loading of 12 W/m 2 , (c) an overtest of the DHLW congfiguration heated to about four times the reference thermal loading; (d) geomechanical evaluations of various room widths up to 9.1 m, variable pillar widths, and a long-drift intersection, (e) an 11-m-dia axisymmetric heated pillar test, and (f) miscellaneous tests to determine stress field and clay seam sliding resistance. The plugging and sealing experiments include (a) salt permeability tests, (b) tests to determine effects of size and scale on behavior of plugs and to determine backfill material behavior and emplacement techniques, and (c) a plug test matrix to evaluate candidate sealing materials. Waste package interaction experiments include (a) simulated-waste package tests that use several design options and engineered barrier materials under reference and accelerated DHLW environments, (b) confirmatory brine migration tests, (c) TRU drum durability tests in dry and wet conditions, (d) options for radiation-source tests using cesium capsules, and (e) actual DHLW tests using up to 40 canisters for technical demonstrations and for addressing concerns of wasteform chemistry, leaching, and near-field radionuclide migration

  9. Simultaneous Thermal Analysis of WIPP and LANL Waste Drum Samples: A Preliminary Report

    Energy Technology Data Exchange (ETDEWEB)

    Wayne, David M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-19

    On Friday, February 14, 2014, an incident in P7R7 of the WIPP underground repository released radioactive material into the environment. The direct cause of the event was a breached transuranic (TRU) waste container, subsequently identified as Drum 68660. Photographic and other evidence indicates that the breach of 68660 was caused by an exothermic event. Subsequent investigations (Britt, 2015; Clark and Funk, 2015; Wilson et al., 2015; Clark, 2015) indicate that the combination of nitrate salts, pH neutralizing chemicals, and organic-based adsorbent represented a potentially energetic mixture. The materials inside the breached steel drum consisted of remediated, 30- to 40-year old, Pu processing wastes from LANL. The contents were processed and repackaged in 2014. Processing activities at LANL included: 1) neutralization of acidic liquid contents, 2) sorption of the neutralized liquid, and 3) mixing of acidic nitrate salts with an absorber to meet waste acceptance criteria. The contents of 68660 and its sibling, 68685, were derived from the same parent drum, S855793. Drum S855793 originally contained ten plastic bags of acidic nitrate salts, and four bags of mixed nitrate and oxalate salts generated in 1985 by Pu recovery operations. These salts were predominantly oxalic acid, hydrated nitrate salts of Mg, Ca, and Fe, anhydrous Na(NO3), and minor amounts of anhydrous and hydrous nitrate salts of Pb, Al, K, Cr, and Ni. Other major components include sorbed water, nitric acid, dissolved nitrates, an absorbent (Swheat Scoop®) and a neutralizer (KolorSafe®). The contents of 68660 are described in greater detail in Appendix E of Wilson et al. (2015)

  10. Simultaneous Thermal Analysis of WIPP and LANL Waste Drum Samples: A Preliminary Report

    International Nuclear Information System (INIS)

    Wayne, David M.

    2015-01-01

    On Friday, February 14, 2014, an incident in P7R7 of the WIPP underground repository released radioactive material into the environment. The direct cause of the event was a breached transuranic (TRU) waste container, subsequently identified as Drum 68660. Photographic and other evidence indicates that the breach of 68660 was caused by an exothermic event. Subsequent investigations (Britt, 2015; Clark and Funk, 2015; Wilson et al., 2015; Clark, 2015) indicate that the combination of nitrate salts, pH neutralizing chemicals, and organic-based adsorbent represented a potentially energetic mixture. The materials inside the breached steel drum consisted of remediated, 30- to 40-year old, Pu processing wastes from LANL. The contents were processed and repackaged in 2014. Processing activities at LANL included: 1) neutralization of acidic liquid contents, 2) sorption of the neutralized liquid, and 3) mixing of acidic nitrate salts with an absorber to meet waste acceptance criteria. The contents of 68660 and its sibling, 68685, were derived from the same parent drum, S855793. Drum S855793 originally contained ten plastic bags of acidic nitrate salts, and four bags of mixed nitrate and oxalate salts generated in 1985 by Pu recovery operations. These salts were predominantly oxalic acid, hydrated nitrate salts of Mg, Ca, and Fe, anhydrous Na(NO 3 ), and minor amounts of anhydrous and hydrous nitrate salts of Pb, Al, K, Cr, and Ni. Other major components include sorbed water, nitric acid, dissolved nitrates, an absorbent (Swheat Scoop®) and a neutralizer (KolorSafe®). The contents of 68660 are described in greater detail in Appendix E of Wilson et al. (2015)

  11. Representation of spatial variability for modelling of flow and transport processes in the Culebra Dolomite at the WIPP site

    International Nuclear Information System (INIS)

    Meigs, L.C.; Beauheim, R.L.

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) is a proposed repository for transuranic wastes constructed in bedded Permian-acre halite deposits in southeastern New Mexico, USA. Site-characterization studies at the WIPP site identified groundwater flow in the Culebra Dolomite Member of the Rustler Formation as the most likely Geologic pathway for radio nuclide transport to the accessible environment in the event of a breach of the WIPP repository through inadvertent human intrusion. The Culebra is a 7-m-thick, variably fractured dolomite with massive and layers. Detailed studies at all scales demonstrated that the Culebra is a heterogeneous medium. Heterogeneity in Culebra properties was incorporated into numerical simulations used for data interpretation and PA calculations in different ways, depending on the amount of data available, the certainty with which the effects of a given approach could be evaluated, and the purpose of the study. When abundant, spatially distributed data were available, the heterogeneity was explicitly included. For example, a stochastic approach was used to generate numerous, equally likely, heterogeneous transmissivity fields conditioned on head and transmissivity data. In other cases, constant parameter values were applied over the model domain. These constant values were selected and applied in two different ways. In simple cases where a conservative bounding value could be identified that would not lead to unrealistically conservative results, that value was used for all calculations. In more complex cases, parameter distributions were developed and single values of the parameters were sampled from the distributions and applied across the entire model domain for each of the PA Monte Carlo simulations. We are currently working to refine our understanding of the multiple rates of diffusion attributable to small-scale spatial variability

  12. Chemistry of brines in salt from the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico: a preliminary investigation

    International Nuclear Information System (INIS)

    Stein, C.L.; Krumhansl, J.L.

