Sample records for nrc guidance nrc

  1. HFE Process Guidance and Standards for potential application to updating NRC guidance

    SciTech Connect (OSTI)

    Jacques Hugo; J. J. Persensky

    2012-07-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) reviews and evaluates the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of these guidance documents to ensure that they remain state-of-the-art design evaluation tools. Thus, the NRC has initiated a project with BNL to update the NRC guidance to remain current with recent research on human performance, advances in HFE methods and tools, and new technology. INL supported Brookhaven National Lab (BNL) to update the detailed HFE review criteria contained in NUREG-0711 and NUREG-0700 based on (1) feedback obtained from end users, (2) the results of NRC research and development efforts supporting the NRC staff’s HFE safety reviews, and (3) other material the project staff identify as applicable to the update effort. INL submitted comments on development plans and sections of NUREGs 0800, 0711, and 0700. The contractor prepared the report attached here as the deliverable for this work.

  2. NRC Recommendations

    Broader source: Energy.gov [DOE]

    Presentation on NRC recommendations to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  3. IN NRC PUBLICATIONS NRC Reference Material

    E-Print Network [OSTI]

    Decommissioning Process

    1999-01-01T23:59:59.000Z

    Publicly released records include, to name a few, NUREG-series publications; Federal Register notices; applicant, licensee, and vendor documents and correspondence; NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their attachments. NRC publications in the NUREG series, NRC regulations, and Title 10, Energy, in the Code of Federal Regulations may also be purchased from one of these two sources.

  4. Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407

    SciTech Connect (OSTI)

    Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

    2013-07-01T23:59:59.000Z

    This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

  5. Status of the NRC Decommissioning Program

    SciTech Connect (OSTI)

    Orlando, D. A.; Camper, L.; Buckley, J.; Pogue, E.; Banovac, K.

    2003-02-24T23:59:59.000Z

    On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.

  6. NRC Construction Light Source Flicker: What We

    E-Print Network [OSTI]

    California at Davis, University of

    NRC Construction Light Source Flicker: What We Need to Know, and Why You Should Care NRC Construction Jennifer A. Veitch, Ph.D. (c) 2013, National Research Council Canada #12;NRC Construction Handbook: Reference & Application (9th Ed.), 2000, p. 3-20 #12;NRC Construction Flicker Effects 1

  7. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    SciTech Connect (OSTI)

    Orlando, D. A.; Camper, L. W.; Buckley, J.

    2002-02-25T23:59:59.000Z

    On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

  8. NRC antitrust licensing actions, 1978--1996

    SciTech Connect (OSTI)

    Mayer, S.J.; Simpson, J.J.

    1997-09-01T23:59:59.000Z

    NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC`s competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC`s antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission`s Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission`s antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC`s antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs.

  9. NRC Leadership Expectations and Practices for Sustaining a High...

    Office of Environmental Management (EM)

    NRC Leadership Expectations and Practices for Sustaining a High Performing Organization NRC Leadership Expectations and Practices for Sustaining a High Performing Organization May...

  10. 1996 NRC annual report. Volume 13

    SciTech Connect (OSTI)

    NONE

    1997-10-01T23:59:59.000Z

    This 22nd annual report of the US Nuclear Regulatory Commission (NRC) describes accomplishments, activities, and plans made during Fiscal Year 1996 (FH 1996)--October 1, 1995, through September 30, 1996. Significant activities that occurred early in FY 1997 are also described, particularly changes in the Commission and organization of the NRC. The mission of the NRC is to ensure that civilian uses of nuclear materials in the US are carried out with adequate protection of public health and safety, the environment, and national security. These uses include the operation of nuclear power plants and fuel cycle plants and medical, industrial, and research applications. Additionally, the NRC contributes to combating the proliferation of nuclear weapons material worldwide. The NRC licenses and regulates commercial nuclear reactor operations and research reactors and other activities involving the possession and use of nuclear materials and wastes. It also protects nuclear materials used in operation and facilities from theft or sabotage. To accomplish its statutorily mandated regulatory mission, the NRC issues rules and standards, inspects facilities and operations, and issues any required enforcement actions.

  11. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

  12. NRC drug-free workplace plan. Revision 1

    SciTech Connect (OSTI)

    NONE

    1997-11-01T23:59:59.000Z

    On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ``NRC Drug-Free Workplace Plan,`` supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance.

  13. Microsoft PowerPoint - 5_Pat Smith_NMMSS_2013_Presentation_NRC...

    National Nuclear Security Administration (NNSA)

    Reconciliation Pat Smith PSI NRC Lead NRC Reconciliation NRC Reconciliation requirements per NUREGBR-0007, Rev. 6 All RIS's must submit an MSR (Material Summary Report)...

  14. A review of NRC staff uses of probabilistic risk assessment

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements its licensing and regulatory processes. In October 1991, the NRC`s Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff`s current uses of PRA. After surveying current staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development. For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group recommended integrating its work with other recent PRA-related activities the staff completed and improving staff interactions with PRA users in the nuclear industry. The Working Group took two key actions by developing general guidance for two uses of PRA within the NRC (that is, screening or prioritizing reactor safety issues and analyzing such issues in detail) and developing guidance on basic terms and methods important to the staff`s uses of PRA.

  15. 4th Annual NRC Small Business Seminar and Matchmaking Event

    Broader source: Energy.gov [DOE]

    The U.S. NRC regulates commercial and institutional uses of nuclear energy to protect the public health and safety, promote the common defense and security, and protect the environment. Attendees will hear directly from NRC leadership on the vision and priorities of the NRC at its Headquarters in Rockville, Maryland, including current acquisition initiatives and how small businesses can support their mission.

  16. Microsoft PowerPoint - 9_NRC Roundtable Cover_Wensday_NMMSS_2014...

    National Nuclear Security Administration (NNSA)

    and Industry Roundtable Discussion Paul Adam, Wolf Creek Nuclear Operating Corp Suzanne Ani, NRC Brian Horn, NRC...

  17. o:\informs\fixforms\nrc741.wpf

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof Energy 2, 2015Visiting8.pdfand Characterization of aHome *NRC FORM 741 (5-2002)

  18. NRC Transportation Security (Part 73 SNF Update and Part 37 Category...

    Office of Environmental Management (EM)

    NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and 2 Materials) NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and 2 Materials) NRC...

  19. NRC policy on future reactor designs

    SciTech Connect (OSTI)

    none,

    1985-07-01T23:59:59.000Z

    On April 13, 1983, the US Nuclear Regulatory Commission issued for public comment a ''Proposed Commission Policy Statement on Severe Accidents and Related Views on Nuclear Reactor Regulation'' (48 FR 16014). This report presents and discusses the Commission's final version of that policy statement now entitled, ''Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants.'' It provides an overview of comments received from the public and the Advisory Committee on Reactor Safeguards and the staff response to these. In addition to the Policy Statement, the report discusses how the policies of this statement relate to other NRC programs including the Severe Accident Research Program; the implementation of safety measures resulting from lessons learned in the accident at Three Mile Island; safety goal development; the resolution of Unresolved Safety Issues and other Generic Safety Issues; and possible revisions of rules or regulatory requirements resulting from the Severe Accident Source Term Program. Also discussed are the main features of a generic decision strategy for resolving Regulatory Questions and Technical Issues relating to severe accidents; the development and regulatory use of new safety information; the treatment of uncertainty in severe accident decision making; and the development and implementation of a Systems Reliability Program for both existing and future plants to ensure that the realized level of safety is commensurate with the safety analyses used in regulatory decisions.

  20. Comparative Analysis Between US NRC Requirements and US DOE Orders - 13402

    SciTech Connect (OSTI)

    Chakraborti, Sayan [MRIGlobal, 425 Volker Blvd, Kansas City, MO 64110 (United States)] [MRIGlobal, 425 Volker Blvd, Kansas City, MO 64110 (United States); Stone, Lynn; Hyatt, Jeannette [Savannah River Nuclear Solutions (United States)] [Savannah River Nuclear Solutions (United States)

    2013-07-01T23:59:59.000Z

    Small modular reactor (SMR) is a nuclear reactor design approach that is expected to herald in a new era of clean energy in the U.S. These reactors are less than one-third the size of conventional large nuclear power reactors, and have factory-fabricated components that may be transported by rail or truck to a site selected to house a small nuclear reactor. To facilitate the licensing of these smaller nuclear reactor designs, the Nuclear Regulatory Commission (NRC) is in the process of developing a regulatory infrastructure to support licensing review of these unique reactor designs. As part of these activities, the NRC has been meeting with the Department of Energy (DOE) and with individual SMR designers to discuss potential policy, licensing, and key technical differences in SMR designs. It is anticipated by the NRC that such licensing interaction and guidance early in the design process will contribute towards minimizing complexity while adding stability and predictability in the licensing and subsequent regulation of new reactor designs such as SMRs. In conjunction with the current NRC initiative of developing the SMR licensing process, early communication and collaboration in the identification and resolution of any potential technical and licensing differences between NRC requirements and similar requirements applicable at DOE sites would help to expedite demonstration and implementation of SMR technology in the US. In order to foster such early communication, Savannah River Nuclear Solutions (SRNS) has begun taking the first steps in identifying and evaluating potential licensing gaps that may exist between NRC and DOE requirements in siting SMRs at DOE sites. A comparison between the existing NRC regulations for Early Site Permits and the DOE Orders was undertaken to establish the degree of correlation between NRC requirements and compliance methods in place at DOE sites. The ability to use existing data and information to expedite the development of the Environmental Report is being evaluated at the Savannah River Site as a case study for application across the DOE Complex. This paper will present areas of direct correlation as well as those where the need for site specific data for either DOE operations or NRC compliance warrant additional interaction between the agencies. Areas where further refinement of the SMR technologies may drive collaborative development of revised regulations through such means as industry consensus standards will also be highlighted. Both NRC and DOE have requirements that mandate public involvement in their processes. The importance and value of early engagement with the public as well as collaborating regulatory agencies is of critical importance when deploying new technologies. (authors)

  1. Congress, NRC mull utility access to FBI criminal files

    SciTech Connect (OSTI)

    Ultroska, D.

    1984-08-01T23:59:59.000Z

    Experiences at Alabama Power Company and other nuclear utilities have promped a request for institutionalizing security checks of personnel in order to eliminated convicted criminals and drug users. The Nuclear Regulatory Commission (NRC), which could provide FBI criminal history information by submitting fingerprints, does not do so, and would require new legislation to take on that duty. Believing that current malevolent employees can be managed with existing procedures, NRC allows criminal background checks only on prospective employees in order to avoid a negative social impact on personnel. Legislation to transfer criminal histories to nuclear facilities is now pending, and NRC is leaning toward a request for full disclosure, partly because of terrorist threats and partly to save manpower time and costs in reviewing case histories.

  2. EPRI/NRC-RES fire human reliability analysis guidelines.

    SciTech Connect (OSTI)

    Lewis, Stuart R. (Electric Power Research Institute, Charlotte, NC); Cooper, Susan E. (U.S. Nuclear Regulatory Commission, Rockville, MD); Najafi, Bijan (SAIC, Campbell, CA); Collins, Erin (SAIC, Campbell, CA); Hannaman, Bill (SAIC, Campbell, CA); Kohlhepp, Kaydee (Scientech, Tukwila, WA); Grobbelaar, Jan (Scientech, Tukwila, WA); Hill, Kendra (U.S. Nuclear Regulatory Commission, Rockville, MD); Hendrickson, Stacey M. Langfitt; Forester, John Alan; Julius, Jeff (Scientech, Tukwila, WA)

    2010-03-01T23:59:59.000Z

    During the 1990s, the Electric Power Research Institute (EPRI) developed methods for fire risk analysis to support its utility members in the preparation of responses to Generic Letter 88-20, Supplement 4, 'Individual Plant Examination - External Events' (IPEEE). This effort produced a Fire Risk Assessment methodology for operations at power that was used by the majority of U.S. nuclear power plants (NPPs) in support of the IPEEE program and several NPPs overseas. Although these methods were acceptable for accomplishing the objectives of the IPEEE, EPRI and the U.S. Nuclear Regulatory Commission (NRC) recognized that they required upgrades to support current requirements for risk-informed, performance-based (RI/PB) applications. In 2001, EPRI and the USNRC's Office of Nuclear Regulatory Research (RES) embarked on a cooperative project to improve the state-of-the-art in fire risk assessment to support a new risk-informed environment in fire protection. This project produced a consensus document, NUREG/CR-6850 (EPRI 1011989), entitled 'Fire PRA Methodology for Nuclear Power Facilities' which addressed fire risk for at power operations. NUREG/CR-6850 developed high level guidance on the process for identification and inclusion of human failure events (HFEs) into the fire PRA (FPRA), and a methodology for assigning quantitative screening values to these HFEs. It outlined the initial considerations of performance shaping factors (PSFs) and related fire effects that may need to be addressed in developing best-estimate human error probabilities (HEPs). However, NUREG/CR-6850 did not describe a methodology to develop best-estimate HEPs given the PSFs and the fire-related effects. In 2007, EPRI and RES embarked on another cooperative project to develop explicit guidance for estimating HEPs for human failure events under fire generated conditions, building upon existing human reliability analysis (HRA) methods. This document provides a methodology and guidance for conducting a fire HRA. This process includes identification and definition of post-fire human failure events, qualitative analysis, quantification, recovery, dependency, and uncertainty. This document provides three approaches to quantification: screening, scoping, and detailed HRA. Screening is based on the guidance in NUREG/CR-6850, with some additional guidance for scenarios with long time windows. Scoping is a new approach to quantification developed specifically to support the iterative nature of fire PRA quantification. Scoping is intended to provide less conservative HEPs than screening, but requires fewer resources than a detailed HRA analysis. For detailed HRA quantification, guidance has been developed on how to apply existing methods to assess post-fire fire HEPs.

  3. Report to the NRC on guidance for preparing scenarios for emergency preparedness exercises at nuclear generating stations. Draft report for comment

    SciTech Connect (OSTI)

    Martin, G.F.; Hickey, E.E.; Moeller, M.P.; Schultz, D.H.; Bethke, G.W.

    1986-03-01T23:59:59.000Z

    A scenario guidance handbook was prepared to assist emergency planners in developing scenarios for emergency preparedness exercises at nuclear power plants. The handbook provides guidance for the development of the objectives of an exercise, the descriptions of scenario events and responses, and the instructions to the participants. Information concerning implementation of the scenario, critiques and findings, and generation and format of scenario data are also included. Finally, examples of manual calculational techniques for producing radiological data are included as an appendix.

  4. Enhancement of NRC station blackout requirements for nuclear power plants

    SciTech Connect (OSTI)

    McConnell, M. W. [United States Nuclear Regulatory Commission, Mail Stop: 012-H2, Washington, DC 20555 (United States)

    2012-07-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to enhance core and spent fuel pool cooling, reactor coolant system integrity, and containment integrity. (authors)

  5. Recommendations for NEAMS Engagement with the NRC: Preliminary Report

    SciTech Connect (OSTI)

    Bernholdt, David E [ORNL

    2012-06-01T23:59:59.000Z

    The vision of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to bring a new generation of analytic tools to the nuclear engineering community in order to facilitate students, faculty, industry and laboratory researchers in investigating advanced reactor and fuel cycle designs. Although primarily targeting at advance nuclear technologies, it is anticipated that these new capabilities will also become interesting and useful to the nuclear regulator Consequently, the NEAMS program needs to engage with the Nuclear Regulatory Commission as the software is being developed to ensure that they are familiar with and ready to respond to this novel approach when the need arises. Through discussions between key NEAMS and NRC staff members, we tentatively recommend annual briefings to the Division of Systems Analysis in the NRC's Office of Nuclear Regulatory Research. However the NEAC subcommittee review of the NEAMS program may yield recommendations that would need to be considered before finalizing this plan.

  6. NRC support for the Kalinin (VVER) probabilistic risk assessment

    SciTech Connect (OSTI)

    Bley, D. [Buttonwood Consulting, Inc. (United States); Diamond, D.J.; Chu, T.L.; Azarm, A.; Pratt, W.T. [Brookhaven National Lab., Upton, NY (United States); Johnson, D. [PLG, Inc. (United States); Szukiewicz, A.; Drouin, M.; El-Bassioni, A.; Su, T.M. [Nuclear Regulatory Commission (United States)

    1998-12-31T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory and its subcontractors. The latter support was carried out through workshops, by documenting the methodology to be used in a set of guides, and through periodic review of the technical activity. The result of this effort to date includes a set of procedure guides, a draft final report on the Level 1 PRA for internal events (excluding internal fires and floods), and progress reports on the fire, flood, and seismic analysis. It is the authors belief that the type of assistance provided by the NRC has been instrumental in assuring a quality product and transferring important technology for use by regulators and operators of Soviet-designed reactors. After a thorough review, the report will be finalized, lessons learned will be applied in the regulatory and operational regimes in the Russian Federation, and consideration will be given to supporting a containment analysis in order to complete a simplified Level 2 PRA.

  7. NRC SUPPORT FOR THE KALININ (VVER) PROBABILISTIC RISK ASSESSMENT

    SciTech Connect (OSTI)

    BLEY,D.; DIAMOND,D.J.; CHU,T.L.; AZARM,A.; PRATT,W.T.; JOHNSON,D.; SZUKIEWICZ,A.; DROUIN,M.; EL-BASSIONI,A.; SU,T.M.

    1998-10-26T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory and its subcontractors. The latter support was carried out through workshops, by documenting the methodology to be used in a set of guides, and through periodic review of the technical activity. The result of this effort to date includes a set of procedure guides, a draft final report on the Level 1 PRA for internal events (excluding internal fires and floods), and progress reports on the fire, flood, and seismic analysis. It is the authors belief that the type of assistance provided by the NRC has been instrumental in assuring a quality product and transferring important technology for use by regulators and operators of Soviet-designed reactors. After a thorough review, the report will be finalized, lessons learned will be applied in the regulatory and operational regimes in the Russian Federation, and consideration will be given to supporting a containment analysis in order to complete a simplified Level 2 PRA.

  8. Government perspective. [FY 1994 budgets for DOE and NRC

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    During April, several Congressional committees held hearings on the FY 1994 budget submitted by the Department of Energy (DOE). DOE has requested a total nuclear energy budget of $165 million, reduced from $299.3 million in FY 1993. Energy Secretary Hazel O'Leary and acting Assistant Secretary for Nuclear Energy, Mr. E.C. Brolin, testified that DOE intends to continue to fund research for light water reactors (LWR) at a level of $57.8 million during FY 1994, a slight decline from the $58.7 million requested for FY 1993. The LWR program funding will allow work to continue on the standardization and design certification programs. However, DOE's proposed $45 million budget cut, to only $15 million, for funding of advanced nuclear research and development programs has been sharply criticized by nuclear industry supporters in Congress. The Nuclear Regulatory Commission's (NRC) Chairman, Ivan Selin, testified before the House Energy and Water Appropriations Subcommittee regarding NRC's budget request. NRC is requesting $547.7 million for FY 1994, an increase of 1.5 percent over the FY 1993 budget.

  9. Peer Review of NRC Standardized Plant Analysis Risk Models

    SciTech Connect (OSTI)

    Anthony Koonce; James Knudsen; Robert Buell

    2011-03-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) Standardized Plant Analysis Risk (SPAR) Models underwent a Peer Review using ASME PRA standard (Addendum C) as endorsed by NRC in Regulatory Guide (RG) 1.200. The review was performed by a mix of industry probabilistic risk analysis (PRA) experts and NRC PRA experts. Representative SPAR models, one PWR and one BWR, were reviewed against Capability Category I of the ASME PRA standard. Capability Category I was selected as the basis for review due to the specific uses/applications of the SPAR models. The BWR SPAR model was reviewed against 331 ASME PRA Standard Supporting Requirements; however, based on the Capability Category I level of review and the absence of internal flooding and containment performance (LERF) logic only 216 requirements were determined to be applicable. Based on the review, the BWR SPAR model met 139 of the 216 supporting requirements. The review also generated 200 findings or suggestions. Of these 200 findings and suggestions 142 were findings and 58 were suggestions. The PWR SPAR model was also evaluated against the same 331 ASME PRA Standard Supporting Requirements. Of these requirements only 215 were deemed appropriate for the review (for the same reason as noted for the BWR). The PWR review determined that 125 of the 215 supporting requirements met Capability Category I or greater. The review identified 101 findings or suggestions (76 findings and 25 suggestions). These findings or suggestions were developed to identify areas where SPAR models could be enhanced. A process to prioritize and incorporate the findings/suggestions supporting requirements into the SPAR models is being developed. The prioritization process focuses on those findings that will enhance the accuracy, completeness and usability of the SPAR models.