    1986-03-01

    We present here analyses of macro- and microscopic (intracrystalline) brines observed within the WIPP facility and in the surrounding halite, with interpretations regarding the origin and history of these fluids and their potential effect(s) on long-term waste storage. During excavation, several large fluid inclusions were recovered from an area of highly recrystallized halite in a thick salt bed at the repository horizon (2150 ft below ground level). In addition, 52 samples of brine ''weeps'' were collected from walls of recently excavated drifts at the same stratigraphic horizon from which the fluid inclusion samples are assumed to have been taken. Analyses of these fluids show that they differ substantially in composition from the inclusion fluids and cannot be explained by mixing of the fluid inclusion populations. Finally, holes in the facility floor that filled with brine were sampled but with no stratographic control; therefore it is not possible to interpret the compositions of these brines with any accuracy, except insofar as they resemble the weep compositions but with greater variation in both K/Mg and Na/Cl ratios. However, the Ca and SO 4 values for the floor holes are relatively close to the gypsum saturation curve, suggesting that brines filling floor holes have been modified by the presence of gypsum or anhydrite, possibly even originating in one or more of the laterally continuous anhydrite units referred to in the WIPP literature as marker beds. In conclusion, the wide compositional variety of fluids found in the WIPP workings suggest that (1) an interconnected hydrologic system which could effectively transport radonuclides away from the repository does not exist; (2) brine migration studies and experiments must consider the mobility of intergranular fluids as well as those in inclusions; and (3) near- and far-field radionuclide migration testing programs need to consider a wide range of brine compositions rather than a few reference brines

  13. Planning, developing, and fielding of thermal/structural interactions in situ tests for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Munson, D.E.; Matalucci, R.V.

    1986-01-01

    Large-scale, well-instrumented underground tests to determine in situ thermal/structural response of bedded salt are being constructed in the WIPP facility in southeastern New Mexico. These tests are an essential component of a broad research and development program to resolve thermal/structural issues, to validate long-term prediction methods, and to develop a design basis for a future repository. They are the result of an extensive planning and evaluation procedure to determine the appropriate test configuration. All details of the tests, including background, decisions, design, site operations, and testing organization are explained. These procedures may be useful in developing other in situ tests

  14. Pre-WIPP in-situ experiments in salt. Part I. Executive summary. Part II. Program description

    Energy Technology Data Exchange (ETDEWEB)

    Sattler, A.R.; Hunter, T.O.

    1979-08-01

    This document presents plans for in-situ experiments in a specific location in southeastern New Mexico. Schedule and facility design were based on features of a representative local potash mine and on contract negotiations with mine owners. Subsequent WIPP program uncertainties have required a delay in the implementation of the activities discussed here; however, the relative schedule for various activities are appropriate for future planning. The document represents a matrix of in-situ activities to address relevant technical issues prior to the availability of a bedded salt repository.

  15. Pre-WIPP in-situ experiments in salt. Part I. Executive summary. Part II. Program description

    International Nuclear Information System (INIS)

    Sattler, A.R.; Hunter, T.O.

    1979-08-01

    This document presents plans for in-situ experiments in a specific location in southeastern New Mexico. Schedule and facility design were based on features of a representative local potash mine and on contract negotiations with mine owners. Subsequent WIPP program uncertainties have required a delay in the implementation of the activities discussed here; however, the relative schedule for various activities are appropriate for future planning. The document represents a matrix of in-situ activities to address relevant technical issues prior to the availability of a bedded salt repository

  16. Report of biological investigations at the Los Medanos Waste Isolation Pilot Plant (WIPP) area of New Mexico during FY 1978

    International Nuclear Information System (INIS)

    Best, T.L.; Neuhauser, S.

    1980-03-01

    The US Department of Energy is considering the construction of a Waste Isolation Pilot Plant (WIPP) in Eddy County, NM. This location is approximately 40 km east of Carlsbad, NM. Biological studies during FY 1978 were concentrated within a 5-mi radius of drill hole ERDA 9. Additional study areas have been established at other sites in the vicinity, e.g., the Gnome site, the salt lakes and several stations along the Pecos River southward from Carlsbad, NM, to the dam at Red Bluff Reservoir in Texas. The precise locations of all study areas are presented and their biology discussed

  17. Radioactive waste disposal: Waste isolation pilot plants (WIPP). (Latest citations from the NTIS Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1993-09-01

    The 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, and examine 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 separate bibliographies. (Contains a minimum of 228 citations and includes a subject term index and title list.)

  18. Report of biological investigations at the Los Medanos Waste Isolation Pilot Plant (WIPP) area of New Mexico during FY 1978

    Energy Technology Data Exchange (ETDEWEB)

    Best, T.L.; Neuhauser, S. (eds.)

    1980-03-01

    The US Department of Energy is considering the construction of a Waste Isolation Pilot Plant (WIPP) in Eddy County, NM. This location is approximately 40 km east of Carlsbad, NM. Biological studies during FY 1978 were concentrated within a 5-mi radius of drill hole ERDA 9. Additional study areas have been established at other sites in the vicinity, e.g., the Gnome site, the salt lakes and several stations along the Pecos River southward from Carlsbad, NM, to the dam at Red Bluff Reservoir in Texas. The precise locations of all study areas are presented and their biology discussed.

  19. Rustler Formation in the waste handling and exhaust shafts, Waste Isolation Pilot Plant (WIPP) site, southeastern New Mexico

    International Nuclear Information System (INIS)

    Holt, R.M.; Powers, D.W.

    1987-01-01

    The Permian Rustler Formation was recently examined in detail in two shafts at the WIPP site: the waste handling shaft (waste shaft) and the exhaust shaft. Fresh exposures of the Rustler in the shafts exhibited abundant primary sedimentary structures. The abundance of primary sedimentary structures observed in the shafts is unequaled in previously described sections. Data are reported here in their stratigraphic context as an initial basis for evaluation of depositional environments of the Rustler and reevaluating the role of dissolution in the formation of the Rustler. 10 refs

  20. Sandia Review of High Bridge Associates Report: Comparison of Plutonium Disposition Alternatives: WIPP Diluted Plutonium Storage and MOX Fuel Irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Shoemaker, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Park, HeeHo Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brady, Patrick Vane [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rechard, Robert P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-08-01

    The subject report from High Bridge Associates (HBA) was issued on March 2, 2016, in reaction to a U.S. Department of Energy (DOE) program decision to pursue down-blending of surplus Pu and geologic disposal at the Waste Isolation Pilot Plant (WIPP). Sandia National Laboratories was requested by the DOE to review the technical arguments presented in the HBA report. Specifically, this review is organized around three technical topics: criticality safety, radiological release limits, and thermal impacts. Questions raised by the report pertaining to legal and regulatory requirements, safeguards and security, international agreements, and costing of alternatives, are beyond the scope of this review.

  1. US EPA Region 4 RMP Facilities

    Science.gov (United States)

    To improve public health and the environment, the United States Environmental Protection Agency (USEPA) collects information about facilities, sites, or places subject to environmental regulation or of environmental interest. Through the Geospatial Data Download Service, the public is now able to download the EPA Geodata shapefile containing facility and site information from EPA's national program systems. The file is Internet accessible from the Envirofacts Web site (http://www.epa.gov/enviro). The data may be used with geospatial mapping applications. (Note: The shapefile omits facilities without latitude/longitude coordinates.) The EPA Geospatial Data contains the name, location (latitude/longitude), and EPA program information about specific facilities and sites. In addition, the file contains a Uniform Resource Locator (URL), which allows mapping applications to present an option to users to access additional EPA data resources on a specific facility or site.

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

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  3. Agriculture: About EPA's National Agriculture Center

    Science.gov (United States)

    EPA's National Agriculture Center (Ag Center), with the support of the United States Department of Agriculture, serves growers, livestock producers, other agribusinesses, and agricultural information/education providers.

  4. EPA Region 1 Environmentally Sensitive Areas (Points)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This coverage represents point equivalents of environmentally sensitive areas in EPA New England. This coverage represents polygon equivalents of environmentally...

  5. A review of WIPP [Waste Isolation Pilot Plant] repository clays and their relationship to clays of adjacent strata

    International Nuclear Information System (INIS)

    Krumhansl, J.L.; Kimball, K.M.; Stein, C.L.

    1990-12-01

    The Salado Formation is a thick evaporite sequence located in the Permian Delaware Basin of southeastern New Mexico. This study focuses on the intense diagenetic alteration that has affected the small amounts of clay, feldspar, and quartz washed into the basin during salt deposition. These changes are of more than academic interest since this formation also houses the WIPP (Waste Isolation Pilot Plant). Site characterization concerns warrant compiling a detailed data base describing the clays in and around the facility horizon. An extensive sampling effort was undertaken to address these programmatic issues as well as to provide additional insight regarding diagenetic mechanisms in the Salado. Seventy-five samples were collected from argillaceous partings in halite at the stratigraphic level of the Waste Isolation Pilot Plant (WIPP). These were compared with twenty-eight samples from cores of the Vaca Triste member of the Salado, a thin clastic unit at the top of the McNutt potash zone, and with a clay-rich sample from the lower contact of the Culebra Dolomite (in the overlying Rustler Formation). These settings were compared to assess the influence of differences in brine chemistry (i.e., halite and potash facies, normal to hypersaline marine conditions) and sediment composition (clays, sandy silt, dolomitized limestone) on diagenetic processes. 44 refs., 11 figs., 5 tabs

  6. Stochastic analysis of radionuclides travel times at the waste isolation pilot plant (WIPP), in New Mexico (U.S.A.)

    International Nuclear Information System (INIS)

    Capilla Roma, J. E.; Gomez-Hernandez, J. J.; Sahuquillo Herraiz, A.

    1999-01-01

    Multiple equally likely transmissivity fields that honor piezo metric head measurements are generated as input to a Monte-Carlo exercise, for the stochastic analysis of travel times in the Culebra dolomite overlaying the Waste Isolation Pilot Plant (WIPP) in New Mexico, USA. Results of the analysis show the importance of modeling variable-density flow as accurately as possible, and of including as much information as possible in the simulations of alternative scenarios. Results also unveil a channel of high transmissivity when transmissivity fields are conditioned to piezo metric data. This channel leads to important reductions of travel time from the WIPP area to the south boundary. The uncertainty of the boundary conditions is analyzed searching for alternative boundary conditions can be obtained that improve the reproduction of piezo metric data and yield a reduction of the minimum travel times to the south boundary. Results of the Monte-Carlo exercise are compared with those from a deterministic analysis showing the limitations of the latter method when trying to estimate extreme values or characterizing the uncertainty of their predictions. The report ends with a brief study on the impact of the small transmissivity measurements at location P-18, showing that its value is not consistent with the model of spatial variability inferred from the data and that it has an important effect on model predictions. (Author)

  7. Stochastic analysis of radionuclides travel times at the waste isolation pilot plant (WIPP), in New Mexico (U. S. A. )

    Energy Technology Data Exchange (ETDEWEB)

    Capilla Roma, J E; Gomez-Hernandez, J J; Sahuquillo Herraiz, A [Universidad Politecnia de Valencia (Spain)

    1999-12-15

    Multiple equally likely transmissivity fields that honor piezo metric head measurements are generated as input to a Monte-Carlo exercise, for the stochastic analysis of travel times in the Culebra dolomite overlaying the Waste Isolation Pilot Plant (WIPP) in New Mexico, USA. Results of the analysis show the importance of modeling variable-density flow as accurately as possible, and of including as much information as possible in the simulations of alternative scenarios. Results also unveil a channel of high transmissivity when transmissivity fields are conditioned to piezo metric data. This channel leads to important reductions of travel time from the WIPP area to the south boundary. The uncertainty of the boundary conditions is analyzed searching for alternative boundary conditions can be obtained that improve the reproduction of piezo metric data and yield a reduction of the minimum travel times to the south boundary. Results of the Monte-Carlo exercise are compared with those from a deterministic analysis showing the limitations of the latter method when trying to estimate extreme values or characterizing the uncertainty of their predictions. The report ends with a brief study on the impact of the small transmissivity measurements at location P-18, showing that its value is not consistent with the model of spatial variability inferred from the data and that it has an important effect on model predictions. (Author)

  8. Site selection and evaluation studies of the Waste Isolation Pilot Plant (WIPP), Los Medanos, Eddy County, NM

    International Nuclear Information System (INIS)

    Griswold, G.B.