  10. NRC Reviewer Aid for Evaluating the Human Factors Engineering Aspects of Small Modular Reactors

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.C.

    2012-01-13T23:59:59.000Z

    Small modular reactors (SMRs) are a promising approach to meeting future energy needs. Although the electrical output of an individual SMR is relatively small compared to that of typical commercial nuclear plants, they can be grouped to produce as much energy as a utility demands. Furthermore, SMRs can be used for other purposes, such as producing hydrogen and generating process heat. The design characteristics of many SMRs differ from those of current conventional plants and may require a distinct concept of operations (ConOps). The U.S. Nuclear Regulatory Commission (NRC) conducted research to examine the human factors engineering (HFE) and the operational aspects of SMRs. The research identified thirty potential human-performance issues that should be considered in the NRC's reviews of SMR designs and in future research activities. The purpose of this report is to support NRC HFE reviewers of SMR applications by identifying some of the questions that can be asked of applicants whose designs have characteristics identified in the issues. The questions for each issue were identified and organized based on the review elements and guidance contained in Chapter 18 of the Standard Review Plan (NUREG-0800), and the Human Factors Engineering Program Review Model (NUREG-0711).

  11. ISDAC - NRC Convair-580 Flight Hours Date Flight

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh School footballHydrogen andHypernucleiNORTHWESTOffice ofOffice- NRC

  12. DOE/NRC F 740M | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015 Business42.1 DEPARTMENTSeptember 27,September 24, 2002The RoundtableDOE/NRC

  13. NRC Institute for Fuel Cell Innovation | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall, Pennsylvania: Energy Resources JumpNEFAppropriationReference Manual 53:NRC

  14. Reassessment of the NRC`s program for protecting allegers against retaliation

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    On July 6, 1993, the Nuclear Regulatory Commission`s (NRC`s) Executive Director for Operations established a review team to reassess the NRC`s program for protecting allegers against retaliation. The team evaluated the current system, and solicited comments from various NRC offices, other Federal agencies, licensees, former allegers, and the public. This report is subject to agency review. The report summarizes current processes and gives an overview of current problems. It discusses: (1) ways in which licensees can promote a quality-conscious work environment, in which all employees feel free to raise concerns without fear of retaliation; (2) ways to improve the NRC`s overall handling of allegations; (3) the NRC`s involvement in the Department of Labor process; (4) related NRC enforcement practices; and (5) methods other than investigation and enforcement that may be useful in treating allegations of potential or actual discrimination. Recommendations are given in each area.

  15. Microsoft PowerPoint - 2_Peter J. Habighorst_NRC Remarks 2013...

    National Nuclear Security Administration (NNSA)

    General licenses 8 NRC Internal actions, cont. * Exports to power reactors in Canada, Germany and Japan were identified: - KNK, THTR, AVR, JOYO, FUGEN, Bruce * General licenses...

  16. Microsoft PowerPoint - 8_Peter Habighorst_NRC_Act of 2012-status...

    National Nuclear Security Administration (NNSA)

    General licenses 8 NRC Internal actions, cont. * Exports to power reactors in Canada, Germany and Japan were identified: - KNK, THTR, AVR, JOYO, FUGEN, Bruce * General licenses...

  17. NRC Technical Research Program to Evaluate Extended Storage and Transportation of Spent Nuclear Fuel - 12547

    SciTech Connect (OSTI)

    Einziger, R.E.; Compton, K.; Gordon, M.; Ahn, T.; Gonzales, H. [United States Nuclear Regulatory Commission, Rockville, Maryland 20852 (United States); Pan, Y. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238 (United States)

    2012-07-01T23:59:59.000Z

    Any new direction proposed for the back-end of spent nuclear fuel (SNF) cycle will require storage of SNF beyond the current licensing periods. The Nuclear Regulatory Commission (NRC) has established a technical research program to determine if any changes in the 10 CFR part 71, and 72 requirements, and associated guidance might be necessary to regulate the safety of anticipated extended storage, and subsequent transport of SNF. This three part program of: 1) analysis of knowledge gaps in the potential degradation of materials, 2) short-term research and modeling, and 3) long-term demonstration of systems, will allow the NRC to make informed regulatory changes, and determine when and if additional monitoring and inspection of the systems is necessary. The NRC has started a research program to obtain data necessary to determine if the current regulatory guidance is sufficient if interim dry storage has to be extended beyond the currently approved licensing periods. The three-phased approach consists of: - the identification and prioritization of potential degradation of the components related to the safe operation of a dry cask storage system, - short-term research to determine if the initial analysis was correct, and - a long-term prototypic demonstration project to confirm the models and results obtained in the short-term research. The gap analysis has identified issues with the SCC of the stainless steel canisters, and SNF behavior. Issues impacting the SNF and canister internal performance such as high and low temperature distributions, and drying have also been identified. Research to evaluate these issues is underway. Evaluations have been conducted to determine the relative values that various types of long-term demonstration projects might provide. These projects or follow-on work is expected to continue over the next five years. (authors)

  18. NRC, SPI, and chasing arrows: Is there common ground

    SciTech Connect (OSTI)

    Rabasca, L.

    1994-12-01T23:59:59.000Z

    After negotiating for 15 months, issuing three white papers, and conducting consumer research, the National Recycling Coalition (NRC, Washington, DC) and the Society of the Plastics Industry, Inc. (SPI, Washington, DC), have agreed to disagree on the use of the familiar chasing arrows logo in SPI's seven-number resin identification code. The desired end result of the talks and debates was supposed to be a plan to change legislation requiring 39 states to use SPI's current resin identification code and a commitment to remove the old code from durable goods and flexible packaging. Ultimately, these actions could have improved markets for polyethylene terephthalate (PET) and high-density polyethylene (HDPE) by reducing contamination caused by confusion over what is actually recycled versus what is merely recyclable.

  19. Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 3, Development documentation

    SciTech Connect (OSTI)

    Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

    1993-10-01T23:59:59.000Z

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program.

  20. Recommendations for NRC policy on shift scheduling and overtime at nuclear power plants

    SciTech Connect (OSTI)

    Lewis, P.M.

    1985-07-01T23:59:59.000Z

    This report contains the Pacific Northwest Laboratory's (PNL's) recommendations to the US Nuclear Regulatory Commission (NRC) for an NRC policy on shift scheduling and hours of work (including overtime) for control room operators and other safety-related personnel in nuclear power plants. First, it is recommended that NRC make three additions to its present policy on overtime: (1) limit personnel to 112 hours of work in a 14-day period, 192 hours in 28 days, and 2260 hours in one year; exceeding these limits would require plant manager approval; (2) add a requirement that licensees obtain approval from NRC if plant personnel are expected to exceed 72 hours of work in a 7-day period, 132 hours in 14 days, 228 hours in 28 days, and 2300 hours in one year; and (3) make the policy a requirement, rather than a nonbinding recommendation. Second, it is recommended that licensees be required to obtain NRC approval to adopt a routine 12-hour/day shift schedule. Third, it is recommended that NRC add several nonbinding recommendations concerning routine 8-hour/day schedules. Finally, because additional data can strengthen the basis for future NRC policy on overtime, five methods are suggested for collecting data on overtime and its effects. 44 refs., 10 tabs.

  1. A RE-LOOK AT THE US NRC SAFETY GOALS

    SciTech Connect (OSTI)

    mubayi v.

    2013-09-22T23:59:59.000Z

    Since they were adopted in 1986, the US NRC’s Safety Goals have played a valuable role as a de facto risk acceptance criterion against which the predicted performance of a commercial nuclear power reactor can be evaluated and assessed. The current safety goals are cast in terms of risk metrics called quantitative health objectives (QHOs), limiting numerical values of the risks of the early and latent health effects of accidental releases of radioactivity to the offsite population. However, while demonstrating compliance with current safety goals has been an important step in assessing the acceptance of the risk posed by LWRs, new or somewhat different goals may be needed that go beyond the current early fatality and latent cancer fatality QHOs in assessing reactor risk. Natural phenomena such as hurricanes seem to be suitable candidates for establishing a background rate to derive a risk goal as their order of magnitude cost of damages is similar to those estimated in severe accident Level 3 PRAs done for nuclear power plants. This paper obtains a risk goal that could have a wider applicability, compared to the current QHOs, as a technology-neutral goal applicable to future reactors and multi-unit sites.

  2. Status of VICTORIA: NRC peer review and recent code applications

    SciTech Connect (OSTI)

    Bixler, N.E. [Sandia National Labs., Albuquerque, NM (United States); Schaperow, J.H. [Nuclear Regulatory Commission, Washington, DC (United States)

    1997-12-01T23:59:59.000Z

    VICTORIA is a mechanistic computer code designed to analyze fission product behavior within a nuclear reactor coolant system (RCS) during a severe accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport and deposition of these materials within the RCS. A summary of the results and recommendations of an independent peer review of VICTORIA by the US Nuclear Regulatory Commission (NRC) is presented, along with recent applications of the code. The latter include analyses of a temperature-induced steam generator tube rupture sequence and post-test analyses of the Phebus FPT-1 test. The next planned Phebus test, FTP-4, will focus on fission product releases from a rubble bed, especially those of the less-volatile elements, and on the speciation of the released elements. Pretest analyses using VICTORIA to estimate the magnitude and timing of releases are presented. The predicted release of uranium is a matter of particular importance because of concern about filter plugging during the test.

  3. Microsoft PowerPoint - 4_JOHN_BALLARD_MARY_MCCDONNELL_NRC DOE...

    National Nuclear Security Administration (NNSA)

    Len Myers Special Requests (301) 903-2180 Len.Myers@nnsa.doe.gov Patricia Smith NRC Reconciliation (301) 903-6860 PatriciaR.Smith@nnsa.doe.gov Reasons to Call NMMSS -...

  4. NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

    SciTech Connect (OSTI)

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)] [U.S. Nuclear Regulatory Commission (United States)

    2013-07-01T23:59:59.000Z

    As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

  5. NRC safety research in support of regulation - FY 1994. Volume 9

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    This report, the tenth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1994. The goal of the Office of Nuclear Regulatory Research (RES) is to ensure the availability of sound technical bases for timely rulemaking and related decisions in support of NRC regulatory/licensing/inspection activities. RES also has responsibilities related to the resolution of generic safety issues and to the review of licensee submittals regarding individual plant examinations. It is the responsibility of RES to conduct the NRC`s rulemaking process, including the issuance of regulatory guides and rules that govern NRC licensed activities.

  6. Coordinating NRC License Closure/Termination and Army Corps of Engineers FUSRAP Cleanups

    SciTech Connect (OSTI)

    Walter, N. [MACTEC, 511 Congress Street, Portland, ME 04101 (United States); Greene, D. R. [LeBoeuf, Lamb, Greene and MacRae LLP, 225 Asylum Street, Hartford, CT 06103 (United States); Knauerhase, R. K. [Combustion Engineering, 2000 Day Hill Road, CEP 5580-2207, Windsor, CT 06095 (United States)

    2006-07-01T23:59:59.000Z

    Overlapping regulatory cleanup programs present a significant challenge for business entities seeking to close and redevelop properties in an environmentally-appropriate but cost-effective manner. In the nuclear decontamination context, this challenge has been recognized in Memoranda of Understanding ('MOUs') between regulators with overlapping responsibilities seeking to minimize duplicative efforts/costs while fulfilling their respective regulatory obligations. For instance, an MOU between the Army Corps of Engineers (the 'Corps') and the Nuclear Regulatory Commission ('NRC') for coordinating Corps' cleanups under the Formerly Utilized Sites Remedial Action Program ('FUSRAP') and NRC D and D to close and terminate an NRC license was reached in July 2001. Similarly, U.S. Environmental Protection Agency ('EPA') and NRC entered into an MOU in October 2002 addressing the interaction between NRC decontamination and decommissioning ('D and D') oversight and EPA's authority under the Comprehensive Environmental Response, Compensation and Liability Act ('CERCLA') at NRC-licensed sites. Yet, despite these MOU agreements, the simultaneous application of different regulatory programs, differing perspectives on their respective objectives and limited experience in addressing such circumstances often can lead to issues that demand creative solutions. This paper examines the interplay of these regulatory programs, the MOU of the agencies seeking to address their responsibilities under them and the coordination of the cleanups and license closure/termination process under the programs. It also offers technical and practical suggestions and insight to cost-effectively manage such efforts based on experiences with these programs and the regulators and stakeholders involved (at the federal, state and local levels). (authors)

  7. New security measures are proposed for N-plants: Insider Rule package is issued by NRC

    SciTech Connect (OSTI)

    Not Available

    1984-09-01T23:59:59.000Z

    New rules proposed by the Nuclear Regulatory Commission (NRC) will require background investigations and psychological assessments of new job candidates and continual monitoring of the behavior of all power plant workers with access to sensitive areas. Licensees will have to submit an ''access authorization'' program for approval describing how they will conduct these security activities. The employee checks will go back five years to examine credit, educational, and criminal histories. Implementation of the rules could involve the Edison Electric Institute as an intermediary to funnel criminal checks from the Justice Department and FBI. The NRC is also considering a clarification of areas designated as ''vital'' because current designations may be too strict.

  8. Final report of the NRC-Agreement State Working Group to evaluate control and accountability of licensed devices

    SciTech Connect (OSTI)

    NONE

    1996-10-01T23:59:59.000Z

    US NRC staff acknowledged that licensees were having problems maintaining control over and accountability for devices containing radioactive material. In June 1995, NRC approved the staff`s suggestion to form a joint NRC-Agreement State Working Group to evaluate the problem and propose solutions. The staff indicated that the Working Group was necessary to address the concerns from a national perspective, allow for a broad level of Agreement State input, and to reflect their experience. Agreement State participation in the process was essential since some Agreement States have implemented effective programs for oversight of device users. This report includes the 5 recommendations proposed by the Working Group to increase regulatory oversight, increase control and accountability of devices, ensure proper disposal, and ensure disposal of orphaned devices. Specifically, the Working Group recommends that: (1) NRC and Agreement States increase regulatory oversight for users of certain devices; (2) NRC and Agreement State impose penalties on persons losing devices; (3) NRC and Agreement States ensure proper disposal of orphaned devices; (4) NRC encourage States to implement similar oversight programs for users of Naturally-Occurring or Accelerator- Produced Material; and (5) NRC encourage non-licensed stakeholders to take appropriate actions, such as instituting programs for material identification.

  9. NRC staff site characterization analysis of the Department of Energy`s Site Characterization Plan, Yucca Mountain Site, Nevada

    SciTech Connect (OSTI)

    NONE

    1989-08-01T23:59:59.000Z

    This Site Characterization Analysis (SCA) documents the NRC staff`s concerns resulting from its review of the US Department of Energy`s (DOE`s) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation`s first geologic repository for high-level radioactive waste. DOE`s SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC`s specific objections related to the SCP, and major comments and recommendations on the various parts of DOE`s program, are presented in SCA Section 2, Director`s Comments and Recommendations. Section 3 contains summaries of the NRC staff`s concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE`s program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC`s responsibilities with respect to DOE`s SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs.

  10. License renewal demonstration program: NRC observations and lessons learned

    SciTech Connect (OSTI)

    Prato, R.J.; Kuo, P.T.; Newberry, S.F.

    1996-12-01T23:59:59.000Z

    This report summarizes the Nuclear Regulatory Commission staff`s observations and lessons learned from the five License Renewal Demonstration Program (LRDP) site visits performed by the staff from March 25, 1996, through August 16, 1996. The LRDP was a Nuclear Energy Institute (NEI) program intended to assess the effectiveness of the guidance provided by NEI 95-10, Revision 0, {open_quotes}Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule,{close_quotes} to implement the requirements of Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), {open_quotes}Requirements for Renewal of Operating Licenses for Nuclear Power Plants.{close_quotes} In general, NEI 95-10 appeared to contain the basic guidance needed for scoping, screening, identifying aging effects, developing aging management programs, and performing time-limited aging analyses. However, inconsistent implementation of this guidance in some areas was an indication that clarification of existing guidance and/or the inclusion-of some new guidance may be needed for applicants to develop a license renewal program that is consistent with the intent of the rule.

  11. NRC Earth Science Decadal Survey-Mission Concept Earth Sciences from the Astronomer's Perspective, a Deep

    E-Print Network [OSTI]

    Christian, Eric

    NRC Earth Science Decadal Survey-Mission Concept Earth Sciences from the Astronomer's Perspective Irina Melnikova #12;1 Earth Sciences from the Astronomer's Perspective 1.0 Mission Concept and Purpose Earth observations from satellites located in deep space offer the exciting opportunity to look

  12. NRC (Nuclear Regulatory Commission) perspective of software QA (quality assurance) in the nuclear history

    SciTech Connect (OSTI)

    Weiss, S.H.

    1988-01-01T23:59:59.000Z

    Computer technology has been a part of the nuclear industry since its inception. However, it is only recently that computers have been integrated into reactor operations. During the early history of commercial nuclear power in the United States, the US Nuclear Regulatory Commission (NRC) discouraged the use of digital computers for real-time control and monitoring of nuclear power plant operation. At the time, this position was justified since software engineering was in its infancy, and horror stories on computer crashes were plentiful. Since the advent of microprocessors and inexpensive computer memories, significant advances have been made in fault-tolerant computer architecture that have resulted in highly reliable, durable computer systems. The NRC's requirement for safety parameter display system (SPDS) stemmed form the results of studies and investigations conducted on the Three Mile Island Unit 2 (TMI-2) accident. An NRC contractor has prepared a handbook of software QA techniques applicable to the nuclear industry, published as NUREG/CR-4640 in August 1987. Currently, the NRC is considering development of an inspection program covering software QA. Future efforts may address verification and validation as applied to expert systems and artificial intelligence programs.

  13. Understanding and Interpreting the NRC's "Data-Based Assessment of Research-Doctorate

    E-Print Network [OSTI]

    Navara, Kristen

    member per year [2000-2006] R Avg. citations per publication [2000-2006] R % Faculty with Grant [2005-06 AY] R % Interdisciplinary Faculty [2005-06 AY] % non-Asian Minority Faculty [2005-06 AY] D % Female Faculty [2005-06 AY] D Awards/Faculty Member [2001-2006] R 10 #12;10/21/2010 6 NRC Methodology

  14. NRC TLD Direct Radiation Monitoring Network. Progress report, October--December 1996

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1997-03-01T23:59:59.000Z

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1996. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs.

  15. NRC TLD Direct Radiation Monitoring Network progress report, October--December 1994. Volume 14, No. 4

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1995-03-01T23:59:59.000Z

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1994. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  16. Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 2, Investigators`s Manual

    SciTech Connect (OSTI)

    Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

    1993-10-01T23:59:59.000Z

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause event at nuclear power plants. This document, Volume II, is a field manual for use by investigators when performing event investigations. Volume II includes the HPIP Procedure, the HPIP Modules, and Appendices that provide extensive documentation of each investigation technique.

  17. U.S. DOE Approach to Address U.S. NRC Key Technical Issues for a License Application

    SciTech Connect (OSTI)

    Ziegler, J. D.; Gunter, T. C.; Gamble, R. P.; Bradbury, R. B.