    1977-12-01

    Bedded-salt deposits of the Salado Formation have been selected for evaluation for a proposed Waste Isolation Pilot Plant (WIPP) to be located in Eddy County, NM, approximately 26 mi east of Carlsbad. Site selection and evaluation studies that included geologic mapping, geophysical surveys, drilling, and resource appraisal were conducted over and under the prospective location. The lower portion of the Salado meets essential criteria for waste isolation. Beds chosen for waste storage lie 2074 to 2730 ft below the surface. High-purity salt exists at these depths, and the geologic structure revealed by geophysical surveys indicates that these beds are essentially flat. Additional geophysical surveys are now under way. The initial interpretation of the new data indicates that more structure may exist in the salt beds in the northern portion of the site area. Full evaluation of potentially commercial deposits of potash and natural gas within the WIPP site will be reported by separate studies, as will be the hydrologic details of the region

  9. Solubility and sorption characteristics of uranium(VI) associated with rock samples and brines/groundwaters from WIPP and NTS

    International Nuclear Information System (INIS)

    Dosch, R.G.

    1981-01-01

    Solubility measurements for U(VI) in WIPP-related brines/groundwaters were made using initial U(VI) concentrations in the range of 1 to 50 μg/ml. Distribution coefficients (Kd) for U(VI) were determined for Culebra and Magenta dolomites using four different brine/groundwater compositions and for argillaceous shale and hornfels samples from the Eleana and Calico Hills Formation on NTS using a groundwater simulant typical of that area. The Kd's were evaluated as functions of: (1) U(VI) concentration (1.4 x 10 -4 to 1.4 μg/ml); (2) solution volume-to-rock mass ratios used in the measurements (5 to 100 ml/g), and for WIPP material only; (3) water composition (0 to 100% brine in groundwater); and (4) sample location in the Culebra and Magenta dolomite members of the Rustler Formation. The results indicate that if groundwater intrudes into a repository and leaches a waste form, significant concentrations of dissolved or colloidal U(VI) could be maintained in the liquid phase. Should these solutions enter an aquifer system, there are reasonable sets of conditions which could lead to subsequent migration of U(VI) away from the repository site

  10. Simulations of the pipe overpack to compute constitutive model parameters for use in WIPP room closure calculations

    International Nuclear Information System (INIS)

    Park, Byoung Yoon; Hansen, Francis D.

    2004-01-01

    The regulatory compliance determination for the Waste Isolation Pilot Plant includes the consideration of room closure. Elements of the geomechanical processes include salt creep, gas generation and mechanical deformation of the waste residing in the rooms. The WIPP was certified as complying with regulatory requirements based in part on the implementation of room closure and material models for the waste. Since the WIPP began receiving waste in 1999, waste packages have been identified that are appreciably more robust than the 55-gallon drums characterized for the initial calculations. The pipe overpack comprises one such waste package. This report develops material model parameters for the pipe overpack containers by using axisymmetrical finite element models. Known material properties and structural dimensions allow well constrained models to be completed for uniaxial, triaxial, and hydrostatic compression of the pipe overpack waste package. These analyses show that the pipe overpack waste package is far more rigid than the originally certified drum. The model parameters developed in this report are used subsequently to evaluate the implications to performance assessment calculations

  11. Design, modeling, and current interpretations of the H-19 and H-11 tracer tests at the WIPP site

    International Nuclear Information System (INIS)

    Meigs, L.C.; Beauheim, R.L.; McCord, J.T.; Tsang, Y.W.; Haggerty, R.

    1996-01-01

    Site-characterization studies at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico, US identified ground-water flow in the Culebra Dolomite Member of the Rustler Formation as the most likely geologic pathway for radionuclide transport to the accessible environment in the event of a breach of the WIPP repository through inadvertent human intrusion. The results of recent tracer tests, as well as hydraulic tests, laboratory measurements, and re-examination of Culebra geology and stratigraphy, have led to a significant refinement of the conceptual model for transport in the Culebra. Tracer test results and geologic observations suggest that flow occurs within fractures, and to some extent within interparticle porosity and vugs connected by microfractures. Diffusion occurs within all connected porosity. Numerical simulations suggest that the data from the tracer tests cannot be simulated with heterogeneous single-porosity models; significant matrix diffusion appears to be required. The low permeability and lack of significant tracer recovery from tracers injected into the upper Culebra suggest that transport primarily occurs in the lower Culebra

  12. Permeability of natural rock salt from the Waste Isolation Pilot Plant (WIPP) during damage evolution and healing

    International Nuclear Information System (INIS)

    Pfeifle, T.W.; Hurtado, L.D.

    1998-06-01

    The US Department of Energy has developed the Waste Isolation Pilot Plant (WIPP) in the bedded salt of southeastern New Mexico to demonstrate the safe disposal of radioactive transuranic wastes. Four vertical shafts provide access to the underground workings located at a depth of about 660 meters. These shafts connect the underground facility to the surface and potentially provide communication between lithologic units, so they will be sealed to limit both the release of hazardous waste from and fluid flow into the repository. The seal design must consider the potential for fluid flow through a disturbed rock zone (DRZ) that develops in the salt near the shafts. The DRZ, which forms initially during excavation and then evolves with time, is expected to have higher permeability than the native salt. The closure of the shaft openings (i.e., through salt creep) will compress the seals, thereby inducing a compressive back-stress on the DRZ. This back-stress is expected to arrest the evolution of the DRZ, and with time will promote healing of damage. This paper presents laboratory data from tertiary creep and hydrostatic compression tests designed to characterize damage evolution and healing in WIPP salt. Healing is quantified in terms of permanent reduction in permeability, and the data are used to estimate healing times based on considerations of first-order kinetics