    2003-02-25T23:59:59.000Z

    Interactions between the U.S. Department of Energy (DOE) staff and the U.S. Nuclear Regulatory Commission (NRC) staff prior to submittal of a license application (LA) for NRC review are focused on resolution of issues relevant to licensing a geologic repository at the Yucca Mountain site. These interactions take place in meetings that are open to the public, the State of Nevada, affected units of local government, and other interested parties. Consistent with a 1992 agreement between the DOE and NRC, resolution of an issue at the staff level can be achieved during the pre-licensing period when the NRC staff has no further questions or comments regarding how the DOE is addressing that issue. In no case does such resolution at the NRC staff level preclude an issue being raised during the licensing proceedings by the NRC or another party to the proceedings. Beginning in 1996, interactions between the DOE and NRC began to focus significant attention on the nine topical areas, called Key Technical Issues (KTIs), that the NRC staff considers to be important in evaluating the post-closure performance of a Yucca Mountain repository. DOENRC meetings to discuss each KTI and achieve technical agreement on the information needed to resolve the issues were held between August 2000 and September 2001. As a result of these meetings, 293 agreements were reached regarding information to be developed by the DOE to supplement the basis for NRC review of the initial LA.* As of April 23, 2003, 77 of these agreements are considered by the NRC to be complete based on information provided by the DOE.

  18. Twenty-third DOE/NRC nuclear air cleaning and treatment conference

    SciTech Connect (OSTI)

    Bellamy, R.R.; Hayes, J.J.; First, M.W.

    1995-01-01T23:59:59.000Z

    The Twenty-Third Department of Energy/Nuclear Regulatory Commission (DOE/NRC) nuclear Air-Cleaning and Treatment Conference was held July 25-28, 1994, in Buffalo, New York. The conference was also sponsored by the Harvard Air-Cleaning Laboratory and the Internation Society of Nuclear Air Treatment Technologies, a nonprofit organization founded to promote technology transfer in the nuclear air-cleaning and treatment area. A total of 192 air-cleaning specialists attended the conference. The United States and 11 foreign countries were represented. The specialists are affiliated with all aspects of the nuclear industry, including government agencies, educational institutions, utilities, architect-engineers, equipment suppliers, and consultants. The high level of international interests is evident from the 40% of papers sponsored by foreign interests. More than 20% of the attendees as well as several members of the Program Committee were from outside the United States. Major topics discussed at this conference included nuclear air-cleaning codes and standards, waste disposal, particulate filter developments (including testing and performance under stress and after aging), sampling and monitoring of process and effluent streams, off-gasses from fuel reprocessing, adsorbents and adsorption, accident control and analysis, and revised source terms for power-plant accidents. A highlight of the conference concerned operations a at the DOE facility at West Valley, New York, where construction is under way to solidify radioactive waste. A recurrent theme throughout the sessions was that, in spite of the large number of guidance documents available in the form of regulations, codes, standards, and directives, multiple difficulties arise when all are invoked simultaneously. Gas processing needs, rather than controls for civilian power plants, will provide the principal challenge during the next decade for the air-cleaning specialists of the world. 15 refs.

  19. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    SciTech Connect (OSTI)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09T23:59:59.000Z

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  20. Accident Conditions versus Regulatory Test for NRC-Approved UF6 Packages

    SciTech Connect (OSTI)

    MILLS, G. SCOTT; AMMERMAN, DOUGLAS J.; LOPEZ, CARLOS

    2003-01-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) approves new package designs for shipping fissile quantities of UF{sub 6}. Currently there are three packages approved by the NRC for domestic shipments of fissile quantities of UF{sub 6}: NCI-21PF-1; UX-30; and ESP30X. For approval by the NRC, packages must be subjected to a sequence of physical tests to simulate transportation accident conditions as described in 10 CFR Part 71. The primary objective of this project was to relate the conditions experienced by these packages in the tests described in 10 CFR Part 71 to conditions potentially encountered in actual accidents and to estimate the probabilities of such accidents. Comparison of the effects of actual accident conditions to 10 CFR Part 71 tests was achieved by means of computer modeling of structural effects on the packages due to impacts with actual surfaces, and thermal effects resulting from test and other fire scenarios. In addition, the likelihood of encountering bodies of water or sufficient rainfall to cause complete or partial immersion during transport over representative truck routes was assessed. Modeled effects, and their associated probabilities, were combined with existing event-tree data, plus accident rates and other characteristics gathered from representative routes, to derive generalized probabilities of encountering accident conditions comparable to the 10 CFR Part 71 conditions. This analysis suggests that the regulatory conditions are unlikely to be exceeded in real accidents, i.e. the likelihood of UF{sub 6} being dispersed as a result of accident impact or fire is small. Moreover, given that an accident has occurred, exposure to water by fire-fighting, heavy rain or submersion in a body of water is even less probable by factors ranging from 0.5 to 8E-6.

  1. Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

    1993-12-01T23:59:59.000Z

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

  2. Review of nuclear power plant offsite power source reliability and related recommended changes to the NRC rules and regulations

    SciTech Connect (OSTI)

    Battle, R.E.; Clark, F.H.; Reddoch, T.W.

    1980-05-01T23:59:59.000Z

    The NRC has stated its concern about the reliability of the offsite power system as the preferred emergency source and about the possible damage to a pressurized water reactor (PWR) that could result from a rapid decay of power grid frequency. ORNL contracted with NRC to provide technical assistance to establish criteria that can be used to evaluate the offsite power system for the licensing of a nuclear power plant. The results of many of the studies for this contract are recommendations to assess and control the power grid during operation. This is because most of the NRC regulations pertaining to the offsite power system are related to the design of the power grid, and we believe that additional emphasis on monitoring the power grid operation will improve the reliability of the nuclear plant offsite power supply. 46 refs., 10 figs.

  3. PHYSICAL FIDELITY CONSIDERATIONS FOR NRC ADVANCED REACTOR CONTROL ROOM TRAINING SIMULATORS USED FOR INSPECTOR/EXAMINER TRAINING

    SciTech Connect (OSTI)

    Branch, Kristi M.; Mitchell, Mark R.; Miller, Mark; Cochrum, Steven

    2010-11-07T23:59:59.000Z

    This paper describes research into the physical fidelity requirements of control room simulators to train U.S. Nuclear Regulatory Commission (NRC) staff for their duties as inspectors and license examiners for next-generation nuclear power plants. The control rooms of these power plants are expected to utilize digital instrumentation and controls to a much greater extent than do current plants. The NRC is assessing training facility needs, particularly for control room simulators, which play a central role in NRC training. Simulator fidelity affects both training effectiveness and cost. Research has shown high simulation fidelity sometimes positively affects transfer to the operational environment but sometimes makes no significant difference or actually impedes learning. The conditions in which these different effects occur are often unclear, especially for regulators (as opposed to operators) about whom research is particularly sparse. This project developed an inventory of the tasks and knowledges, skills, and abilities that NRC regulators need to fulfill job duties and used expert panels to characterize the inventory items by type and level of cognitive/behavioral capability needed, difficulty to perform, importance to safety, frequency of performance, and the importance of simulator training for learning these capabilities. A survey of current NRC staff provides information about the physical fidelity of the simulator on which the student trained to the control room to which the student was assigned and the effect lack of fidelity had on learning and job performance. The study concludes that a high level of physical fidelity is not required for effective training of NRC staff.

  4. Structure/piping sensitivity studies for the US NRC Seismic Safety Margins Research Program. [PWR; BWR

    SciTech Connect (OSTI)

    Shieh, L.C.; O'Connell, W.J.; Johnson, J.J.

    1983-01-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a NRC-funded, multi-year program conducted by Lawrence Livermore National Laboratory (LLNL). One of the goals of the program is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis design process and explicitly includes the uncertainties inherent in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. In Phase I, a probabilistic computational procedure was developed for the seismic safety assessment. In Phase II, sensitivity studies were performed, codes and models were improved, and analysis of the Zion plant was completed.

  5. Comparison of the NRC and the IAEA regulatory documents in the area of nuclear fuel systems

    SciTech Connect (OSTI)

    El-Adham, K.; Shinaishin, M.A.

    1991-04-01T23:59:59.000Z

    A main objective of this work was to identify the safety requirements in the area of fuel system design and performance from both the International Atomic Energy Agency (IAEA) and U.S. Nuclear Regulatory Commission (NRC) points of view. The study covered requirements during normal plant operation as well as during accident conditions. This study revealed that, although none of the factors to be considered for fuel safety were neglected in the IAEA regulatory documents, these documents are not complete in themselves, particularly because they lack quantitative guidelines and specific industrial standards. Although generality makes the IAEA requirements adaptable to many countries, on the other hand, it makes their applicability constrained by the availability of highly qualified and experienced personnel who can translate the qualitative requirements given in these documents into actual engineering solutions. 20 refs.

  6. CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

    SciTech Connect (OSTI)

    Charak, I.; Kier, P.H. [Argonne National Lab., IL (United States)

    1995-04-01T23:59:59.000Z

    Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule ({section}50.62); (2) station blackout ({section}50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term ({section}50.34(f) and {section}100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements ({section}50.55a, etc); (6) ECCS acceptance criteria ({section}50.46)(b); (7) combustible gas control ({section}50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle ({section}51.51); and (11) (standards {section}50.55a).

  7. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1996-03-01T23:59:59.000Z

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  8. Technical description of the NRC long-term whole-rod and crud performance test

    SciTech Connect (OSTI)

    Einziger, R.E.; Fish, R.L.; Knecht, R.L.

    1982-09-01T23:59:59.000Z

    Westinghouse Hanford Company (WHC) and EG and G-Idaho are jointly conducting a long-term, low-temperature, spent-fuel, whole rod and crud behavior test to provide the Nuclear Regulatory Commission (NRC) with information to assist in the licensing of light water reactor (LWR) spent-fuel, dry storage facilities. Readily available fuel rods from an H.B. Robinson Unit 2 (PWR) fuel assembly and a Peach Bottom-II (BWR) fuel assembly were selected for use in the 50-month test. Both intact and defected rods will be tested in inert and oxidizing atmospheres. A 230/sup 0/C test temperature was selected for the first 10-month run. Both nondestructive and destructive examinations are planned to characterize the fuel rod behavior during the 5-y test. Four interim examinations and a final examination will be conducted. Crud spallation behavior will be investigated by sampling the crud particulate from the test capsules at each of the four interim examinations and at the end of the test. The background to whole rod testing, description of rod breach mechanisms, and a detailed description of the test are presented in this document.

  9. Modeling prismatic HTGRs with U.S. N.R.C advanced gas reactor evaluator (AGREE)

    SciTech Connect (OSTI)

    Seker, V.; Drzewiecki, T.; Downar, T. [Nuclear Engineering and Radiological Sciences, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 (United States); Kelly, J. M. [US Nuclear Regulatory Commission, Washington, DC (United States)

    2012-07-01T23:59:59.000Z

    A core fluids and heat transfer model has been developed for the prismatic high temperature gas reactor in support of the US NRC Next Generation Nuclear Plant (NGNP) evaluation model. The core fluids modeling relies on a subchannel approach in which the primary coolant flow path through the core region and vertical in-core and ex-core gaps can be modeled as individual subchannels. These subchannels are connected together to represent a three dimensional reactor. An initial validation calculation for the core fluids model has been performed using data available in literature for bypass flow. The predicted bypass flow was within 2.6% of the value reported in the literature. The core level heat transfer model is based on a triangular finite volume method, where the base triangle is one sixth of the prismatic block. In order to improve the spatial accuracy at this level, a triangular refinement method was also implemented. The fuel compact temperature is calculated by a cylindrical conduction model which is implicitly coupled to the triangular core level model. The preliminary verification of the model was performed by comparing AGREE to a finite element code COMSOL by analyzing the MHTGR core heat transfer. Further verification and validation is currently an ongoing effort. (authors)

  10. Recent Updates to NRC Fuel Performance Codes and Plans for Future Improvements

    SciTech Connect (OSTI)

    Geelhood, Kenneth J.

    2011-12-31T23:59:59.000Z

    FRAPCON-3.4a and FRAPTRAN 1.4 are the most recent versions of the U.S. Nuclear Regulatory Commission (NRC) steady-state and transient fuel performance codes, respectively. These codes have been assessed against separate effects data and integral assessment data and have been determined to provide a best estimate calculation of fuel performance. Recent updates included in FRAPCON-3.4a include updated material properties models, models for new fuel and cladding types, cladding finite element analysis capability, and capability to perform uncertainty analyses and calculate upper tolerance limits for important outputs. Recent updates included in FRAPTRAN 1.4 include: material properties models that are consistent with FRAPCON-3.4a, cladding failure models that are applicable for loss-of coolant-accident and reactivity initiated accident modeling, and updated heat transfer models. This paper briefly describes these code updates and data assessments, highlighting the particularly important improvements and data assessments. This paper also discusses areas of improvements that will be addressed in upcoming code versions.

  11. LBB evaluation for a typical Japanese PWR primary loop by using the US NRC approved methods

    SciTech Connect (OSTI)

    Swamy, S.A.; Bhowmick, D.C.; Prager, D.E. [Westinghouse Nuclear Technology Division, Pittsburgh, PA (United States)

    1997-04-01T23:59:59.000Z

    The regulatory requirements for postulated pipe ruptures have changed significantly since the first nuclear plants were designed. The Leak-Before-Break (LBB) methodology is now accepted as a technically justifiable approach for eliminating postulation of double-ended guillotine breaks (DEGB) in high energy piping systems. The previous pipe rupture design requirements for nuclear power plant applications are responsible for all the numerous and massive pipe whip restraints and jet shields installed for each plant. This results in significant plant congestion, increased labor costs and radiation dosage for normal maintenance and inspection. Also the restraints increase the probability of interference between the piping and supporting structures during plant heatup, thereby potentially impacting overall plant reliability. The LBB approach to eliminate postulating ruptures in high energy piping systems is a significant improvement to former regulatory methodologies, and therefore, the LBB approach to design is gaining worldwide acceptance. However, the methods and criteria for LBB evaluation depend upon the policy of individual country and significant effort continues towards accomplishing uniformity on a global basis. In this paper the historical development of the U.S. LBB criteria will be traced and the results of an LBB evaluation for a typical Japanese PWR primary loop applying U.S. NRC approved methods will be presented. In addition, another approach using the Japanese LBB criteria will be shown and compared with the U.S. criteria. The comparison will be highlighted in this paper with detailed discussion.

  12. Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland

    SciTech Connect (OSTI)

    Wheeler, Timothy A.; Whitehead, Donnie W.; Lois, Erasmia

    1999-07-01T23:59:59.000Z

    This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations.

  13. Proceedings of the 21st DOE/NRC nuclear air cleaning conference; Volume 2, Sessions 9--16

    SciTech Connect (OSTI)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01T23:59:59.000Z

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers. (MHB)

  14. Greater-than-Class C low-level radioactive waste characterization. Appendix E-5: Impact of the 1993 NRC draft Branch Technical Position on concentration averaging of greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Tuite, P.; Tuite, K.; Harris, G. [Waste Management Group, Inc., Peekskill, NY (United States)

    1994-09-01T23:59:59.000Z

    This report evaluates the effects of concentration averaging practices on the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) generated by the nuclear utility industry and sealed sources. Using estimates of the number of waste components that individually exceed Class C limits, this report calculates the proportion that would be classified as GTCC LLW after applying concentration averaging; this proportion is called the concentration averaging factor. The report uses the guidance outlined in the 1993 Nuclear Regulatory Commission (NRC) draft Branch Technical Position on concentration averaging, as well as waste disposal experience at nuclear utilities, to calculate the concentration averaging factors for nuclear utility wastes. The report uses the 1993 NRC draft Branch Technical Position and the criteria from the Barnwell, South Carolina, LLW disposal site to calculate concentration averaging factors for sealed sources. The report addresses three waste groups: activated metals from light water reactors, process wastes from light-water reactors, and sealed sources. For each waste group, three concentration averaging cases are considered: high, base, and low. The base case, which is the most likely case to occur, assumes using the specific guidance given in the 1993 NRC draft Branch Technical Position on concentration averaging. To project future GTCC LLW generation, each waste category is assigned a concentration averaging factor for the high, base, and low cases.

  15. NRC Consultation and Monitoring at the Savannah River Site: Focusing Reviews of Two Different Disposal Actions - 12181

    SciTech Connect (OSTI)

    Ridge, A. Christianne; Barr, Cynthia S.; Pinkston, Karen E.; Parks, Leah S.; Grossman, Christopher J.; Alexander, George W. [U.S. Nuclear Regulatory Commission (United States)

    2012-07-01T23:59:59.000Z

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms, and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to radionuclide release from the waste. Because the waste inventory and concentration at both sites is sufficient to generate unacceptable doses to an off-site member of the public or inadvertent intruder in the absence of engineered barriers, the NRC staff review focused on the engineering features DOE plans to put in place to limit radionuclide release. At the FTF, DOE expects that peak doses are delayed beyond a 10,000 year performance period by a combination of (1) the flow-limiting effect of the steel tank liner and (2) chemical conditions created by the stabilizing grout overlying the waste that limit the solubility of key radionuclides for tens of thousands of years. At the SDF, DOE expects that flow will be significantly limited by water shedding along the closure cap lower drainage layer and that radionuclide release will be further limited by radionuclide precipitation or sorption within the high pH, chemically reducing conditions created within the saltstone waste form. Because the performance of both facilities depends on the performance of engineered barriers for thousands of years, the reviews included a detailed evaluation of the expected long-term behavior of these barriers. As previously discussed, NRC staff reviews of DOE waste determinations during consultation are designed to evaluate the three NDAA criteria, whereas the review of an updated PA during monitoring only addresses whether the NRC staff has reasonable assurance that the planned disposal action will meet the performance objectives of 10 CFR Part 61. The NRC staff review of the Waste Determination for the FTF did not include conclusions about whether the planned disposal of residual waste at the FTF would meet the NDAA criteria because of the substantial uncertainties in the degree of waste removal DOE would achieve and other technical uncertainties. The main product of the NRC staff review of the planned FTF disposal action is the recommendation that DOE should conduct waste release experiments to increase support for key modeling assumptions related to: (1) the evolution of pH and Eh in the grouted tank syst

  16. EPRI/NRC-RES fire PRA guide for nuclear power facilities. Volume 1, summary and overview.

    SciTech Connect (OSTI)

    Not Available

    2004-09-01T23:59:59.000Z

    This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. The methods have been developed under the Fire Risk Re-quantification Study. This study was conducted as a joint activity between EPRI and the U. S. NRC Office of Nuclear Regulatory Research (RES) under the terms of an EPRI/RES Memorandum of Understanding [RS.1] and an accompanying Fire Research Addendum [RS.2]. Industry participants supported demonstration analyses and provided peer review of this methodology. The documented methods are intended to support future applications of Fire PRA, including risk-informed regulatory applications. The documented method reflects state-of-the-art fire risk analysis approaches. The primary objective of the Fire Risk Study was to consolidate recent research and development activities into a single state-of-the-art fire PRA analysis methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. Methodological debates were resolved through a consensus process between experts representing both EPRI and RES. The consensus process included a provision whereby each major party (EPRI and RES) could maintain differing technical positions if consensus could not be reached. No cases were encountered where this provision was invoked. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods. In several areas, this project has, in fact, developed new methods and approaches. Such advances typically relate to areas of past methodological debate.

  17. SSI sensitivity studies and model improvements for the US NRC Seismic Safety Margins Research Program. Rev. 1

    SciTech Connect (OSTI)

    Johnson, J.J.; Maslenikov, O.R.; Benda, B.J.

    1984-10-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a US NRC-funded program conducted by Lawrence Livermore National Laboratory. Its goal is to develop a complete fully coupled analysis procedure for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. In Phase II of the SSMRP, the methodology was applied to the Zion nuclear power plant. Three topics in the SSI analysis of Zion were investigated and reported here - flexible foundation modeling, structure-to-structure interaction, and basemat uplift. The results of these investigations were incorporated in the SSMRP seismic risk analysis. 14 references, 51 figures, 13 tables.

  18. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    SciTech Connect (OSTI)

    Not Available

    1992-08-01T23:59:59.000Z

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

  19. THE NRC HAS ISSUED Ati ACTION PLAN FOR CLEANUP OF 46 SfTES that;;ece

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7 AugustAFRICAN3uj: ;;I : T' j-jE: iLie'Al ...NRC

  20. US NRC-Sponsored Research on Stress Corrosion Cracking Susceptibility of Dry Storage Canister Materials in Marine Environments - 13344

    SciTech Connect (OSTI)

    Oberson, Greg; Dunn, Darrell [U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington DC, 20555 (United States)] [U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington DC, 20555 (United States); Mintz, Todd; He, Xihua; Pabalan, Roberto; Miller, Larry [Center for Nuclear Waste Regulatory Analyses, 6220 Culebra Rd, San Antonio TX, 78238 (United States)] [Center for Nuclear Waste Regulatory Analyses, 6220 Culebra Rd, San Antonio TX, 78238 (United States)

    2013-07-01T23:59:59.000Z

    At a number of locations in the U.S., spent nuclear fuel (SNF) is maintained at independent spent fuel storage installations (ISFSIs). These ISFSIs, which include operating and decommissioned reactor sites, Department of Energy facilities in Idaho, and others, are licensed by the U.S. Nuclear Regulatory Commission (NRC) under Title 10 of the Code of Federal Regulations, Part 72. The SNF is stored in dry cask storage systems, which most commonly consist of a welded austenitic stainless steel canister within a larger concrete vault or overpack vented to the external atmosphere to allow airflow for cooling. Some ISFSIs are located in marine environments where there may be high concentrations of airborne chloride salts. If salts were to deposit on the canisters via the external vents, a chloride-rich brine could form by deliquescence. Austenitic stainless steels are susceptible to chloride-induced stress corrosion cracking (SCC), particularly in the presence of residual tensile stresses from welding or other fabrication processes. SCC could allow helium to leak out of a canister if the wall is breached or otherwise compromise its structural integrity. There is currently limited understanding of the conditions that will affect the SCC susceptibility of austenitic stainless steel exposed to marine salts. NRC previously conducted a scoping study of this phenomenon, reported in NUREG/CR-7030 in 2010. Given apparent conservatisms and limitations in this study, NRC has sponsored a follow-on research program to more systematically investigate various factors that may affect SCC including temperature, humidity, salt concentration, and stress level. The activities within this research program include: (1) measurement of relative humidity (RH) for deliquescence of sea salt, (2) SCC testing within the range of natural absolute humidity, (3) SCC testing at elevated temperatures, (4) SCC testing at high humidity conditions, and (5) SCC testing with various applied stresses. Results to date indicate that the deliquescence RH for sea salt is close to that of MgCl{sub 2} pure salt. SCC is observed between 35 and 80 deg. C when the ambient (RH) is close to or higher than this level, even for a low surface salt concentration. (authors)

  1. Nuclear Crisis Communications: The Plan Worked. A Critique of NRC Communications in the Fukushima Daiichi Reactor Crisis - 12073

    SciTech Connect (OSTI)

    Brenner, Eliot; Harrington, Holly; Schmidt, Rebecca [U.S. Nuclear Regulatory Commission, Rockville, MD 20852 (United States)

    2012-07-01T23:59:59.000Z

    'Call the AV-Photo folks and get someone in here to shoot b-roll. We'll never be able to accommodate the network cameras and the only way I can get this to the media is to produce it ourselves'. Eliot Brenner, Director NRC Office of Public Affairs, March 12, 2011. For the past four years we have been speaking to audiences at Waste Management about communications issues. Last year, though we were kept from attending because of the federal budget crisis, our surrogates described to you the lessons the nuclear industry should draw from the BP Gulf oil spill crisis. Those remarks were delivered 11 days before the Fukushima Daiichi tragedy became the nuclear landmark of a generation - an industry changing event with worldwide ramifications, both in science and regulation and in communications. Eliot Brenner cut his teeth on crisis communication in the aviation industry where tragedy unfolds rapidly. He has been a speech-writer to three cabinet secretaries, spokesman for the Federal Aviation Administration and now spokesman for the Nuclear Regulatory Commission since 2004. Holly Harrington manages the NRC crisis response program and has 26 years federal public affairs experience, including eight years at the Federal Emergency Management Agency. Her crisis experience includes the 1989 Loma Prieta earthquake, numerous hurricanes and floods, Sept 11, and, now Fukushima Daiichi. Rebecca Schmidt is a veteran government relations professional whose decades in Washington include service with the House Armed Services Committee, the House Budget Committee and the Secretary of Defense. Collectively, the Offices of Public Affairs and Congressional Affairs conducted the largest outreach for the agency since Three Mile Island. We worked with the basic rule, described to Waste Management last year just 11 days before Fukushima - communicate early, often and clearly. The response - while not without its problems and lessons - went as smoothly as a chaotic event like Fukushima could go. That was due in large measure to the fact that the NRC has a well-tested system of responding to nuclear emergencies, and we followed our plan. (authors)

  2. NRC safety research in support of regulation. Volume 8, FY 1993

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This report, the ninth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission`s rules, regulatory guides, or other guidance.

  3. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    SciTech Connect (OSTI)

    Tom Elicson; Bentley Harwood; Richard Yorg; Heather Lucek; Jim Bouchard; Ray Jukkola; Duan Phan

    2011-03-01T23:59:59.000Z

    The application NUREG/CR-6850 EPRI/NRC fire PRA methodology to DOE facility presented several challenges. This paper documents the process and discusses several insights gained during development of the fire PRA. A brief review of the tasks performed is provided with particular focus on the following: • Tasks 5 and 14: Fire-induced risk model and fire risk quantification. A key lesson learned was to begin model development and quantification as early as possible in the project using screening values and simplified modeling if necessary. • Tasks 3 and 9: Fire PRA cable selection and detailed circuit failure analysis. In retrospect, it would have been beneficial to perform the model development and quantification in 2 phases with detailed circuit analysis applied during phase 2. This would have allowed for development of a robust model and quantification earlier in the project and would have provided insights into where to focus the detailed circuit analysis efforts. • Tasks 8 and 11: Scoping fire modeling and detailed fire modeling. More focus should be placed on detailed fire modeling and less focus on scoping fire modeling. This was the approach taken for the fire PRA. • Task 14: Fire risk quantification. Typically, multiple safe shutdown (SSD) components fail during a given fire scenario. Therefore dependent failure analysis is critical to obtaining a meaningful fire risk quantification. Dependent failure analysis for the fire PRA presented several challenges which will be discussed in the full paper.

  4. PRA In Design: Increasing Confidence in Pre-operational Assessments of Risks (Results of a Joint NASA/ NRC Workshop)

    SciTech Connect (OSTI)

    Robert Youngblood

    2010-06-01T23:59:59.000Z

    In late 2009, the National Aeronautics and Space Administration (NASA) and the U.S. Nuclear Regulatory Commission (NRC) jointly organized a workshop to discuss technical issues associated with application of risk assessments to early phases of system design. The workshop, which was coordinated by the Idaho National Laboratory, involved invited presentations from a number of PRA experts in the aerospace and nuclear fields and subsequent discussion to address the following questions: (a) What technical issues limit decision-makers’ confidence in PRA results, especially at a preoperational phase of the system life cycle? (b) What is being done to address these issues? (c) What more can be done? The workshop resulted in participant observations and suggestions on several technical issues, including the pursuit of non-traditional approaches to risk assessment and the verification and validation of risk models. The workshop participants also identified several important non-technical issues, including risk communication with decision makers, and the integration of PRA into the overall design process.

  5. NRC Form 741

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i- DNANuclear SecurityA

  6. Final Environmental Impact Statement for the construction and operation of Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3-70). Volume 2, Public comments and NRC response

    SciTech Connect (OSTI)

    Zeitoun, A. [Science Applications International Corp., Germantown, MD (United States)

    1994-08-01T23:59:59.000Z

    The Final Environmental Impact Statement (FEIS) (Volume 1), was prepared by the Nuclear Regulatory Commission (NRC) in accordance with regulation 10 CFR Part 51, which implements the National Environmental Policy Act (NEPA), to assess the potential environmental impacts for licensing the construction and operation of a proposed gaseous centrifuge enrichment facility to be built in Claiborne Parish, Louisiana by Louisiana Energy Services, L.P. (LES). The proposed facility would have a production capacity of about 866 metric tons annually of up to 5 weight percent enriched UF{sub 6}, using a proven centrifuge technology. Included in the assessment are co on, both normal operations and potential accidents (internal and external events), and the eventual decontamination and decommissioning of the site. In order to help assure that releases from the operation of the facility and potential impacts on the public are as low as reasonably achievable, an environmental monitoring program was developed by LES to detect significant changes in the background levels of uranium around the site. Other issues addressed include the purpose and need for the facility, the alternatives to the proposed action, potential disposition of the tails, the site selection process, and environmental justice. The NRC staff concludes that the facility can be constructed and operated with small and acceptable impacts on the public and the environment, and proposes to issue a license to the applicant, Louisiana Energy Services, to authorize construction and operation of the proposed facility. The letters in this Appendix have been divided into three sections. Section One contains letters to which the NRC responded by addressing specific comments. Section Two contains the letters that concerned the communities of Forest Grove and Center Springs. Section Three is composed of letters that required no response. These letters were generally in support of the facility.

  7. NRC Job Code V6060: Extended in-situ and real time monitoring. Task 4: Detection and monitoring of leaks at nuclear power plants external to structures

    SciTech Connect (OSTI)

    Sheen, S. H. (Nuclear Engineering Division)

    2012-08-01T23:59:59.000Z

    In support of Task 4 of the NRC study on compliance with 10 CFR part 20.1406, minimization of contamination, Argonne National Laboratory (ANL) conducted a one-year scoping study, in concert with a parallel study performed by NRC/NRR staff, on monitoring for leaks at nuclear power plants (NPPs) external to structures. The objective of this task-4 study is to identify and assess those sensors and monitoring techniques for early detection of abnormal radioactive releases from the engineered facility structures, systems and components (SSCs) to the surrounding underground environment in existing NPPs and planned new reactors. As such, methods of interest include: (1) detection of anomalous water content of soils surrounding SSCs, (2) radionuclides contained in the leaking water, and (3) secondary signals such as temperature. ANL work scope includes mainly to (1) identify, in concert with the nuclear industry, the sensors and techniques that have most promise to detect radionuclides and/or associated chemical releases from SSCs of existing NPPs and (2) review and provide comments on the results of the NRC/NRR staff scoping study to identify candidate technologies. This report constitutes the ANL deliverable of the task-4 study. It covers a survey of sensor technologies and leak detection methods currently applied to leak monitoring at NPPs. The survey also provides a technology evaluation that identifies their strength and deficiency based on their detection speed, sensitivity, range and reliability. Emerging advanced technologies that are potentially capable of locating releases, identifying the radionuclides, and estimating their concentrations and distributions are also included in the report along with suggestions of required further research and development.

  8. Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

    SciTech Connect (OSTI)

    Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

    1982-02-01T23:59:59.000Z

    In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

  9. Validation of the U.S. NRC coupled code system TRITON/TRACE/PARCS with the special power excursion reactor test III (SPERT III)

    SciTech Connect (OSTI)

    Wang, R. C.; Xu, Y.; Downar, T. [Dept. of Nuclear Engineering and Radiological Sciences, Univ. of Michigan, Ann Arbor, MI 48104 (United States); Hudson, N. [RES Div., U.S. NRC, Rockville, MD (United States)

    2012-07-01T23:59:59.000Z

    The Special Power Excursion Reactor Test III (SPERT III) was a series of reactivity insertion experiments conducted in the 1950's. This paper describes the validation of the U.S. NRC Coupled Code system TRITON/PARCS/TRACE to simulate reactivity insertion accidents (RIA) by using several of the SPERT III tests. The work here used the SPERT III E-core configuration tests in which the RIA was initiated by ejecting a control rod. The resulting super-prompt reactivity excursion and negative reactivity feedback produced the familiar bell shaped power increase and decrease. The energy deposition during such a power peak has important safety consequences and provides validation basis for core coupled multi-physics codes. The transients of five separate tests are used to benchmark the PARCS/TRACE coupled code. The models were thoroughly validated using the original experiment documentation. (authors)

  10. Guide to NRC reporting and recordkeeping requirements. Compiled from requirements in Title 10 of the U.S. Code of Federal Regulations as codified on December 31, 1993; Revision 1

    SciTech Connect (OSTI)

    Collins, M.; Shelton, B.

    1994-07-01T23:59:59.000Z

    This compilation includes in the first two sections the reporting and recordkeeping requirements applicable to US Nuclear Regulatory Commission (NRC) licensees and applicants and to members of the public. It includes those requirements codified in Title 10 of the code of Federal Regulations, Chapter 1, on December 31, 1993. It also includes, in a separate section, any of those requirements that were superseded or discontinued between January 1992 and December 1993. Finally, the appendix lists mailing and delivery addresses for NRC Headquarters and Regional Offices mentioned in the compilation. The Office of Information Resources Management staff compiled this listing of reporting and recordkeeping requirements to briefly describe each in a single document primarily to help licensees readily identify the requirements. The compilation is not a substitute for the regulations, and is not intended to impose any new requirements or technical positions. It is part of NRC`s continuing efforts to comply with the Paperwork Reduction Act of 1980 and the Office of Management and Budget regulations that mandate effective and efficient Federal information resources management programs.

  11. NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

  12. Analysis of a CRDM Nozzle Break LOCA Without Scram Using the U.S. NRC Coupled Code TRAC-M/PARCS

    SciTech Connect (OSTI)

    Cuadra, A.; Ragusa, J.; Downar, T. [Purdue University, West Lafayette, IN 47907 (United States); Ivanov, K. [The Pennsylvania State University, University Park, PA 16802 (United States)

    2002-07-01T23:59:59.000Z

    Recently, through-wall circumferential cracks in several control rod drive mechanism (CRDM) nozzle penetrations were detected at the Oconee-3 nuclear power plant. The presence of these cracks was seen as a potential precursor to a small break loss of coolant accident. In order to assess the impact of a postulated failure of a CRDM housing, analyses were performed using the U.S. NRC coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. Although deemed highly unlikely, it was assumed that no control rods inserted in order to bound any possible reactivity transient associated with the break. The thermal-hydraulic model used to perform the study is based on an existing model of Oconee, built for PTS analysis, which models the whole plant and some of its control systems. A refined vessel model based on a TMI model was used to increase the resolution of the results and facilitate coupling to PARCS. All relevant ECCS systems were modeled and the control system allowed for, in addition to automatic actions, some assumed operator intervention. In particular, HPI throttling was modeled to maintain the hot leg subcooled at 42 +/- 7 K, and prevent an excessive amount of cold water from being injected into the system. A spatial kinetics analysis of this event was necessary because of the wide range of core conditions which occurred during the transient, from hot full power operation conditions to the cold zero power shutdown state. Analysis of the event with point kinetics and 'best estimate' reactivity coefficients resulted in significant miss-prediction of the core power response. Conversely, the three-dimensional kinetics solution with cross section data generated over the entire range of the event led to a more accurate calculation of the power response and the overall analysis of the system transient response. This paper will describe the analysis of the control rod drive nozzle break event without scram using TRAC-M/PARCS. (authors)

  13. NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

  14. Public Comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Appendices

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This volume contains several appendices. Appendix A contains the list of individuals and organizations providing comments at various stages of the rulemaking process. The names of commenters at the public meetings are listed in the order that they spoke at the meeting; those who submitted written comments are listed by docket number. Appendix B contains the summaries of comments made. Each comment summary is identified by a unique comment number. Appendix C presents the concerns and NRC staff responses. Each concern embodies one or more comments on similar or related issues. The associated comment numbers are referenced for each concern. The concerns are organized by topic areas. A three-letter identifier for the topic, followed by a number, is assigned to each concern.

  15. Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

    SciTech Connect (OSTI)

    Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Industrial and Medical Nuclear Safety; Tingle, W. [Dept. of Environment, Health, and Natural Resources, Raleigh, NC (United States). Div. of Radiation Protection

    1997-05-01T23:59:59.000Z

    As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ``Applications for the Use of Sealed Sources in Portable Gauging Devices,`` and in NMSs Policy and guidance Directive 2-07, ``Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.`` This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications.

  16. Scenario guidance handbook for emergency-preparedness exercises at nuclear facilities

    SciTech Connect (OSTI)

    Laughlin, G.J.; Martin, G.F.; Desrosiers, A.E.

    1983-01-01T23:59:59.000Z

    As part of the Emergency Preparedness Implementation Appraisal Program conducted by the Nuclear Regulatory Commission (NRC) with the technical assistance of the Pacific Northwest Laboratory (PNL), emergency preparedness exercises are observed on an annual basis at all licensed reactor facilities. One of the significant findings to arise from these observations was that a large number of the commonly observed problems originated in the design of the scenarios used as a basis for each exercise. In an effort to help eliminate some of these problems a scenario guidance handbook has been generated by PNL for the NRC to assist nuclear power plant licensees in developing scenarios for emergency preparedness exercises.

  17. Codes and standards and other guidance cited in regulatory documents. Revision 1

    SciTech Connect (OSTI)

    Ankrum, A.; Nickolaus, J.; Vinther, R.; Maguire-Moffitt, N.; Hammer, J.; Sherfey, L.; Warner, R. [Pacific Northwest Lab., Richland, WA (United States)

    1994-08-01T23:59:59.000Z

    As part of the US Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program, Pacific Northwest Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. In addition to updating previous information, Revision 1 adds citations from the NRC Inspection Manual and the Improved Standard Technical Specifications. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Generic Letters, Policy Statements, Regulatory Guides, and the Standard Review Plan (NUREG-0800).

  18. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-11-07T23:59:59.000Z

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

  19. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2008-01-12T23:59:59.000Z

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

  20. RESEARCH CENTRES GRID National Research Centres (NRC)

    E-Print Network [OSTI]

    F2 Battery House Waite Sports Ground (Fullarton Rd) C6 Waite Oval EATING PLACES Lirra Lirra Café E2 Arboretum (Inset) B6 BBQ Area - Gum Oval C2 BBQ Area - Waterhole D6 Garden of Discovery F1 McLeod House Union (AUU) Office / Shop E2 McLeod House, G External Studies Office D2 Charles Hawker, G Student

  1. ARM - Campaign Instrument - nrc-convair580

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492air Comments? We would love to hear from you!jpl Comments? We would love togovInstrumentsnrc-convair580

  2. NRC Licensing Strategy Development for the NGNP

    SciTech Connect (OSTI)

    Mark R. Holbrook; Trevor Cook

    2008-09-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) project will provide the basis for commercialization of a new generation of advanced nuclear plants that utilize hightemperature gas-cooled reactor (HTGR) technology. The inherently safe HTGR design characteristics can be utilized to supply high-temperature process heat, co-generated electricity, and/or hydrogen for a number of industrial applications (e.g., petrochemical processes). Completion of the NGNP will result in a facility that demonstrates the safety and economics of the design, the commercial industrial potential of the technology, and the viability of the licensing strategy.

  3. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C1 1 1 1 1

  4. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C1 1 1 1 12 ***

  5. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C1 1 1 1 12 ***3.A

  6. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C1 1 1 1 12

  7. Sample Form DOE NRC 740M

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNLMay 2010 NationalStorm Water

  8. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1a ComplexMaersk LineManhattan1Y-12

  9. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1a ComplexMaersk

  10. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1a ComplexMaersk2*** Company Name

  11. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1a ComplexMaersk2*** Company Name

  12. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1a ComplexMaersk2*** Company Name.A

  13. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1a ComplexMaersk2*** Company

  14. NRC Solomons RFQ | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall, Pennsylvania: Energy Resources JumpNEFAppropriationReference Manual

  15. Codes and standards and other guidance cited in regulatory documents

    SciTech Connect (OSTI)

    Nickolaus, J.R.; Bohlander, K.L.