  13. Communication skills to ensure patient satisfaction.

    Science.gov (United States)

    Shendurnikar, Niranjan; Thakkar, Pareshkumar A

    2013-11-01

    Every pediatrician would want to satisfy their patients and their parents to sustain good practice, earn name and fame and simultaneously to avoid litigation in this era of consumer protection act. This can be achieved only by use of good communication skills. Today the patients demand time, information and want their questions to be answered. They expect politeness, empathy and human touch from doctors. Time constraints, arrogance, telephone calls, language barriers and cultural insensitivity are the important barriers to good communication. Research has shown that doctor, who undergoes training to acquire good communication skills, can better satisfy his patients. Good communication skill is an art which can be acquired or improved by putting conscious efforts in day to day practice. Such skills should also be incorporated as part of medical teaching curriculum. Asking open ended questions, effective listening, appropriate praise, providing enough information as part of advice and finally checking their understanding, are the key areas of communication during medical interview. During this process pediatrician should ensure to address the parental concerns, should empathize with parents and involve parents in decision making. This will not only ensure satisfaction of parents but also their adherence to the therapy and to the pediatrician.

  14. Hispanos en la EPA: Grace Robiou

    Science.gov (United States)

    La diversidad de la fuerza laboral es importante para la Agencia de Protección Ambiental de EE.UU. (EPA, por sus siglas en inglés). Los empleados hispanos de la EPA contribuyen diariamente hacia la protección de la salud y el medio ambiente.

  15. Hispanos en la EPA: Fabiola Estrada

    Science.gov (United States)

    La diversidad de la fuerza laboral es importante para la Agencia de Protección Ambiental de EE.UU. (EPA, por sus siglas en inglés). Los empleados hispanos de la EPA contribuyen diariamente hacia la protección de la salud y el medio ambiente.

  16. Perfiles de hispanos en la EPA

    Science.gov (United States)

    La diversidad de la fuerza laboral es importante para la Agencia de Protección Ambiental de EE.UU. (EPA, por sus siglas en inglés). Los empleados hispanos de la EPA contribuyen diariamente hacia la protección de la salud y el medio ambiente de todos.

  17. Hispanos en la EPA: Nadtya Y. Hong

    Science.gov (United States)

    La diversidad de la fuerza laboral es importante para la Agencia de Protección Ambiental de EE.UU. (EPA, por sus siglas en inglés). Los empleados hispanos de la EPA contribuyen diariamente hacia la protección de la salud y el medio ambiente.

  18. Hispanos en la EPA: Matthew Tejada

    Science.gov (United States)

    La diversidad de la fuerza laboral es importante para la Agencia de Protección Ambiental de EE.UU. (EPA, por sus siglas en inglés). Los empleados hispanos de la EPA contribuyen diariamente hacia la protección de la salud y el medio ambiente.

  19. Hispanos en la EPA: Joel Corona

    Science.gov (United States)

    La diversidad de la fuerza laboral es importante para la Agencia de Protección Ambiental de EE.UU. (EPA, por sus siglas en inglés). Los empleados hispanos de la EPA contribuyen diariamente hacia la protección de la salud y el medio ambiente.

  20. EPA Scientific Knowledge Management Assessment and Needs

    Science.gov (United States)

    A series of activities have been conducted by a core group of EPA scientists from across the Agency. The activities were initiated in 2012 and the focus was to increase the reuse and interoperability of science software at EPA. The need for increased reuse and interoperability ...

  1. EPA Regulation of Bed Bug Pesticides

    Science.gov (United States)

    All pesticides must be registered by EPA before being sold and used in the U.S., other than those that rely on a limited set of active ingredients (so-called minimum risk pesticides). EPA reviews for safety and effectiveness.

  2. 40 CFR 73.52 - EPA recordation.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false EPA recordation. 73.52 Section 73.52... ALLOWANCE SYSTEM Allowance Transfers § 73.52 EPA recordation. (a) General recordation. Except as provided in...) following receipt of an allowance transfer request pursuant to § 73.50, by moving each allowance from the...

  3. EPA perspective on federal facility agreements

    International Nuclear Information System (INIS)

    Grundler, C.

    1988-01-01

    Although DOE's image with Congress and the media concerning environmental compliance may be poor, EPA sees the Department's recent attitude toward the environment as good. DOE and EPA must continue to move forward. In particular, EPA would like to emphasize less study of a problem and more clean-up. Strong, enforceable agreements will allow this goal to be met by letting EPA take more risks in its decision making. Currently EPA is developing an enforcement strategy for Federal facilities. This strategy will address identifying Federal facilities of concern, increasing enforcement and compliance monitoring activities at those facilities, implementing the model agreements, resource planning, and the establishment of an Agency Management System for Federal facilities. There are over 1000 Federal facilities which are listed on the EPA compliance docket. Over 200 Federal facilities are expected to be included on the NPL. Increased EPA attention may increase the ability of the various Federal agencies to obtain the necessary funding. Another subject being addressed by EPA is the liability of government contractors under the environmental statutes. The Agency is developing a GoCo enforcement strategy. In the hazardous waste enforcement program, three criteria are being considered for determining when to proceed against a contractor: Degree of contractor control over the hazardous waste management activity. Who is actually performing the work, and Degree of Departmental cooperation

  4. Ensuring the validity of calculated subcritical limits

    International Nuclear Information System (INIS)

    Clark, H.K.

    1977-01-01

    The care taken at the Savannah River Laboratory and Plant to ensure the validity of calculated subcritical limits is described. Close attention is given to ANSI N16.1-1975, ''Validation of Calculational Methods for Nuclear Criticality Safety.'' The computer codes used for criticality safety computations, which are listed and are briefly described, have been placed in the SRL JOSHUA system to facilitate calculation and to reduce input errors. A driver module, KOKO, simplifies and standardizes input and links the codes together in various ways. For any criticality safety evaluation, correlations of the calculational methods are made with experiment to establish bias. Occasionally subcritical experiments are performed expressly to provide benchmarks. Calculated subcritical limits contain an adequate but not excessive margin to allow for uncertainty in the bias. The final step in any criticality safety evaluation is the writing of a report describing the calculations and justifying the margin

  5. A comparison of real-time radiography results and visual characterization results with emphasis on WIPP WAC and TRAMPAC compliance issues

    International Nuclear Information System (INIS)

    Hailey, S.M.