    1996-08-01T23:59:59.000Z

    As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).

  16. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions, LLC

    2003-08-25T23:59:59.000Z

    The purpose of this program guidance document is to provide technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the SARP and/or C of C shall govern. The C of C states: ''...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, ''Operating Procedures,'' of the application.'' It further states: ''...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, ''Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC approved, users need to be familiar with 10 CFR {section} 71.11, ''Deliberate Misconduct.'' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions. Following these instructions assures that operations are safe and meet the requirements of the SARP. This document is available on the Internet at: ttp://www.ws/library/t2omi/t2omi.htm. Users are responsible for ensuring they are using the current revision and change notices. Sites may prepare their own document using the word-for-word steps in th is document, in sequence, including Notes and cautions. Site specific information may be included as necessary. The document, and revisions, must then be submitted to CBFO at sitedocuments@wipp.ws for approval. A copy of the approval letter from CBFO shall be available for audit purposes. Users may develop site-specific procedures addressing preoperational activities, quality assurance (QA), hoisting and rigging, and radiation health physics to be used with the instructions contained in this document. Users may recommend changes to this document by submitting their recommendations (in writing) to the WIPP M&O Contractor RH Packaging Maintenance Engineer for evaluation. If approved, the change(s) will be incorporated into this document for use by ALL users. Before first use and every 12 months after, user sites will be audited to this document to ensure compliance. They will also be audited within one year from the effective date of revisions to this document.

  17. Microsoft Word - SmartGrid - NRC Input to DOE Requestrvjcomments...

    Broader source: Energy.gov (indexed) [DOE]

    are most problematic near the end of a fuel cycle (typically 18 months) where reactor power control is more complicated. NPPs control systems will not be interfaced with or...

  18. Microsoft PowerPoint - NRC Nuclear Export Controls Implementing...

    National Nuclear Security Administration (NNSA)

    international treaties, agreements, and other obligations * Apply to any person who exports or imports nuclear equipment and material with few exceptions * Authorize export...

  19. Kathy Yelick Co-authors NRC Report on Computer Performance -...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the lab's NERSC Division, was a panelist in a March 22 discussion of "The Future of Computer Performance: Game Over or Next Level?" a new report by the National Research Council....

  20. Recent MELCOR and VICTORIA Fission Product Research at the NRC

    SciTech Connect (OSTI)

    Bixler, N.E.; Cole, R.K.; Gauntt, R.O.; Schaperow, J.H.; Young, M.F.

    1999-01-21T23:59:59.000Z

    The MELCOR and VICTORIA severe accident analysis codes, which were developed at Sandia National Laboratories for the U. S. Nuclear Regulatory Commission, are designed to estimate fission product releases during nuclear reactor accidents in light water reactors. MELCOR is an integrated plant-assessment code that models the key phenomena in adequate detail for risk-assessment purposes. VICTORIA is a more specialized fission- product code that provides detailed modeling of chemical reactions and aerosol processes under the high-temperature conditions encountered in the reactor coolant system during a severe reactor accident. This paper focuses on recent enhancements and assessments of the two codes in the area of fission product chemistry modeling. Recently, a model for iodine chemistry in aqueous pools in the containment building was incorporated into the MELCOR code. The model calculates dissolution of iodine into the pool and releases of organic and inorganic iodine vapors from the pool into the containment atmosphere. The main purpose of this model is to evaluate the effect of long-term revolatilization of dissolved iodine. Inputs to the model include dose rate in the pool, the amount of chloride-containing polymer, such as Hypalon, and the amount of buffering agents in the containment. Model predictions are compared against the Radioiodine Test Facility (RTF) experiments conduced by Atomic Energy of Canada Limited (AECL), specifically International Standard Problem 41. Improvements to VICTORIA's chemical reactions models were implemented as a result of recommendations from a peer review of VICTORIA that was completed last year. Specifically, an option is now included to model aerosols and deposited fission products as three condensed phases in addition to the original option of a single condensed phase. The three-condensed-phase model results in somewhat higher predicted fission product volatilities than does the single-condensed-phase model. Modeling of U02 thermochemistry was also improved, and results in better prediction of vaporization of uranium from fuel, which can react with released fission products to affect their volatility. This model also improves the prediction of fission product release rates from fuel. Finally, recent comparisons of MELCOR and VICTORIA with International Standard Problem 40 (STORM) data are presented. These comparisons focus on predicted therrnophoretic deposition, which is the dominant deposition mechanism. Sensitivity studies were performed with the codes to examine experimental and modeling uncertainties.

  1. Agenda Highlights: 2012 DOE-NRC NMMSS Annual User Training

    National Nuclear Security Administration (NNSA)

    Initiatives U.S.-Australian Cooperation Agreement AwardsRecognitions Update on Blue Ribbon Commission Report (Tentative) Cyber security Issues and Implications GAO report...

  2. PRESENTATION TO NRC BURNING PLASMA PANEL DR. STEPHEN O. DEAN

    E-Print Network [OSTI]

    JANUARY 17, 2003 In response to request by panel co-chair John Ahearne as follows: "We have heard from" #12;2 BOTTOM LINES FUSION IS NOT ON THE RADAR SCREEN OF THE U. S. ELECTRIC UTILITIES ! To get DEVELOPMENT WOULD ALSO ATTRACT INTEREST FROM INDUSTRY GENERAL ATOMICS, FOR HISTORICAL REASONS, IS UNIQUE

  3. Nuclear safety information sharing agreement between NRC and...

    Energy Savers [EERE]

    3116 Public Meeting Summaries - July 2007 Fifth National Report for the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management...

  4. Radiocolloids in leachate from the NRC field lysimeter investigations

    SciTech Connect (OSTI)

    Brey, R.R.; Butikofer, T. [Idaho State Univ., Pocatello, ID (United States)] [Idaho State Univ., Pocatello, ID (United States); McConnell, J.W.; Rogers, R.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1998-12-31T23:59:59.000Z

    An investigation of colloidal particles has been completed on leachate samples collected from sand and soil-filled lysimeters (of the Field Lysimeter Investigation: Low-Level Waste Data Base Development Program) in which low-level radioactive waste forms were buried. An array of analytical techniques including: gamma spectroscopy, liquid scintillation spectrometry, gross alpha and beta particle proportional counting, energy dispersive X-ray analysis (EDX), neutron activation analysis (NAA), X-ray fluorescence analysis (XRF), proton induced X-ray emission analysis (PIXE), gravimetric analysis, and scanning electron microscopy (SEM), were performed on samples thought to contain colloidal particles to determine particle composition and the nature of their association with radioactive material. Several different types of particles ranging in size from 0.02 to 20 {micro}m were identified within the leachate including crystalline calcium hydroxide particles, rounded siliceous grains, angular weathered soil, and spherical particles apparently composed of an organic polymer. The primary radioactive material associated with these particles was Sr-90. About 2% of the total Sr-90 activity in the leachate is associated with colloidal particles. This information indicates that colloidal particles play a role in radioactive material transport through lysimeter soils.

  5. Predictive Bias and Sensitivity in NRC Fuel Performance Codes

    SciTech Connect (OSTI)

    Geelhood, Kenneth J.; Luscher, Walter G.; Senor, David J.; Cunningham, Mitchel E.; Lanning, Donald D.; Adkins, Harold E.

    2009-10-01T23:59:59.000Z

    The latest versions of the fuel performance codes, FRAPCON-3 and FRAPTRAN were examined to determine if the codes are intrinsically conservative. Each individual model and type of code prediction was examined and compared to the data that was used to develop the model. In addition, a brief literature search was performed to determine if more recent data have become available since the original model development for model comparison.

  6. February 9, 2011 UMTC DOCTORAL PROGRAMS WITH NRC ASSESSMENT RANGES

    E-Print Network [OSTI]

    Minnesota, University of

    ,30) Computer Science (20,35) Applied Plant Sciences (22,25) Communication Studies (23,62) Health Services Science (3,15) Aerospace Engineering and Mechanics (4,3) Applied Economics (4,7) Chemical Engineering (5,4) Natural Resource Science and Management (2,4) American Studies (3,4) Food Science (3,15) Aerospace

  7. Nuclear Material Transaction Report NRC 741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 1

  8. Nuclear Material Transaction Report NRC 741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 1D

  9. Nuclear Material Transaction Report NRC741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1

  10. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 A

  11. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 A

  12. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 A

  13. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 A

  14. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 A

  15. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1 A

  16. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C l l a10B 1 1 1

  17. Nuclear safety information sharing agreement between NRC and DOE's Office

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking ofOilNEWResponse to Time-Based Rates fromNuclear Securityand Facility

  18. Jennifer Schaefer > NRC Postdoctoral Fellow - National Institute of

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn12electron beam chargesJennifer Awe About Us

  19. NRC Leadership Expectations and Practices for Sustaining a High Performing

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagement ofConverDyn NOPR ConverDyn NOPR ConverDyn2 OMB Control

  20. DOE/NRC F 740M | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy, OAPMMilestone | DepartmentEA - 0942 E N v8 AUDIT14

  1. DOE Replies Support NRC Commissioners and Authority to Withdraw Yucca

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof"WaveInteractions and PolicyCybersecurity Threats |

  2. Use of Barrier Analysis in NRC Staff's Performance Assessment Reviews |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium TransferonUS-India EnergyUnlocking

  3. Agenda Highlights: 2012 DOE-NRC NMMSS Annual User Training

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AO 474.2 Chg 1KANSASVisit to theAgenda

  4. DOE/NRC Forms | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14Russianvolunteer |At.<ENDMENT/MODIFICATION NO.Template FORNRC

  5. Microsoft Word - 0906 NMMSS News DOE NRC Approved.doc

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and FeedbackProgrammatic UpdatePublic6

  6. DOE/NRC F 742 | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015 Business42.1 DEPARTMENTSeptember 27,September 24, 2002The RoundtableDOE/NRCfor

  7. DOE/NRC F 742C | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015 Business42.1 DEPARTMENTSeptember 27,September 24, 2002The

  8. Guidance for implementing the long-term surveillance program for UMTRA Project Title I Disposal Sites

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    This guidance document has two purposes: it provides guidance for writing site-specific long-term surveillance plans (LTSP) and it describes site surveillance, monitoring, and long-term care techniques for Title I disposal sites of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC Section 7901 et seq.). Long-term care includes monitoring, maintenance, and emergency measures needed to protect public health and safety and the environment after remedial action is completed. This document applies to the UMTRCA-designated Title I disposal sites. The requirements for long-term care of the Title I sites and the contents of the LTSPs are provided in U.S. Nuclear Regulatory Commission (NRC) regulations (10 CFR Section 40.27) provided in Attachment 1.

  9. GUIDANCE ON IMPLEMENTING RADIONUCLIDE NESHAPS

    E-Print Network [OSTI]

    . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Background and History of the Standards . . . . . . . . . 2 1.2 Implementing these Standards - Radionuclide Emissions Other than Radon from DOE Facilities . . . . . . . . . . . . . . . . 13 2.2.2 Subpart I - NRC Licensed and Non-DOE Federal Facilities . . . . . . . . . . . . . . . . . . 14 2.3 NESHAPS

  10. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2002-03-04T23:59:59.000Z

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT Shipping Package, and directly related components. This document complies with the minimum requirements as specified in TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event there is a conflict between this document and the SARP or C of C, the SARP and/or C of C shall govern. C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SAR P charges the WIPP Management and Operation (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize these operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

  11. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-02-28T23:59:59.000Z

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.

  12. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    OHara, J.M.; Higgins, J.C.

    2010-01-31T23:59:59.000Z

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  13. Guidance for implementing the UMTRA Project long-term surveillance program

    SciTech Connect (OSTI)

    Not Available

    1992-09-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) has issued a general license for the custody and long-term care of US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project permanent disposal sites. The purpose of this general license is to ensure that the UMTRA disposal sites will be cared for in such a manner as to protect the public health and safety and the environment upon completion of remedial actions. The general license will be in effect for a disposal site when NRC accepts the disposal site long-term surveillance plan (LTSP) that meets the requirements of 10 CFR 40.27. The site LTSP describes in detail the long-term surveillance program, including any monitoring, maintenance, and emergency measures necessary to fulfill the conditions of the general license. This guidance document provides (1) instructions for preparing the disposal site LTSPs and (2) instructions for carrying out the UMTRA Project long-term surveillance program, including any monitoring that may be required. The information provided in this document also is in accordance with the regulatory requirements set forth in 40 CFR 192. On January 5, 1985, the US Tenth Circuit Court of Appeals remanded the groundwater standards, 40 CFR 192.02. Proposed groundwater standards were issued for comment on September 24, 1987 (52 FR 3600). When the groundwater standards become final, this document will be revised, as appropriate. This document also will be updated in response to any changes to 10 CFR 40, or in response to changes in the manner in which the long-term care of the licensed disposal sites is carried out.

  14. Guidance for implementing the UMTRA Project long-term surveillance program. Final report, Revision 1

    SciTech Connect (OSTI)

    Not Available

    1992-09-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) has issued a general license for the custody and long-term care of US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project permanent disposal sites. The purpose of this general license is to ensure that the UMTRA disposal sites will be cared for in such a manner as to protect the public health and safety and the environment upon completion of remedial actions. The general license will be in effect for a disposal site when NRC accepts the disposal site long-term surveillance plan (LTSP) that meets the requirements of 10 CFR 40.27. The site LTSP describes in detail the long-term surveillance program, including any monitoring, maintenance, and emergency measures necessary to fulfill the conditions of the general license. This guidance document provides (1) instructions for preparing the disposal site LTSPs and (2) instructions for carrying out the UMTRA Project long-term surveillance program, including any monitoring that may be required. The information provided in this document also is in accordance with the regulatory requirements set forth in 40 CFR 192. On January 5, 1985, the US Tenth Circuit Court of Appeals remanded the groundwater standards, 40 CFR 192.02. Proposed groundwater standards were issued for comment on September 24, 1987 (52 FR 3600). When the groundwater standards become final, this document will be revised, as appropriate. This document also will be updated in response to any changes to 10 CFR 40, or in response to changes in the manner in which the long-term care of the licensed disposal sites is carried out.

  15. Computer surety: computer system inspection guidance. [Contains glossary

    SciTech Connect (OSTI)

    Not Available

    1981-07-01T23:59:59.000Z

    This document discusses computer surety in NRC-licensed nuclear facilities from the perspective of physical protection inspectors. It gives background information and a glossary of computer terms, along with threats and computer vulnerabilities, methods used to harden computer elements, and computer audit controls.

  16. Technical Guidance

    Broader source: Energy.gov [DOE]

    The Office of Technical Guidance, within the Office of Health, Safety and Security develops and issues Government-wide and Department-wide technical guidance to ensure that classified nuclear...

  17. Microsoft PowerPoint - 7_GARY_LANGLIE_NMMSS 2014 NRC HEU Report...

    National Nuclear Security Administration (NNSA)

    speech 91% of HEU exports occurred before 1990 Most HEU exported to France, Germany, and Canada HEU Imports - 100 200 300 400 500 600 700 800 900 1958 1959 1960 1961...

  18. Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

    SciTech Connect (OSTI)

    Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

    1986-03-01T23:59:59.000Z

    This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

  19. Dismantling of Loop-Type Channel Equipment of MR Reactor in NRC 'Kurchatov Institute' - 13040

    SciTech Connect (OSTI)

    Volkov, Victor; Danilovich, Alexey; Zverkov, Yuri; Ivanov, Oleg; Kolyadin, Vyacheslav; Lemus, Alexey; Pavlenko, Vitaly; Semenov, Sergey; Fadin, Sergey; Shisha, Anatoly; Chesnokov, Alexander [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)] [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)

    2013-07-01T23:59:59.000Z

    In 2009 the project of decommissioning of MR and RTF reactors was developed and approved by the Expert Authority of the Russian Federation (Gosexpertiza). The main objective of the decommissioning works identified in this project: - complete dismantling of reactor equipment and systems; - decontamination of reactor premises and site in accordance with the established sanitary and hygienic standards. At the preparatory stage (2008-2010) of the project the following works were executed: loop-type channels' dismantling in the storage pool; experimental fuel assemblies' removal from spent fuel repositories in the central hall; spent fuel assembly removal from the liquid-metal-cooled loop-type channel of the reactor core and its placement into the SNF repository; and reconstruction of engineering support systems to the extent necessary for reactor decommissioning. The project assumes three main phases of dismantling and decontamination: - dismantling of equipment/pipelines of cooling circuits and loop-type channels, and auxiliary reactor equipment (2011-2012); - dismantling of equipment in underground reactor premises and of both MR and RTF in-vessel devices (2013-2014); - decontamination of reactor premises; rehabilitation of the reactor site; final radiation survey of reactor premises, loop-type channels and site; and issuance of the regulatory authorities' de-registration statement (2015). In 2011 the decommissioning license for the two reactors was received and direct MR decommissioning activities started. MR primary pipelines and loop-type facilities situated in the underground reactor hall were dismantled. Works were also launched to dismantle the loop-type channels' equipment in underground reactor premises; reactor buildings were reconstructed to allow removal of dismantled equipment; and the MR/RTF decommissioning sequence was identified. In autumn 2011 - spring 2012 results of dismantling activities performed are: - equipment from underground rooms (No. 66, 66A, 66B, 72, 64, 63) - as well as from water and gas loop corridors - was dismantled, with the total radwaste weight of 53 tons and the total removed activity of 5,0 x 10{sup 10} Bq; - loop-type channel equipment from underground reactor hall premises was dismantled; - 93 loop-type channels were characterized, chopped and removed, with radwaste of 2.6 x 10{sup 13} Bq ({sup 60}Co) and 1.5 x 10{sup 13} Bq ({sup 137}Cs) total activity removed from the reactor pool, fragmented and packaged. Some of this waste was placed into the high-level waste (HLW) repository of the Center. Dismantling works were executed with application of remotely operated mechanisms, which promoted decrease of radiation impact on the personnel. The average individual dose for the personnel was 1.9 mSv/year in 2011, and the collective dose is estimated as 0.0605 man x Sv/year. (authors)

  20. Can. J. Fish. Aquat. Sci. 53: 20442051 (1996). 1996 NRC Canada Seasonal variation of lipid composition,

    E-Print Network [OSTI]

    F. Cavaletto, Thomas F. Nalepa, Ronald Dermott, Wayne S. Gardner, Michael A. Quigley, and Gregory A on fresh food inputs at this time (Quigley 1988; Der- mott and Corning 1988). Diporeia lipid levels.S. Gardner, M.A. Quigley, and G.A. Lang. National Oceanic and Atm

  1. U.S. NRC CONFIRMATORY LEVEL 1 PRA SUCCESS CRITERIA ACTIVITIES

    SciTech Connect (OSTI)

    Donald Helton; Hossein Esmaili; Robert Buell

    2011-03-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to support a number of risk-informed initiatives. The fidelity and realism of these models are ensured through a number of processes including cross-comparison with industry models, review and use by a wide range of technical experts, and confirmatory analysis. This paper will describe a key activity in the latter arena. Specifically, this paper will describe MELCOR analyses performed to augment the technical basis for confirming or modifying specific success criteria of interest. The analyses that will be summarized provide the basis for confirming or changing success criteria in a specific 3-loop pressurized-water reactor and a Mark-I boiling-water reactor. Initiators that have been analyzed include loss-of-coolant accidents, loss of main feedwater, spontaneous steam generator tube rupture, inadvertent opening of a relief valve at power, and station blackout. For each initiator, specific aspects of the accident evolution are investigated via a targeted set of calculations (3 to 22 distinct accident analyses per initiator). Further evaluation is ongoing to extend the analyses’ conclusions to similar plants (where appropriate), with consideration of design and modeling differences on a scenario-by-scenario basis. This paper will also describe future plans.

  2. Joint NRC/ANS meeting on basic thermal-hydraulic mechanisms in LWR analysis

    SciTech Connect (OSTI)

    Hsu, Y Y; Lee, R [comps.

    1983-04-01T23:59:59.000Z

    Separate abstracts were prepared for 18 papers in this conference proceedings. Three papers are also included in the proceedings that were previously abstracted for EDB. (LEW)

  3. Overview of ORNL/NRC programs addressing durability of concrete structures

    SciTech Connect (OSTI)

    Naus, D.J.; Oland, C.B.

    1994-06-01T23:59:59.000Z

    The role of reinforced concrete relative to its applications as either safety-related structures in nuclear power or engineered barriers of low-level radioactive waste disposal facilities is described. Factors that can affect the long-term durability of reinforced concrete are identified. Overviews are presented of the Structural Aging Program, which is addressing the aging management of safety-related concrete structures in nuclear power plants, and the Permeability Test Methods and Data Program, which is identifying pertinent data and information for use in performance assessments of engineered barriers for low-level radioactive waste disposal.

  4. Beta particle measurement and dosimetry Requirements at NRC-licensed facilities

    SciTech Connect (OSTI)

    Rathbun, L.A.; Endres, G.W.R.; Fox, R.A.; Roberson, P.L.; Scherpelz, R.I.

    1984-08-01T23:59:59.000Z

    Researchers from Pacific Northwest Laboratroy (PNL) have conducted beta radiation measurements under laboratory and field conditions to assess the degree of the measurement problem and offer suggestions for possible remedies. The primary measurement systems selected for use in this study were the silicon (Si) surface barrier spectrometer system and the multielement beta dosimeter. Three boiling water reactors (BWRs), two pressurized water reactors (PWRs), and one fuel fabrication facility were visited during the course of the study. Although beta fields from cobalt-60 were the most common type found at commercial reactor facilities, higher energy beta fields were found at locations associated with spent fuel handling, liquid radioactive waste, and BWR turbine components. Commercially-available dosimeters and survey instruments were used to measure the same laboratory and licensee facility beta fields characterized with PNL's active and passive spectrometers. A prototype spectrometer was also used in the laboratory measurements. The commercial instruments and dosimeters used in this study typically responded low to the beta fields measured, especially where maximum beta energies were less than approximately 500 keV.

  5. Microsoft PowerPoint - 4_Paul_NRC MC&A Inspection Summary NMMSS...

    National Nuclear Security Administration (NNSA)

    - The inspection was very well coordinated concerning documentation and observation of fuel locations - Water in the fuel pool was of good water quality - Fuel history sheets were...

  6. Microsoft PowerPoint - 12_BRIAN_HORN_NRC and DOE recognition...

    National Nuclear Security Administration (NNSA)

    and - Inventory reconciled within 30 days of receipt - 170 RIS's * 65 reactors * 7 Fuel cycle * 98 Licensees primarily possessing < 350 grams of fissile "Outstanding" in...

  7. LETTER REPORT SUMMARY RESULTS OF THE NRC TEAM INTERACTION SKILLS STUDY AT DIABLO CANYON POWER PLANT

    SciTech Connect (OSTI)

    Hauth, J. T.; Toquam, J. L.; Bramwell, A. T.; Fleming, T. E.

    1990-12-01T23:59:59.000Z

    This report presents information to participants in the Team Interaction Skills study conducted at Diablo Canyon Power Plant from September to November 1989. A study was conducted to develop and assess measures of team interaction skills of nuclear power plant control room crews in simulated emergency conditions. Data were collected at a boiling water reactor (BWR) and pressurized water reactor (PWA) using three sets of rating scales; Behaviorally Anchored Rating Scales (BARS), Behavioral Frequency rating scales, and Technical Performance rating scales. Diablo Canyon Power Plant agreed to serve as the PWR plant in the study. Obse!Vers consisting of contract license examiners, Diablo Canyon Power Plant training instructors, and project staff used the rating scales to provide assessments of team interaction skills and technical skills of control room crews during emerg-3ncy scenarios as part of license requalification training. Crew members were also asked to providH self-ratings of their performance to gather information regarding crew responses to the Team Interactions Skills rating scales.

  8. DOE Does Not Oppose Petitions to Intervene in Yucca Mountain NRC Proceeding

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy, OAPM |TRU Waste Cleanup at Bettis DOEElectric Transmission||

  9. Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference; Sessions 1--8

    SciTech Connect (OSTI)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01T23:59:59.000Z

    Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

  10. Twenty-first DOE/NRC nuclear air-cleaning conference

    SciTech Connect (OSTI)

    Bellamy, R.R. [Nuclear Regulatory Commission, Washington, DC (United States); Moeller, D.W.; First, M.W. [Harvard Univ., Cambridge, MA (United States)

    1991-01-01T23:59:59.000Z

    The Twenty-First Department of Energy/Nuclear Regulatory Commission Nuclear Air-Cleaning Conference was held August 12-16, 1990, in San Diego, California. A total of 232 air-cleaning specialists attended the conference. The United States and 14 foreign countries were represented, and the specialists were affiliated with government agencies, educational institutions, and the nuclear industry. Several major topics were discussed during the conference, including development and use of industry codes and standards; chemical processing off-gas cleaning; particulate filter developments, including filter testing and filter response to physical stress; development of adsorbents, including laboratory testing and in-place testing; incineration and vitrification; containment venting; reactor operations, including design and modeling; and measurement systems capable of verifying safe operation. The conference continued to provide a forum for direct and efficient interchange of technical and philosophical information among the participants. The high level of foreign participation and interest continues, as evidenced by over one half of the papers being sponsored by foreign interests, and one quarter of the attendees being from outside the United States. Further evidence of international interest was seen in a plenary session devoted to nuclear air-cleaning programs in nine different countries. A common concern throughout many of the sessions was the development of meaningful standards, their implementation for existing air-cleaning system, and the use of these standards by regulatory agencies. 13 refs., 2 tabs.

  11. Microsoft PowerPoint - 5_Pat Smith_NMMSS_2013_Presentation_NRC Reconciliation.pptx

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA

  12. http://www.nrc.gov/reading-rm/doc-collections/cfr/part020/full-

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. HirschOccurrence Reporting and2. TheAirA

  13. http://www.nrc.gov/reading-rm/doc-collections/cfr/part061/full-

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. HirschOccurrence Reporting and2.

  14. Kathy Yelick Co-authors NRC Report on Computer Performance - NERSC Center

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |Is Your Home as ReadyAppointed to National Academies ComputerNews,

  15. DOE Makes Filing with NRC in Support OF Authority to Withdraw Yucca

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof"Wave theJulyD&DDepartment offorEnergygoal, 52% smallApplication

  16. DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof"WaveInteractionsMaterialsDevelopEnergyof EnergyDOE, NEPA,

  17. DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you0and Transparency, and MoreEnergyof EnergyDepartmentDOE's RoundDepartment

  18. o:\informs\fixforms\nrc740m.wpf | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof Energy 2, 2015Visiting8.pdfand Characterization of aHome *

  19. Microsoft Word - SmartGrid - NRC Input to DOE Requestrvjcomments.docx

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions forCheneyNovemberi CONTENTS ExecutiveHouse Committee on345ThisNuclear

  20. NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_Cost Estimating35.docMusings on| Department of Energy NPR Sheds2

  1. Microsoft PowerPoint - NRC Managent Persectives_Marissa Bailey [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and Feedback onWorkingIAEAMOXRole inStrategy

  2. Microsoft Word - NMMSS Newsletter October 2014 Final-NRC 10-16 comments.docx

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis andB - H, Page i PART I2MAY news October 2014

  3. Minutes from 12 December 2006 DOE/NRC Video Teleconference Call on Section 3116 Implementation Activities

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions forCheneyNovemberiMid-Level EthanolDepartment of EnergyINDIAN12

  4. POLICY GUIDANCE MEMORANDUM #19 Guidance on Transition to Eliminate...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    9 Guidance on Transition to Eliminate FCIP (Expired) POLICY GUIDANCE MEMORANDUM 19 Guidance on Transition to Eliminate FCIP (Expired) THIS GUIDANCE HAS EXPIRED Guidance on the...

  5. Lessons Learned Quarterly Report, March 2002 | Department of...

    Energy Savers [EERE]

    NRC Seeks Comments on Draft NEPA Guidance DOE-wide NEPA Contracts Update Essential Fish Habitat Final Rule Issued Transitions CEQ Task Force to Modernize NEPA Senior NEPA...

  6. GUIDANCE FOR THE PROPER CHARACTERIZATION AND CLASSIFICATION OF LOW SPECIFIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED OBJECTS FOR DISPOSAL

    SciTech Connect (OSTI)

    PORTSMOUTH JH; BLACKFORD LT

    2012-02-13T23:59:59.000Z

    Regulatory concerns over the proper characterization of certain waste streams led CH2M HILL Plateau Remediation Company (CHPRC) to develop written guidance for personnel involved in Decontamination & Decommissioning (D&D) activities, facility management and Waste Management Representatives (WMRs) involved in the designation of wastes for disposal on and off the Hanford Site. It is essential that these waste streams regularly encountered in D&D operations are properly designated, characterized and classified prior to shipment to a Treatment, Storage or Disposal Facility (TSDF). Shipments of waste determined by the classification process as Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) must also be compliant with all applicable U.S. Department of Transportation (DOE) regulations as well as Department of Energy (DOE) orders. The compliant shipment of these waste commodities is critical to the Hanford Central Plateau cleanup mission. Due to previous problems and concerns from DOE assessments, CHPRC internal critiques as well as DOT, a management decision was made to develop written guidance and procedures to assist CHPRC shippers and facility personnel in the proper classification of D&D waste materials as either LSA or SCO. The guidance provides a uniform methodology for the collection and documentation required to effectively characterize, classify and identify candidate materials for shipping operations. A primary focus is to ensure that waste materials generated from D&D and facility operations are compliant with the DOT regulations when packaged for shipment. At times this can be difficult as the current DOT regulations relative to the shipment of LSA and SCO materials are often not clear to waste generators. Guidance is often sought from NUREG 1608/RAMREG-003 [3]: a guidance document that was jointly developed by the DOT and the Nuclear Regulatory Commission (NRC) and published in 1998. However, NUREG 1608 [3] is now thirteen years old and requires updating to comply with the newer DOT regulations. Similar challenges present themselves throughout the nuclear industry in both commercial and government operations and therefore, this is not only a Hanford Site problem. Shipping radioactive wastes as either LSA or SCO rather than repacking it is significantly cheaper than other DOT radioactive materials shipping classifications particularly when the cost of packages is included. Additionally, the need to 'repackage' materials for transport can often increase worker exposure, necessitated by 'repackaging' waste materials into DOT 7 A Type A containers.

  7. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    O'Hara, J.M.; W. Gunther, G. Martinez-Guridi

    2010-02-26T23:59:59.000Z

    New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I&C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I&C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I&C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I&C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I&C conditions as part of the design process and the HSI features and functions that support operators to monitor I&C performance and manage I&C degradations when they occur. In addition, we identified topics for future research.

  8. Recommendations for probabilistic seismic hazard analysis: Guidance on uncertainty and use of experts

    SciTech Connect (OSTI)

    Budnitz, R.J.; Apostolakis, G.; Boore, D.M. [and others

    1997-04-01T23:59:59.000Z

    Probabilistic Seismic Hazard Analysis (PSHA) is a methodology that estimates the likelihood that various levels of earthquake-caused ground motion will be exceeded at a given location in a given future time period. Due to large uncertainties in all the geosciences data and in their modeling, multiple model interpretations are often possible. This leads to disagreement among experts, which in the past has led to disagreement on the selection of ground motion for design at a given site. In order to review the present state-of-the-art and improve on the overall stability of the PSHA process, the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Energy (DOE), and the Electric Power Research Institute (EPRI) co-sponsored a project to provide methodological guidance on how to perform a PSHA. The project has been carried out by a seven-member Senior Seismic Hazard Analysis Committee (SSHAC) supported by a large number other experts. The SSHAC reviewed past studies, including the Lawrence Livermore National Laboratory and the EPRI landmark PSHA studies of the 1980`s and examined ways to improve on the present state-of-the-art. The Committee`s most important conclusion is that differences in PSHA results are due to procedural rather than technical differences. Thus, in addition to providing a detailed documentation on state-of-the-art elements of a PSHA, this report provides a series of procedural recommendations. The role of experts is analyzed in detail. Two entities are formally defined-the Technical Integrator (TI) and the Technical Facilitator Integrator (TFI)--to account for the various levels of complexity in the technical issues and different levels of efforts needed in a given study.

  9. NRC Research Program on Plant Aging: Listing and summaries of reports issued through September 1993. Revision 4

    SciTech Connect (OSTI)

    Vora, J.P.

    1993-12-01T23:59:59.000Z

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through September 1993 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject.

  10. Radiological Control of Water in Reactor Pond of MR Reactor in NRC 'Kurchatov Institute', During Dismantling Work - 13462

    SciTech Connect (OSTI)

    Stepanov, Alexey; Simirsky, Yury; Semin, Ilya; Volkovich, Anatoly; Ivanov, Oleg [National Research Center 'Kurchatov Institute', Moscow (Russian Federation)] [National Research Center 'Kurchatov Institute', Moscow (Russian Federation)

    2013-07-01T23:59:59.000Z

    The analysis of the activity and radionuclide composition of water from the MR reactor pond for ?,?,?-ray radionuclides was made. To solve this problem we use a wide range of laboratory equipment: gamma spectrometric complex, beta spectrometric complex, vacuum alpha spectrometer, and spectrometric complex with liquid scintillator. The water from MR reactor pond contains: Cs-137 (2,6*10{sup 2} Bq/g), Co-60(1,8 Bq/g), Sr-90 (1,0*10{sup 2} Bq/g), H-3 (7,0*10{sup 3} Bq/g), and components of nuclear fuel (U-232,U-234,U-235,U-236,U-238). Therefore the cleaning water from radioactivity waste occurs to be quite a complicated radiochemical task. (authors)

  11. A PROPOSED METHOD FOR ESTIMATING FAILURE RATES OF DEGRADED PASSIVE COMPONENTS IN THE NRC SIGNIFICANCE DETERMINATION PROCESS

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Johnson, Kenneth I.; Ivans, William J.; Lowry, Peter P.

    2013-11-01T23:59:59.000Z

    This paper outlines a methodology for estimation of the incremental core damage frequency associated with the degradation of passive components with a view to its application in the US Nuclear Regulatory Commission's significance determination process. The method involves use of simplified physics-based models of materials degradation and the probabilistic comparison of transient loads with deteriorating system capacities.

  12. Multi-physics coupled code reactor analysis with the U.S. NRC code system TRACE/PARCS

    SciTech Connect (OSTI)

    Xu, Y.; Downar, T.; Ward, A. [Purdue Univ. (United States); Kozlowski, T. [KTH, Nuclear Power Safety (Sweden); Ivanov, K. [Penn State Univ. (United States)

    2006-07-01T23:59:59.000Z

    This paper will focus on the PARCS code and some of the recent applications of the coupled TRACE/PARCS codes to OECD LWR benchmarks and to the Advanced CANDU Reactor, the ACR-700. (authors)

  13. Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18

    SciTech Connect (OSTI)

    NONE

    1995-10-01T23:59:59.000Z

    The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

  14. Directory of certificiates of compliance for radioactive materials packages: Report of NRC approved packages. Revision 19, Volume 1

    SciTech Connect (OSTI)

    NONE

    1996-10-01T23:59:59.000Z

    This directory provides information on packagings approved by the U.S. Nuclear Regulatory Commission.

  15. Microsoft Word - 1aDOE-ID-12-047 Westinghouse EC B3-6 NRC.doc

    Broader source: Energy.gov (indexed) [DOE]

    and safety procedures. They are currently only intending to have fresh fuel material, depleted for this first project, and will ship the material to TAMU. TAMU will receive...

  16. Microsoft PowerPoint - 4_Paul_NRC MC&A Inspection Summary NMMSS 2013.ppt [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1aMargaretForeignInspection Summary

  17. Social Media and the NRC: What We're Doing, Why We're Doing It, and

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCO OverviewRepositoryManagement | DepartmentImpactWhat Else We Might Do |

  18. Microsoft PowerPoint - 2_Peter J. Habighorst_NRC Remarks 2013 NMMSS Users Meeting.pptx

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1aMargaret CanForeign

  19. Microsoft PowerPoint - 2_Peter J. Habighorst_NRC Remarks 2013 NMMSS Users Meeting.pptx

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby/%2AOU1aMargaret CanForeignSTATE OF NMMSS

  20. Microsoft PowerPoint - 12_BRIAN_HORN_NRC and DOE recognition May 13 2014.ppt [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:Administration SandiaAdministrationMartyn - Global

  1. Microsoft PowerPoint - 7_GARY_LANGLIE_NMMSS 2014 NRC HEU Report Presentation 21April2014.pptx

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and Feedback on NMMSSSourceUS

  2. Microsoft PowerPoint - 9_NRC Roundtable Cover_Wensday_NMMSS_2014_Powerpoint_TEMPLATE.ppt [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and Feedback onWorking Group - Reactorand

  3. Microsoft PowerPoint - NRC Nuclear Export Controls Implementing the NSG Trigger List_Gary Langlie [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and Feedback onWorkingIAEAMOXRole

  4. Microsoft Word - 1aDOE-ID-12-047 Westinghouse EC B3-6 NRC.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your HomeOverviewCleanupShipping Form3 - March, 2014970127

  5. LCC Guidance Rates

    Broader source: Energy.gov [DOE]

    Notepad text file provides the LCC guidance rates in a numbered format for the various regions throughout the U.S.

  6. Water Efficiency Goal Guidance

    Broader source: Energy.gov [DOE]

    The Council on Environmental Quality (CEQ) issued water efficiency goal guidance in Federal Agency Implementation of Water Efficiency and Management Provisions of Executive Order 13514. This...

  7. wind_guidance

    Broader source: Energy.gov [DOE]

    Guidance to Accompany Non-Availability Waiver of the Recovery Act Buy American Provisions for 5kW and 50kW Wind Turbines

  8. Guidance Systems Division ,

    Office of Legacy Management (LM)

    Oockec No. 10-0772 22 OCT 1981 Bcndlx CorporaLion ' Guidance Systems Division , ATTN: Mr. Wf 11 la,,, Hnrr,,or Manngar, PlanL Englne0rtny Teterboro, New Jersey 07608 uwm STATES...

  9. Tables of cross references among SECY 82-111, NUREG 0700, NUREG 0835, NUREG 0801

    SciTech Connect (OSTI)

    Savage, J.W.

    1982-03-10T23:59:59.000Z

    This memorandum cross references topical statements extracted from four NRC documents that are useful for guidance in reviewing the Human Factors Engineering designs of main control rooms and control centers outside the main control rooms.

  10. Policy Guidance Memorandum | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Policy Guidance Memorandum Policy Guidance Memorandum Documents Available for Download POLICY GUIDANCE MEMORANDUM 13 Reemployment Priority List Selections This memorandum provides...

  11. Policy Guidance Memorandum | Department of Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Policy Guidance Memorandum Policy Guidance Memorandum Documents Available for Download POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES This has...

  12. Engineering Library Guidance

    E-Print Network [OSTI]

    Kaji, Hajime

    Science & Engineering Library Library Guidance April 2014 1 #12;Contents 1 Overview of Waseda University Library 2 Science & Engineering Library and the Student Reading Room 3 WINE: Waseda's Library Catalog3 WINE: Waseda's Library Catalog 4 Library Services 5 Notes 2 #12;How many libraries

  13. Building Energy Use Benchmarking Guidance

    Broader source: Energy.gov [DOE]

    Guidance describes the Energy Independence and Security Act of 2007 section 432 requirement for benchmarking Federal facilities.