    1994-01-01

    Visual characterization provides a means of confirming the real-time radiography (RTR) certification process and process knowledge. RTR and visual characterization have been conducted on thirty-three drums containing transuranic (TRU) waste in support of the Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP) at the Idaho National Engineering Laboratory. Argonne National Laboratory - West (ANL-W) detected a small can of liquid in one of these drums during the visual examination, resulting in a WIPP Waste Acceptance Criteria (WIPP-WAC) miscertification. The remaining thirty-two drums were certified correctly by the RTR system at the Stored Waste Examination Pilot Plant (SWEPP) for WIPP-WAC and TRUPACT-II Authorized Methods for Payload Control (TRAMPAC) requirements. TRAMPAC contains restrictions on the weights of specific materials allowed in the waste, based on the shipping category. Items on the restricted list for a given shipping category are allowed in quantities less than 1 percent of the weight of the waste. RTR can estimate the weights of certain broad categories in homogeneous waste forms, however, the capability to estimate weights at the 1 percent level is not presently realistic. Process knowledge forms the basis of conformance to these weight requirements. Visual characterization suggests process knowledge is not completely adequate at this level

  6. Ensuring Economic Security in Lending Sphere

    Directory of Open Access Journals (Sweden)

    Ivan Vadimovich Kochikin

    2016-06-01

    Full Text Available Relevance of the topic is determined by the need for sustainable development of the country’s banking system, capable of ensuring the process of raising funds to producers and the public for their projects. One of the implementation of this objective is to discourage unfair behavior in financial markets. Trust is a key factor in the development of financial markets, therefore it is necessary to suppress the appearance of unfair practices and participants – black creditors, falsification of financial statements, trading on insider information and market manipulation. It requires a whole range of activities, and above all ensuring the inevitability and proportionality of punishment for unscrupulous players, the introduction of requirements for the business reputation of the management of financial institutions.The article is devoted to structuring legal violations in the lending sphere. The analysis of indicators of credit organizations in Russia was conducted to fulfill this aim. This analysis revealed the causes of sustainable growth of overdue accounts payable – job cuts in enterprises, violations in the financial sector, various errors in the credit granting / raising. The authors carry out the systematization and classification of offenses in the area of lending, provide examples, as well as factual material illustrating the violations in the lending process having the characteristics of a fraud. The article substantiates the obligations of employees of the credit institution, in the result of which risks of granting credit to fraudsters can be reduced. The methods of fraud prevention should include the identified methods of protection against fraud in the area under consideration – exchange of information by banks associated with the criminal intentions of customers; technology development and technical support, training, and personnel responsibilities.

  7. Surgical treatment for obesity: ensuring success.

    Science.gov (United States)

    Andris, Deborah A

    2005-01-01

    In the United States, obesity has reached epidemic proportions. Serious medical complications, impaired quality of life, and premature mortality are all associated with obesity. Medical conditions such as type 2 diabetes mellitus, hypertension, hyperlipidemia, or sleep apnea can improve or be cured with weight loss. Medical treatment programs focused on diet, behavior modification, and/or pharmacologic intervention have met with limited long-term success. Although surgical treatments for obesity have become popular in recent years, they should only be used as a last resort for weight loss. Not all patients can be considered appropriate candidates for surgery; therefore, guidelines based on criteria from the National Institutes of Health should be used preoperatively to help identify suitable persons. Most individuals who opt for weight-loss surgery have usually struggled for many years with losing weight and keeping it off, but surgery alone will not ensure successful weight loss. Patient education is imperative for long-term success. Moreover, any such educational regimen should include information on diet, vitamin and mineral supplementation, and lifestyle changes, as well as expected weight-loss results and improvements in comorbid conditions. Patients must be willing to commit to a long-term follow-up program intended to promote successful weight loss and weight maintenance and to prevent metabolic and nutritional complications.

  8. Reproducing Epidemiologic Research and Ensuring Transparency.

    Science.gov (United States)

    Coughlin, Steven S

    2017-08-15

    Measures for ensuring that epidemiologic studies are reproducible include making data sets and software available to other researchers so they can verify published findings, conduct alternative analyses of the data, and check for statistical errors or programming errors. Recent developments related to the reproducibility and transparency of epidemiologic studies include the creation of a global platform for sharing data from clinical trials and the anticipated future extension of the global platform to non-clinical trial data. Government agencies and departments such as the US Department of Veterans Affairs Cooperative Studies Program have also enhanced their data repositories and data sharing resources. The Institute of Medicine and the International Committee of Medical Journal Editors released guidance on sharing clinical trial data. The US National Institutes of Health has updated their data-sharing policies. In this issue of the Journal, Shepherd et al. (Am J Epidemiol. 2017;186:387-392) outline a pragmatic approach for reproducible research with sensitive data for studies for which data cannot be shared because of legal or ethical restrictions. Their proposed quasi-reproducible approach facilitates the dissemination of statistical methods and codes to independent researchers. Both reproducibility and quasi-reproducibility can increase transparency for critical evaluation, further dissemination of study methods, and expedite the exchange of ideas among researchers. © The Author(s) 2017. Published by Oxford University Press on behalf of the Johns Hopkins Bloomberg School of Public Health. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  9. EPA requirements for the uranium fuel cycle

    International Nuclear Information System (INIS)

    Dunster, H.J.