  14. EPAct 2005 Metering Guidance Overview

    Office of Environmental Management (EM)

    * Agency policiesguidance Potential Roles for Utilities * Guidanceupdates on time-based pricing * Metering services * Finance installations * Other? Useful Documents * Guidance...

  15. Policy and Guidance | Department of Energy

    Energy Savers [EERE]

    Policy and Guidance Policy and Guidance Policy and Guidance Orders and Guides Directive Type Directive Number PolicyGuidance Title and Link Date Published Order DOE O 413.3B...

  16. Energy Sector Cybersecurity Framework Implementation Guidance

    Broader source: Energy.gov (indexed) [DOE]

    DRAFT FOR PUBLIC COMMENT SEPTEMBER, 2014 ENERGY SECTOR CYBERSECURITY FRAMEWORK IMPLEMENTATION GUIDANCE Energy Sector Cybersecurity Framework Implementation Guidance Table of...

  17. Selection of a discount rate for use in NRC regulatory analyses and application of discount rates to future averted health effects

    SciTech Connect (OSTI)

    Paananen, O.H.; Hendrickson, P.L.

    1993-01-01T23:59:59.000Z

    The principal objective of this report is to provide background information and recommendations on the use of discount rates in the regulatory analysis process. The report focuses on two issues selecting the appropriate discount rate or rates to use when conducting a regulatory analysis, and applying the selected discount rate to future health-related benefits estimated to result from alternative regulatory actions.

  18. PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report. NRC/EPRI/Westinghouse Report No. 11. Appendices K-P

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

    1982-09-01T23:59:59.000Z

    This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

  19. Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS

    SciTech Connect (OSTI)

    Lee, Deokjung [Purdue University (United States); Downar, Thomas J. [Purdue University (United States); Ulses, Anthony [U.S. Nuclear Regulatory Commission (United States); Akdeniz, Bedirhan [Pennsylvania State University (United States); Ivanov, Kostadin N. [Pennsylvania State University (United States)

    2004-10-15T23:59:59.000Z

    An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. Nuclear Regulatory Commission coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two-phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady-state and transient phases of the benchmark. Additional analyses of four fictitious extreme scenarios are performed to provide a basis for code-to-code comparisons and comprehensive testing of the thermal-hydraulics/neutronics coupling. The obtained results of sensitivity studies on the effect of direct moderator heating on transient simulation indicate the importance of this modeling aspect.

  20. From 1998 to 2000, through the Interagency Steering Committee on Radiation Standards (ISCORS), the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental

    E-Print Network [OSTI]

    . The parameters used in the dose modeling for the scenarios and the dose conversion factors calculated for each were taken. Approximately half of the samples were analyzed by the U.S. Department of Energy's Oak

  1. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Volume 2, Session 3A--Session 4B

    SciTech Connect (OSTI)

    Not Available

    1994-07-01T23:59:59.000Z

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers have been cataloged separately.

  2. Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1

    SciTech Connect (OSTI)

    Not Available

    1994-07-01T23:59:59.000Z

    The 1994 Symposium on Valve and Pump Testing, jointly sponsored by the Board of Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provides a forum for the discussion of current programs and methods for inservice testing and motor-operated valve testing at nuclear power plants. The symposium also provides an opportunity to discuss the need to improve that testing in order to help ensure the reliable performance of pumps and valves. The participation of industry representatives, regulators, and consultants results in the discussion of a broad spectrum of ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. This document, Volume 1, covers sessions 1A through session 2C. The individual papers have been cataloged separately.

  3. Microsoft PowerPoint - 8_Peter Habighorst_NRC_Act of 2012-status final 5-12 presentation.ppt [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch Project Lead SAMS  SAMSRoundtableUse of

  4. Microsoft PowerPoint - 4_JOHN_BALLARD_MARY_MCCDONNELL_NRC DOE REporting requirements_presentations_4-29-14.ppt [Compatibility M

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysis and Feedback on NMMSS Performance

  5. Guidance | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 RussianBy: Thomas P. D'Agostino,Glen WattmanInvestigationsandGridTheNEPA Guidance

  6. O&M Metering Guidance

    Broader source: Energy.gov [DOE]

    Presentation covers the O&M Metering Guidance and is given at the Spring 2010 Federal Utility Partnership Working Group (FUPWG) meeting in Rapid City, South Dakota.

  7. Radiation Protection Guidance Hospital Staff

    E-Print Network [OSTI]

    Kay, Mark A.

    Page 1 Radiation Protection Guidance For Hospital Staff Prepared for Stanford ..................................................................................................................... 17 The Basic Principles of Radiation Protection........................................................... 17 Protection against Radiation Exposure

  8. RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT

    E-Print Network [OSTI]

    Holland, Jeffrey

    RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT: Minors in Research Laboratories or Animal Facilities Page 1 of 4 PURPOSE: The purpose of this document is to provide guidance for Purdue sponsored programs which are designed for youth under the age of 15 and which have documented

  9. Army Policy Guidance for UESCs

    Broader source: Energy.gov [DOE]

    Presentation—given at the Spring 2009 Federal Utility Partnership Working Group (FUPWG) meeting—provides an overview of the U.S. Army's utility energy service contract (UESC) program and its UESC draft policy guidance.

  10. DEPARTMENTAL EMERGENCY PLAN Guidance Document

    E-Print Network [OSTI]

    Johnston, Daniel

    DEPARTMENTAL EMERGENCY PLAN Guidance Document #12;1 TABLE OF CONTENTS TABLE OF CONTENTS .................................................................................................12 EMERGENCY MANAGEMENT TEAM ........................................................12 ............................................................................................25 ADDITIONAL INFORMATIONAL DOCUMENTS.........................................25 #12;2 THIS PAGE

  11. Information architecture. Volume 3: Guidance

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    The purpose of this document, as presented in Volume 1, The Foundations, is to assist the Department of Energy (DOE) in developing and promulgating information architecture guidance. This guidance is aimed at increasing the development of information architecture as a Departmentwide management best practice. This document describes departmental information architecture principles and minimum design characteristics for systems and infrastructures within the DOE Information Architecture Conceptual Model, and establishes a Departmentwide standards-based architecture program. The publication of this document fulfills the commitment to address guiding principles, promote standard architectural practices, and provide technical guidance. This document guides the transition from the baseline or defacto Departmental architecture through approved information management program plans and budgets to the future vision architecture. This document also represents another major step toward establishing a well-organized, logical foundation for the DOE information architecture.

  12. Renewable Energy Requirement Guidance for EPAct 2005 and Executive...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Requirement Guidance for EPAct 2005 and Executive Order 13423 Renewable Energy Requirement Guidance for EPAct 2005 and Executive Order 13423 Guidance specifies conditions for...

  13. accident management guidance: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    React to Public Earnings Guidance investigates security analysts' reactions to public management guidance and assesses whether managers management provides public guidance....

  14. LM Records and Information Management Transition Guidance (January...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Records and Information Management Transition Guidance (January 2015) LM Records and Information Management Transition Guidance (January 2015) This guidance document establishes a...

  15. Building America Climate-Specific Guidance | Department of Energy

    Energy Savers [EERE]

    Building America Building America Climate-Specific Guidance Building America Climate-Specific Guidance Building America Climate-Specific Guidance 2014 Housing Innovation...

  16. Lead-Safe Housing Policy Guidance

    E-Print Network [OSTI]

    Lead-Safe Housing Policy Guidance #12;ACKNOWLEDGEMENTS This guidance was prepared by the Alliance Gumm. The Alliance thanks the Childhood Lead Poisoning Prevention Branch of the Centers for Disease..............................................................................................................................1 PART I Basic Lead-Safe Housing Standards

  17. Hybrid vehicle-centric route guidance

    E-Print Network [OSTI]

    Farver, Jennifer M. (Jennifer Margaret), 1976-

    2005-01-01T23:59:59.000Z

    This thesis proposes a hybrid route guidance system in which predictive guidance is generated in a centralized layer and revised in a reactive, decentralized layer that resides on-board the vehicle. This hybrid approach ...

  18. Work Experience Guidance for Managers

    E-Print Network [OSTI]

    Work Experience Guidance for Managers When approached with a request for work experience, managers. Any queries regarding CRB checks should be directed to your designated HR Manager. When a work any work, paid or unpaid: Before 7am or after 7pm For more than two hours on a school day or Sunday

  19. Guidance on site selection for

    E-Print Network [OSTI]

    harvestingbrash materialfollowingtimber harvestingto supply biomass for heat and power generation. A numberGuidance on site selection for brash removal Forest Research, May 2009 The Research Agency SELECTION FOR BRASH REMOVAL | Forest Research | May 09 #12;Brash Removal Background Interest is growingin

  20. Stump Harvesting: Interim Guidance on

    E-Print Network [OSTI]

    , including biomass for fossil fuel substitution. Forest harvesting residues are increasingly being used to supply biomass for heat and power generation in the UK and attention is now turning to the potentialStump Harvesting: Interim Guidance on Site Selection and Good Practice Forest Research, April 2009

  1. MINOR for Natural Resources Conservation Conserving Earth's biological diversity and safeguarding the benefits or "ecosystem services"

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    -fall even yrs) NRC 534 Forest Measurements (4cr-fall odd yrs) 2 NRC 540 Forest Resources Management (4cr Resources Policy & Administration (3cr-sprg) NRC 576 Water Resources Management (3cr-fall even yrs) NRC 590 Resources and Sustainability (3cr-sprg) NRC 597EL Environmental Law (3cr

  2. California Energy Commission GUIDANCE ON WASTE

    E-Print Network [OSTI]

    California Energy Commission GUIDANCE GUIDANCE ON WASTE MANAGEMENT PLANS FOR ENERGY EFFICIENCY) obtain waste management plans for each proposed project receiving funding under the Energy Efficiency of waste. The Energy Commission is providing the following guidance to assist recipients of EECBG Program

  3. OFFSHORE WIND FARMS Guidance note for Environmental

    E-Print Network [OSTI]

    OFFSHORE WIND FARMS Guidance note for Environmental Impact Assessment In respect of FEPA and CPA requirements Version 2 - June 2004 #12;Offshore Wind Farms: Guidance Note for Environmental Impact Assessment 2004 #12;Offshore Wind Farms: Guidance Note for Environmental Impact Assessment in Respect of FEPA

  4. BEST MANAGEMENT PRACTICES & GUIDANCE MANUAL: DESERT

    E-Print Network [OSTI]

    CALIFORNIA ENERGY COMMISSION BEST MANAGEMENT PRACTICES & GUIDANCE MANUAL: DESERT RENEWABLE ENERGY SOUTHWEST REGION #12;Draft BMPs and Guidance October 5, 2009 DISCLAIMER Best Management Practices & Guidance Eugenia Laychak Mignon Marks James W. Reede, Jr., Ed. D. Paul Richins Authors Roger Johnson Manager

  5. Evidence-Based Background Material Underlying Guidance for Federal...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Material Underlying Guidance for Federal Agencies in Implementing Strategic Sustainability Performance Plans Evidence-Based Background Material Underlying Guidance for...

  6. Guidance for Radiation Accident Management

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8,Dist.NewofGeothermal Heaton Armed- Deep VadoseGuidance

  7. POLICY GUIDANCE MEMORANDUM #31 - Procedures for Regularizing...

    Energy Savers [EERE]

    1 - Procedures for Regularizing Illegal Appointments POLICY GUIDANCE MEMORANDUM 31 - Procedures for Regularizing Illegal Appointments As part of the Department's ongoing effort to...

  8. Oral Presentation Guidance For ESCO Interviews

    Broader source: Energy.gov [DOE]

    Document provides guidance to enhance a Federal agency's effectiveness when interviewing a potential energy services company (ESCO) for an energy savings performance contract (ESPC) project.

  9. Council on Environmental Quality - Guidance for Environmental...

    Open Energy Info (EERE)

    for Environmental Assessments of Forest Health Projects Jump to: navigation, search OpenEI Reference LibraryAdd to library Memorandum: Council on Environmental Quality - Guidance...

  10. EPA - Guidance for Incorporating Environmental Justice Concerns...

    Open Energy Info (EERE)

    Environmental Justice Concerns in EPA's NEPA Compliance Analyses Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

  11. Guidance for Procurement Officials | Department of Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Acquisition Guidance Acquisition Guide Contracting for Support Services Department of Energy Acquisition System - A Guide for Executives Ethics in Procurement Lobbying Brochure...

  12. Energy Sector Cybersecurity Framework Implementation Guidance

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    JANUARY 2015 ENERGY SECTOR CYBERSECURITY FRAMEWORK IMPLEMENTATION GUIDANCE U.S. DEPARTMENT OF ENERGY OFFICE OF ELECTRICITY DELIVERY AND ENERGY RELIABILITY Energy Sector...

  13. Energy Intensity Baselining and Tracking Guidance

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Learn more at betterbuildings.energy.gov Energy Intensity Baselining and Tracking Guidance i Preface The U.S. Department of Energy's (DOE's) Better Buildings, Better Plants Program...

  14. Background information on RSO Test Deeming Guidance

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    information on RSO Test Deeming Guidance BPA has now had over two years of experience implementing Slice under the Regional Dialogue contract. Slice product customers are required...

  15. Guidance on Incorporating EPA's Pollution Prevention Strategy...

    Broader source: Energy.gov (indexed) [DOE]

    The guidance discusses the Environmental Protection Agency's definition of pollution prevention; how to incorporate pollution prevention into the EPA environmental review process...

  16. Participatory Carbon Monitoring: Operational Guidance for National...

    Open Energy Info (EERE)

    Participatory Carbon Monitoring: Operational Guidance for National REDD+ Carbon Accounting Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Participatory Carbon...

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    Broader source: Energy.gov (indexed) [DOE]

    Additional Guidance Regarding Application of Current Procedures for Testing Energy Consumption of Clothes Washers with Warm Rinse Cycles, Issued: June 30, 2010. Draft of DOE...

  18. Appendix F References | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    December. Washington, D.C. Available online at: http:www.nrc.govreading-rmdoc-collectionsnuregsstaffsr1811finalsr1811.html (accessed May 29, 2012) NRC 2006 Saricks,...

  19. Energy Department Issues Request For Proposal for Nuclear Regulatory...

    Office of Environmental Management (EM)

    Facilities procurement. The NRC Licensed Facilities contract is for managing Spent Nuclear Fuel (SNF) storage facilities and licenses under NRC regulations. The scope...

  20. albright generating station: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437 (NRC, 1996), (NRC, 1999); (2) the Environmental Report submitted by DEK; (3) consultation with Federal, State,...

  1. MICHAEL L. CORRADINI Wisconsin Distinguished Professor Nuclear Engineering and Engineering Physics, Chair, Engineering Physics Department

    E-Print Network [OSTI]

    Volpe, Francesco

    Laboratories, the AECL and CEC. He was Vice-Chairman of the 1985 NRC Steam Explosion Review Group and other NRC

  2. Directory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Document Name Sort items in descending order Object Created Object Last Modified NRC Concrete Meeting Busby NRC Concrete Meeting Busby LightWaterReactorSus...

  3. Data Protection Act 1998 Guidance for

    E-Print Network [OSTI]

    Mottram, Nigel

    Data Protection Act 1998 ­ Guidance for Staff/Students v1.0 v1.0 June 2012 Elaine Forbes, registered in Scotland, number SC015263 #12;Data Protection Act 1998 ­ Guidance for Staff/Students v1.0 Page .................................................................................................... 2 2. Personal Data in the University

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    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Steam Load Reduction Guidance Emergency Management Program v October 2014 Steam_Load_Reduction_Guidance_DSRDSR 1.0 PurposeandScope Utilities provides steam to the campus community for space heating, hot water in the steam distribution system or the Central Energy Plant, the preservation of building infrastructure

  5. A robust guidance system for aircraft approach and landing 

    E-Print Network [OSTI]

    Yu, Ren-Jye

    1999-01-01T23:59:59.000Z

    system (GS) to assist pilots during approach and landing. This GS consists of three modules: the Guidance Manager (GM), the Guidance Executive (GE) and the Guidance Display (GD). Modular design allows parallel development of these modules and the GS...

  6. Guidance on New Construction under an Energy Savings Performance...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

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  7. State Energy Program Fiscal Year 2006 Formula Grant Guidance

    Broader source: Energy.gov (indexed) [DOE]

    STATE ENERGY PROGRAM NOTICE 06-1 EFFECTIVE DATE: January 6, 2006 SUBJECT: PROGRAM YEAR 2006 STATE ENERGY PROGRAM FORMULA GRANT GUIDANCE PURPOSE To establish grant guidance and...

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    Broader source: Energy.gov (indexed) [DOE]

    STATE ENERGY PROGRAM FORMULA GRANT GUIDANCE PROGRAM YEAR 2007 STATE ENERGY PROGRAM NOTICE 07-01 EFFECTIVE DATE: April 3, 2007 PURPOSE To establish grant guidance and management...

  9. POLICY GUIDANCE MEMORANDUM #35 Procedures for Compliance with...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of Position POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of...

  10. POLICY GUIDANCE MEMORANDUM #09A Direct Hire Authority for Acquisition...

    Office of Environmental Management (EM)

    9A Direct Hire Authority for Acquisition Positions (Expired) POLICY GUIDANCE MEMORANDUM 09A Direct Hire Authority for Acquisition Positions (Expired) THIS GUIDANCE HAS EXPIRED...

  11. POLICY GUIDANCE MEMORANDUM #33 - Requirements for DOE Delegated...

    Energy Savers [EERE]

    3 - Requirements for DOE Delegated Examining Procedures POLICY GUIDANCE MEMORANDUM 33 - Requirements for DOE Delegated Examining Procedures The purpose of this guidance is to...

  12. POLICY GUIDANCE MEMORANDUM #38 EXCEPTION TO POLICY REGARDING...

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    POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES This has...

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    Energy Savers [EERE]

    4B Direct Hire Authority for Contract Specialist positions POLICY GUIDANCE MEMORANDUM 34B Direct Hire Authority for Contract Specialist positions Policy Guidance Memorandum 34B...

  14. POLICY GUIDANCE MEMORANDUM #02 Using Schedule A Hiring Authority...

    Energy Savers [EERE]

    2 Using Schedule A Hiring Authority for ARRA Positions (Expired) POLICY GUIDANCE MEMORANDUM 02 Using Schedule A Hiring Authority for ARRA Positions (Expired) THIS GUIDANCE HAS...

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    Energy Savers [EERE]

    3 Permanent and Nonpermanent Positions, Appointments, & CHRIS Codes POLICY GUIDANCE MEMORANDUM 23 Permanent and Nonpermanent Positions, Appointments, & CHRIS Codes DOE Guidance -...

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    Broader source: Energy.gov (indexed) [DOE]

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  17. POLICY GUIDANCE MEMORANDUM #12 Payment of Expenses for Professional...

    Energy Savers [EERE]

    POLICY GUIDANCE MEMORANDUM 12 Payment of Expenses for Professional Credentials POLICY GUIDANCE MEMORANDUM 12 Payment of Expenses for Professional Credentials Departmental...

  18. Energy Department Seeks Feedback on Draft Guidance for the Hydroelectr...

    Energy Savers [EERE]

    Feedback on Draft Guidance for the Hydroelectric Production Incentive Program Energy Department Seeks Feedback on Draft Guidance for the Hydroelectric Production Incentive Program...

  19. Federal Renewable Energy Guidance to EPACT 2005 | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Renewable Energy Guidance to EPACT 2005 Federal Renewable Energy Guidance to EPACT 2005 Presentation covers the agency renewable energy requirements for EPACT 2005 given at the...

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    Energy Savers [EERE]

    Habitat Evaluation: Guidance for the Review of Environmental Impact Assessment Documents Habitat Evaluation: Guidance for the Review of Environmental Impact Assessment Documents...

  1. BLM Manual 8270 - General Procedural Guidance for Paleontological...

    Open Energy Info (EERE)

    - General Procedural Guidance for Paleontological Resource Management Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - Guide...