    1975-01-01

    The draft Environmental Statement issued by the Environmental Protection Agency (EPA) in the United States in preparation for Proposed Rulemaking Action concerning 'Environmental radiation protection requirements for normal operations of activities in the uranium fuel cycle' is summarized and discussed. The standards proposed by the EPA limit the annual dose equivalents to any member of the public, and also the releases of radionuclides to the 'general environment' for each gigawatt year of electrical energy produced. These standards were based on cost effectiveness arguements and levels and correspond to the ICRP recommendation to keep all exposures as low as reasonably achievable, economic and social factors being taken into account. They should be clearly distinguished from dose limits, although the EPA does not make this at all clear. The EPA seems to have shown an unexpected lack of understanding of the recommendations of ICRP Publication 9 (1965) and an apparent unawareness of ICRP Publication 22 (1973), and has therefore wrongly presented the new standards as a significant change in policy. The EPA has reviewed the information on the likely level of dose equivalents to members of the public and the likely cost reductions, thereby quantifying existing principles as applied to the fuel cycle as a whole. The EPA has stated that its proposals could be achieved as a cost in the region of Pound100,000 per death (or major genetic defect). It is pointed out that the EPA's use of the term 'waste' to exclude liquid and gaseous effluents may cause confusion. (U.K.)

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

    International Nuclear Information System (INIS)

    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

  11. 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.

  12. WIPP WAC Equivalence Support Measurements for Low-Level Sludge Waste at Los Alamos National Laboratory - 12242

    Energy Technology Data Exchange (ETDEWEB)

    Gruetzmacher, Kathleen M.; Bustos, Roland M.; Ferran, Scott G.; Gallegos, Lucas E. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Lucero, Randy P. [Pajarito Scientific Corporation, Santa Fe, New Mexico 87507 (United States)

    2012-07-01

    Los Alamos National Laboratory (LANL) uses the Nevada National Security Site (NNSS) as an off-site disposal facility for low-level waste (LLW), including sludge waste. NNSS has issued a position paper that indicates that systems that are not certified by the Carlsbad Field Office (CBFO) for Waste Isolation Pilot Plant (WIPP) disposal of Transuranic (TRU) waste must demonstrate equivalent practices to the CBFO certified systems in order to assign activity concentration values to assayed items without adding in the Total Measurement Uncertainty (TMU) when certifying waste for NNSS disposal. Efforts have been made to meet NNSS requirements to accept sludge waste for disposal at their facility. The LANL LLW Characterization Team uses portable high purity germanium (HPGe) detector systems for the nondestructive assay (NDA) of both debris and sludge LLW. A number of performance studies have been conducted historically by LANL to support the efficacy and quality of assay results generated by the LANL HPGe systems, and, while these detector systems are supported by these performance studies and used with LANL approved procedures and processes, they are not certified by CBFO for TRU waste disposal. Beginning in 2009, the LANL LLW Characterization Team undertook additional NDA measurements of both debris and sludge simulated waste containers to supplement existing studies and procedures to demonstrate full compliance with the NNSS position paper. Where possible, Performance Demonstration Project (PDP) drums were used for the waste matrix and PDP sources were used for the radioactive sources. Sludge drums are an example of a matrix with a uniform distribution of contaminants. When attempting to perform a gamma assay of a sludge drum, it is very important to adequately simulate this uniform distribution of radionuclides in order to accurately model the assay results. This was accomplished by using a spiral radial source tube placement in a sludge drum rather than the standard

  13. Hydrologic analyses of two brine encounters in the vicinity of the Waste Isolation Pilot Plant (WIPP) Site

    International Nuclear Information System (INIS)

    Spiegler, P.

    1982-12-01

    The data from ERDA-6 indicates a naturally fractured reservoir of the two-porosity type. The best estimate of the volume is about 60 thousand to 120 thousand barrels. The data from WIPP-12 also indicates a naturally fractured reservoir of the two-porosity type. The best estimate of the volume is about 5 million to 10 million barrels. The excess pressure above hydrostatic pressure suggests that the reservoirs were formed many millions of years ago. The location of the fractures suggest that their formation may be connected to the tilting of the Delaware Basin as a unit. The effect of the flow testing data on a drilling scenario through the repository many years following its closure is evaluated

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

    International Nuclear Information System (INIS)

    RECHARD, ROBERT P.

    2000-01-01

    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

  15. A pilot effectiveness study of the Enhancing Parenting Skills (EPaS) 2014 programme for parents of children with behaviour problems: study protocol for a randomised controlled trial.

    Science.gov (United States)

    Williams, Margiad Elen; Hutchings, Judy

    2015-05-20

    The Enhancing Parenting Skills (EPaS) 2014 programme is a home-based, health visitor-delivered parenting support programme for parents of children with identified behaviour problems. This trial aims to evaluate the effectiveness of the EPaS 2014 programme compared to a waiting-list treatment as usual control group. This is a pragmatic, multicentre randomised controlled trial. Sixty health visitors will each be asked to identify two families that have a child scoring above the clinical cut-off for behaviour problems using the Eyberg Child Behaviour Inventory (ECBI). Families recruited to the trial will be randomised in a 1:1 ratio into an intervention or waiting-list control group. Randomisation will occur within health visitor to ensure that each health visitor has one intervention family and one control family. The primary outcome is change in child behaviour problems as measured by the parent-reported ECBI. Secondary outcomes include other measures of child behaviour, parent behaviour, and parental depression as measured by parent-reports and an independent observation of parent and child behaviour. Follow-up measures will be collected 6-months after the collection of baseline measures. This is the first rigorous evaluation of the EPaS 2014 programme. The trial will provide important information on the effectiveness of a one-to-one home-based intervention, delivered by health visitors, for pre-school children with behaviour problems. It will also examine potential mediating (improved parent behaviour and/or improved parental depression) and moderating (single parent, teenage parent, poverty, low education level) factors. Current Controlled Trials ISRCTN06867279 (18 June 2014).

  16. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 6, Chapter D, Appendices D4--D13: Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    This report (Vol. 6) for the WIPP facility contains appendices on the following information: Site characterization; general geology; ecological monitoring; and chemical compatibility of waste forms and container materials.

  17. Environmental Protection Agency - EPA Pub Central

    Data.gov (United States)

    U.S. Environmental Protection Agency — PubMed Central (PMC) is a full-text, online archive of journal literature operated by the National Library of Medicine. The EPA is using PMC to permanently preserve...

  18. EPA Facility Registry Service (FRS): RADINFO

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  19. EPA CIO Governance Board Membership List

    Science.gov (United States)

    In keeping with OMB guidance on implementing the Federal Information Technology Reform Act (FITARA), EPA is publishing its list of officials who perform the duties or responsibilities of a Bureau CIO.

  20. Level IV Ecoregions of EPA Region 1

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  1. Level III Ecoregions of EPA Region 1

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  2. EPA Linked Open Data: Toxics Release Inventory

    Data.gov (United States)

    U.S. Environmental Protection Agency — TRI is a publicly available EPA database reported annually by certain covered industry groups, as well as federal facilities. It contains information about more than...

  3. Concerns raised over new EPA members

    Science.gov (United States)

    Gwynne, Peter

    2017-12-01

    The Trump administration has nominated three new members of the Environmental Protection Agency (EPA) who critics say are undermining laws and “pampering” the industries they are supposed to regulate.

  4. Meet EPA Researcher Endalkachew Sahle-Demessie

    Science.gov (United States)

    Meet EPA Researcher Endalkachew Sahle-Demessie. Chemical and Environmental Engineer Endalkachew Sahle-Demessie, Ph.D., works on various projects, including nanomaterials and water resources, in EPA’s National Risk Management Research Laboratory.

  5. EPA Administrative Law Judge Legal Documents

    Data.gov (United States)

    U.S. Environmental Protection Agency — This dataset contains Decisions and Orders originating from EPAs Office of Administrative Law Judges (OALJ), which is an independent office in the Office of the...

  6. EPA Facility Registry Service (FRS): NEI

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  7. EPA RE-Powering Mapper Feasibility Studies

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  8. EPA Facility Registry Service (FRS): BIA

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  9. EPA RE-Powering Mapper Region 7

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  10. EPA RE-Powering Mapper Large Scale

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  11. EPA RE-Powering Mapper Region 6

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  12. EPA RE-Powering Mapper Region 8

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  13. EPA RE-Powering Mapper Region 5

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  14. EPA RE-Powering Mapper Region 3

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated...

  15. EPA Facility Registry Service (FRS): BRAC

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  16. EPA Region 6 REAP Composite Geodatabse

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Regional Ecological Assessment Protocol (REAP) is a screening level tool created as a way to identify priority ecological resources within the five EPA Region 6...

  17. EPA Facility Registry Service (FRS): NCDB

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  18. EPA Center for Corporate Climate Leadership

    Science.gov (United States)

    EPA's Center for Corporate Climate Leadership is a comprehensive resource to help organizations measure & manage GHG emissions. The Center provides technical tools, educational resources, opportunities for information sharing & highlights best practices.

  19. Level IV Ecoregions of EPA Region 5

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  20. Level IV Ecoregions of EPA Region 10

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  1. Level IV Ecoregions of EPA Region 2

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  2. Level IV Ecoregions of EPA Region 3

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  3. Level III Ecoregions of EPA Region 2

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  4. Level III Ecoregions of EPA Region 4

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  5. Level III Ecoregions of EPA Region 8

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions for EPA Administrative Regions were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the...

  6. Level IV Ecoregions of EPA Region 7

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  7. Level IV Ecoregions of EPA Region 6

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...

  8. Substance Identification Information from EPA's Substance Registry

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Substance Registry Services (SRS) is the authoritative resource for basic information about substances of interest to the U.S. EPA and its state and tribal...

  9. Springs, US EPA Region 9, 2013, SDWIS

    Data.gov (United States)

    U.S. Environmental Protection Agency — EPAâ??s Safe Drinking Water Information System (SDWIS) databases store information about drinking water. The federal version (SDWIS/FED) stores the information EPA...

  10. Reservoirs, US EPA Region 9, 2013, SDWIS

    Data.gov (United States)

    U.S. Environmental Protection Agency — EPAâ??s Safe Drinking Water Information System (SDWIS) databases store information about drinking water. The federal version (SDWIS/FED) stores the information EPA...

  11. EPA Monthly Key Performance Indicator Dashboards 2018

    Science.gov (United States)

    2018 reports are added each month, which measure how well EPA web content is meeting three performance goals: increases in how much users consume content, are able to find or discover what they need, and their level of engagement.

  12. EPA RE-Powering Screening Shapefile

    Data.gov (United States)

    U.S. Environmental Protection Agency — The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management (OLEM) Center for Program Analysis (CPA) initiated the RE-Powering America’s...

  13. EPA Region 1 Sole Source Aquifers

    Data.gov (United States)

    U.S. Environmental Protection Agency — This coverage contains boundaries of EPA-approved sole source aquifers. Sole source aquifers are defined as an aquifer designated as the sole or principal source of...

  14. Checklist for Reviewing EPA Quality Management Plans

    Science.gov (United States)

    This checklist will be used to review the Quality Management Plans (QMPs) that are submitted to the Quality Staff of the Office of Environmental Information (OEI) for Agency review under EPA Order 5360.1 A2.

  15. Quality Management Plan for EPA Region 1

    Science.gov (United States)

    The QMP describes policies, procedures & management systems within EPA NE that govern quality assurance & quality control activities supporting the transparency & scientific defensibility of environmental data collected, used & disseminated by the Region.

  16. EPA Facility Registry Service (FRS): Power Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains data on power plants, based on the Energy Information Administration's EIA-860 dataset and supplemented with data from EPA's Facility...

  17. EPA Communications Stylebook: Training and Education

    Science.gov (United States)

    It is the policy of EPA that our staff should have and develop good communications skills. Besides writing, style, and design skills, we seek to develop audience analysis and targeting, marketing and media selection, and computer skills.

  18. EPA Linked Open Data: Facility Registry Service

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Facility Registry Service (FRS) identifies facilities, sites, or places subject to environmental regulation or of environmental interest to EPA programs or...

  19. Level IV Ecoregions of EPA Region 8

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions for EPA Administrative Regions were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the...

  20. Level III Ecoregions of EPA Region 10

    Data.gov (United States)

    U.S. Environmental Protection Agency — Ecoregions by EPA region were extracted from the seamless national shapefile. Ecoregions denote areas of general similarity in ecosystems and in the type, quality,...