  2. Energy Department Releases New Greenhouse Gas Reporting Guidance...

    Energy Savers [EERE]

    New Greenhouse Gas Reporting Guidance, Seeks Public Comment Energy Department Releases New Greenhouse Gas Reporting Guidance, Seeks Public Comment March 22, 2005 - 10:54am Addthis...

  3. Guidance for Energy Efficiency and Conservation Block Grant Grantees...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing Programs Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing...

  4. Microsoft Word - Final ALOHA Guidance Report Version May 24 2004...

    Broader source: Energy.gov (indexed) [DOE]

    Code Guidance ALOHA Computer Code Application Guidance for Documented Safety Analysis Final Report U.S. Department of Energy Office of Environment, Safety and Health...

  5. Energy Department Issues Tribal Renewable Energy Purchase Guidance...

    Energy Savers [EERE]

    Issues Tribal Renewable Energy Purchase Guidance and Project Development Resources Energy Department Issues Tribal Renewable Energy Purchase Guidance and Project Development...

  6. Technical Standards, ALOHA-Code Guidance- June 22, 2004

    Broader source: Energy.gov [DOE]

    DOE-EH-4.2.1.4-ALOHA-Code Guidance, ALOHA Computer Code Application Guidance for Documented Safety Analysis

  7. Treasury, Energy Announce Guidance for Tax Treatment of Smart...

    Office of Environmental Management (EM)

    Treasury, Energy Announce Guidance for Tax Treatment of Smart Grid Investment Grants Treasury, Energy Announce Guidance for Tax Treatment of Smart Grid Investment Grants March 10,...

  8. Guidance on New Construction under an Energy Savings Performance...

    Broader source: Energy.gov (indexed) [DOE]

    Guidance on New Construction under an Energy Savings Performance Contract November 2013 This document provides guidance on the limitations on the use of an energy savings...

  9. Vibrotactile Guidance for Wayfinding of Blind Walkers

    E-Print Network [OSTI]

    Manduchi, Roberto; Flores, German; Kurniawan, Sri; Morales, Lourdes; Martinson, Eric; Sisbot, Akin

    2015-01-01T23:59:59.000Z

    travel aid for the blind. Systems, Man, and Cybernetics,Guidance for Wayfinding of Blind Walkers G. Flores, S.the form of a belt for guiding blind walkers. This interface

  10. Guidance for Local Wind Energy Ordinances

    Broader source: Energy.gov [DOE]

    Note: The documents described in this summary were designed to provide guidance to local governments that wish to develop their own siting rules for wind turbines. While they were developed under...

  11. Moving Your Laboratory Safely Guidance Document

    E-Print Network [OSTI]

    Baker, Chris I.

    Moving Your Laboratory Safely Guidance Document Revised March 2010, Page 1 #12;Table of Contents­radiological 301-496-3457 Ergonomic evaluations 301-496-7990 Hazardous, solid and mixed waste management 301

  12. Program Year 2013 State Energy Program Formula Grant Guidance

    Broader source: Energy.gov [DOE]

    This document contains State Energy Program Formula grant guidance for 2013, effective April 16, 2013.

  13. Crescent Junction Disposal Site Diversion Channel Design, North Side Disposal Cell Sources of Data:

    E-Print Network [OSTI]

    unknown authors

    Checked b"t me-Kao a MName A e4719 lProblem Statement: " Design erosion protection for the north slope of the disposal cell to prevent detrimental erosion from surface water flows from upland area, consistent with the requirements of 40 CFR Part 192 and NRC guidance in NUREG 1623.

  14. Guidance Manual for K-12 SchoolsGuidance Manual for K-12 Schools prepared for

    E-Print Network [OSTI]

    Jia, Songtao

    Compliance and Best Management Practices prepared by: October 2006 Facilities O peration and Ma intenanceAreas .............................................................................................1-5 1.3 Best Management PracticesGuidance Manual for K-12 SchoolsGuidance Manual for K-12 Schools prepared for: Environmental

  15. Safety of magnetic fusion facilities: Guidance

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities.

  16. Requirements for the MINOR in Environmental Science Five courses required. Total credits = minimum of 15

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    515 Microbiology of Soil NRC 528 Forest & Wetland Hydrology NRC 540 Forest Management NRC 564 Wildlife Science & Management NRC 578 Watershed Science & Mgt Environmental Policy & Land Use ECON 308 Environmental Economics ENVIRDES 553 Resource Policy and Planning ENVIRDES 574 City Planning ENVIRDES 575

  17. General Guidance on NEPA | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral Guidance on NEPA General Guidance on NEPA

  18. General Privacy Act Guidance | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral Guidance on NEPA General Guidance on NEPAPrivacy

  19. Energy.gov Article Guidance | Department of Energy

    Energy Savers [EERE]

    About Energy.gov Web Policies Energy.gov Article Guidance Energy.gov Article Guidance Energy.gov is managed by a team of digital communications specialists in the Office of...

  20. Guidance on NEPA Review for Corrective Actions under the Resource...

    Energy Savers [EERE]

    and Recovery Act (RCRA) Guidance on NEPA Review for Corrective Actions under the Resource Conservation and Recovery Act (RCRA) This guidance results from the work of a Task Team...

  1. Guidance for Environmental Background Analysis Volume III: Groundwater

    E-Print Network [OSTI]

    Guidance for Environmental Background Analysis Volume III: Groundwater Prepared for: Naval This guidance document provides instructions for characterizing groundwater background conditions and comparing datasets representing groundwater impacted by an actual or potential chemical release to appropriate

  2. Green Impact Universities and Colleges: EXCELLENCE guidance

    E-Print Network [OSTI]

    Harman, Neal.A.

    Green Impact Universities and Colleges: EXCELLENCE guidance 1.0 Introduction Green Impact progressing through institutionally bespoke workbooks to green their departments and campuses, the need, rather than reaching a pre-set endpoint, so we are developing Green Impact to ensure our participants

  3. Guidance for performing site inspections under CERCLA

    SciTech Connect (OSTI)

    Not Available

    1992-09-01T23:59:59.000Z

    This guidance presents EPA`s site inspection (SI) strategy. The strategy discusses procedural guidelines to investigate potential Superfund (CERCLA) sites for evaluation pursuant to the Hazard Ranking System (HRS), revised in accordance with the Superfund Amendments and Reauthorization Act of 1986. The HRS is the primary means by which EPA evaluates sites for superfund`s National Priorities List (NPL).

  4. Forestry Commission Wales Guidance on rental levels for Hydro Power

    E-Print Network [OSTI]

    Forestry Commission Wales Guidance on rental levels for Hydro Power Guidance on rental levels for hydro power projects Tel: 02920 475961 Email: hydrowales@forestry.gsi.gov.uk Version 1.0 Mike Pitcher 17th December, 2012 #12;2 Guidance on rental levels for hydro power |Version 1.0 | Mike Pitcher 17

  5. Guidance on peat soils 1 | Peat | Helen Cariss

    E-Print Network [OSTI]

    Guidance on peat soils 1 | Peat | Helen Cariss Forestry and deep peat Purpose This policy guidance on forestry and deep peat acts as the country level guidance for FCW. It applies to regulatory functions: conserving and enhancing biodiversity climate change mitigation maintaining the peat and soil resource

  6. Commissioning Guidance for ESPCs | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'sEnergyTexas1.Space Data CorporationPast ProjectsGuidance for ESPCs

  7. GC GUIDANCE ON ELECTRIC VEHICLE RECHARGING STATIONS

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2: FinalOffers3.pdf0-45.pdf0 Budget Fossil EnergyFull Text ManagementDOE REALGC GUIDANCE

  8. Guidance for Planning Exercises | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral GuidanceEnergy LaunchingGrowingValidations

  9. Guidance, Reports, and Documents | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral GuidanceEnergyServices »Department ofSites

  10. Policy and Guidance | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122Commercial602 1,39732onMakeEducationRemediationDepartmentaD,2014RetaliationGuidance

  11. All NEPA Guidance | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you0 ARRA Newsletters 20103-03Energy AdvancedJudgeAlice OrrellGuidance &

  12. Site Transition Plan Guidance | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOriginEducationVideo »UsageSecretary of EnergyFocus GroupSherrellHanfordPlan Guidance Site

  13. Guidance for Deployment of Mobile Technologies for Nuclear Power...

    Energy Savers [EERE]

    Workers This report is a guidance document prepared for the benefit of commercial nuclear power plants' (NPPs) supporting organizations and personnel who are considering or...

  14. Guidance for Energy Efficiency and Conservation Block Grant Grantees...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Grant Grantees on Qualified Energy Conservation Bonds and New Clean Renewable Energy Bonds Guidance for Energy Efficiency and Conservation Block Grant Grantees on Qualified Energy...

  15. GUIDANCE FOR ENERGY EFFICIENCY AND CONSERVATION BLOCK GRANT RECIPIENTS...

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    This document provides guidance for energy efficiency and block grant recipients on closeout procedures for non-state energy office recipients. eecbgcloseoutguidance10-11-11.pdf...

  16. Enforcement Guidance Supplement 00-02: Price-Anderson Amendment...

    Office of Environmental Management (EM)

    enforcement interaction (i.e., low-reporters); and Establish a mechanism for the feedback of program implementation lessons-learned into existing EH-Enforcement guidance....

  17. Guidance Regarding Actions That May Proceed During the NEPA Process...

    Energy Savers [EERE]

    gives examples of the types of actions that may proceed as interim actions, describes case studies, and outlines the steps in the EIS process for interim actions. Guidance...

  18. POLICY GUIDANCE MEMORANDUM #18 Advertisement of Federal Career...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    8 Advertisement of Federal Career Intern Program Employment Opps (Expired) POLICY GUIDANCE MEMORANDUM 18 Advertisement of Federal Career Intern Program Employment Opps (Expired)...

  19. POLICY GUIDANCE MEMORANDUM #32A Schedule A Appointments of Persons...

    Energy Savers [EERE]

    A Appointments of Persons with Disabilities and Appointments for Disabled Veterans POLICY GUIDANCE MEMORANDUM 32A Schedule A Appointments of Persons with Disabilities and...

  20. POLICY GUIDANCE MEMORANDUM #29 Employment Offers Letters Performance...

    Energy Savers [EERE]

    9 Employment Offers Letters Performance Management POLICY GUIDANCE MEMORANDUM 29 Employment Offers Letters Performance Management This memorandum is to ensure compliance with DOE...

  1. Policy Guidance Memorandum #37 Procedures for Excepted Service...

    Energy Savers [EERE]

    7 Procedures for Excepted Service Exceptionally Well Qualified (EWQ) Appointments Policy Guidance Memorandum 37 Procedures for Excepted Service Exceptionally Well Qualified (EWQ)...

  2. POLICY GUIDANCE MEMORANDUM #28 Requirements for Non-Competitive...

    Energy Savers [EERE]

    for Non-Competitive Reassignments into Supervisory andor Managerial Positions POLICY GUIDANCE MEMORANDUM 28 Requirements for Non-Competitive Reassignments into...

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    Broader source: Energy.gov (indexed) [DOE]

    Efficiency and Conservation Block Grant (EECBG) Program Guidance 10-011 dealing with formula grants. eecbgrecoveryactprogramguidance10-011.pdf More Documents & Publications...

  4. Enforcement Guidance Supplement 01-01, Nuclear Weapon Program...

    Office of Environmental Management (EM)

    OF ENFORCEMENT AND INVESTIGATION SUBJECT: Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Section 1.3 of the Operational Procedures for...

  5. Greenhouse Gas Guidance and Reporting | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and Reporting Greenhouse Gas Guidance and Reporting Federal agencies are required to inventory and manage their greenhouse gas (GHG) emissions to meet Federal goals and mitigate...

  6. POLICY GUIDANCE MEMORANDUM #27 Certification Program on Prohibited...

    Office of Environmental Management (EM)

    7 Certification Program on Prohibited Personnel Practices and Whistleblower Protections POLICY GUIDANCE MEMORANDUM 27 Certification Program on Prohibited Personnel Practices and...

  7. Memorandum Guidance for the Preparation of Department of Energy...

    Energy Savers [EERE]

    serves as the primary mechanism for documenting compliance with DOE's requirements for radiation protection of the public and environment. Memorandum Guidance for the...

  8. Office of Personnel Management (OPM) Guidance on Diversity and...

    Broader source: Energy.gov (indexed) [DOE]

    and Inclusion Agency Specific Strategic Plan Guidance.pdf OPM Hispanic Employment Data Report 2011.pdf Model Strategies for Recruitment and Hiring of People with...

  9. CEQ Issues Revised Draft Guidance on Consideration of Greenhouse...

    Broader source: Energy.gov (indexed) [DOE]

    revised draft guidance on consideration of greenhouse gas (GHG) emissions and the effects of climate change in National Environmental Policy Act (NEPA) reviews on December 18,...

  10. Energy Department Seeks Additional Feedback on Draft Guidance...

    Broader source: Energy.gov (indexed) [DOE]

    implementation of Section 242 of the Energy Policy Act of 2005, the "Hydroelectric Production Incentive Program." Public comments on the initial Section 242 Draft Guidance were...

  11. Technical background document for soil screening guidance. Review draft

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    The document provides the technical background behind the development of the November 1994 Soil Screening Guidance for Superfund. These documents define the Soil Screening framework, a suite of methodologies for developing Soil Screening Levels (SSLs) for 107 chemicals commonly found at Superfund sites. The document is an updated version of the background document developed in support of the September 30, 1993, draft SSL guidance (PB93-963508). The document and the Guidance is available for public comment and is currently undergoing extensive peer review. Because the guidance is still under review, it and this document should not be used until they are finalized following this rigorous technical review and public comment.

  12. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    Fuel Cell Technologies Publication and Product Library (EERE)

    This guidance document provides information on safety requirements for hydrogen and fuel cell projects funded by the U.S. Department of Energy Fuel Cell Technologies Program.

  13. axon guidance factors: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    16 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  14. anteroposterior axon guidance: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    14 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  15. axon guidance events: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    14 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  16. axon growth guidance: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    18 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  17. axon guidance regulators: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    19 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  18. axon guidance defective: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    14 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  19. POLICY GUIDANCE MEMORANDUM #30 Job Opportunity Announcement Template...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Job Opportunity Announcement templates throughout the Deparment to improve Hiring Reform Initiatives. POLICY GUIDANCE MEMORANDUM 30 Job Opportunity Announcement Template...

  20. DOE Audit Guidance for For-Profit Financial Assistance Awards...

    Office of Environmental Management (EM)

    I) April 2012 1 I. GENERAL AUDIT PROGRAM A. PURPOSE AND APPLICABILITY The following General Audit Program provides requirements and guidance for independent audit organizations in...

  1. Qualified Energy Conservation Bond (QECB) Update: New Guidance...

    Broader source: Energy.gov (indexed) [DOE]

    Lawrence Berkeley National Laboratory Qualified Energy Conservation Bond (QECB) Update: New Guidance from the U.S. Department of Treasury and the Internal Revenue Service...

  2. Guidance for Energy Efficiency and Conservation Block Grant Recipients...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Guidelines Guidance for Energy Efficiency and Conservation Block Grant Program grantees on planning and conducting program evaluations on Recovery Act funded EECBG programs...

  3. Adaptation to Climate Variability and Change: A Guidance Manual...

    Open Energy Info (EERE)

    to Climate Variability and Change: A Guidance Manual for Development Planning Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Adaptation to Climate Variability and...

  4. POLICY GUIDANCE MEMORANDUM #08 DOE Fair Labor Standards Act ...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    8 DOE Fair Labor Standards Act (FLSA) ExemptNon-Exempt Status Determination POLICY GUIDANCE MEMORANDUM 08 DOE Fair Labor Standards Act (FLSA) ExemptNon-Exempt Status...

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    Energy Savers [EERE]

    on Establishing, Applying, and Revising Categorical Exclusions Under the National Environmental Policy Act Guidance for Federal Departments and Agencies on Establishing,...

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    Office of Environmental Management (EM)

    1A Approval Process for Dual Compensation Waivers for Reemployed Annuitants POLICY GUIDANCE MEMORANDUM 11A Approval Process for Dual Compensation Waivers for Reemployed Annuitants...

  7. Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

    SciTech Connect (OSTI)

    O'Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; and Bzostek, J.

    2009-09-30T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M&T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M&Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M&Ts. The M&Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M&Ts for each trend, and (2) whether M&Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M&T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

  8. Cask system design guidance for robotic handling

    SciTech Connect (OSTI)

    Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

    1990-10-01T23:59:59.000Z

    Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

  9. Environmental Guidance Program Reference Book: American Indian Religious Freedom Act

    SciTech Connect (OSTI)

    Not Available

    1987-11-01T23:59:59.000Z

    This Reference Book contains a copy of the American Indian Religious Freedom Act and guidance for DOE compliance with the statute. The document is provided to DOE and contractor staff for informational purposes only and should not be interpreted as legal guidance. Updates that include important new requirements will be provided periodically.

  10. Annex 2 Risk Guidance Science Programme Office Project Management

    E-Print Network [OSTI]

    1 Annex 2 ­ Risk Guidance Science Programme Office Project Management Guidance on Risk Management and technical performance. However, with appropriate procedures, risks can be managed and in so doing, present as bad things happening. The objective of risk management is to identify, assess, reduce, accept

  11. Annex 2 Risk Management Guidance and Template SPO Project Management

    E-Print Network [OSTI]

    1 Annex 2 ­ Risk Management Guidance and Template SPO Project Management Guidance on Risk Management Introduction Risk is any action or event that affects a project's ability to achieve its on cost, schedule and technical performance. However, with appropriate procedures, risks can be managed

  12. Manure Storage Winter Capacity Planning Level Guidance January 1, 2013

    E-Print Network [OSTI]

    Guiltinan, Mark

    1 Manure Storage Winter Capacity Planning Level Guidance January 1, 2013 The guidance outlined in this document is to be used to determine the Manure Storage Winter Capacity Planning Level for CAFO operations must be documented in the NMP Standard Format. For determining the manure storage winter capacity

  13. Guidance on Microbial Contamination in Previously Flooded Outdoor Areas

    E-Print Network [OSTI]

    Guidance on Microbial Contamination in Previously Flooded Outdoor Areas Environmental Health Buford Highway NE (F-60) Atlanta, GA 30341 March 2011 #12;2 Guidance on Microbial Contamination in Previously Flooded Outdoor Areas Problem Statement Microbial contamination--both bacterial and viral

  14. Guidance for the Quality Assurance of Fire Protection Systems

    Broader source: Energy.gov [DOE]

    This quality assurance document is intended to provide guidance for the DOE fire protection community in the continuing effort to ensure the reliability of fire protection systems. This guidance document applies the concepts of DOE Order 5700.6C, Quality Assurance, to the management of fire protection systems.

  15. An Adaptive Vehicle Guidance System instigated from Ant Colony Behavior

    E-Print Network [OSTI]

    Casillas Barranquero, Jorge

    safety [4], a minimization of the energy consumption, and others. A Vehicle Guidance System (VGS) assistsAn Adaptive Vehicle Guidance System instigated from Ant Colony Behavior Habib M. Kammoun, Ilhem of the high dynamicity of traffic flow and the polynomial increase in the number of vehicles on road networks

  16. Washington and Lee University Guidance on Information Security

    E-Print Network [OSTI]

    Marsh, David

    Washington and Lee University Guidance on Information Security This guidance addresses common issues that have come up during information security discussions with offices and departments across, Information Security Program Committee Chair (sdittman@wlu.edu) or Dean Tallman, Information Security Officer

  17. Climate Change Guidance: A Pragmatic Approach to Client

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    10/21/11 Climate Change Guidance: A Pragmatic Approach to Client Needs Climate, Water and Ecosystems- Shaping the Great Plains October 13, 2011 #12;10/21/11 Climate Change Guidance: A Pragmatic Approach to Client NeedsClimate Science ­ 2011 ·Yes, the climate is changing. ·Climate science is changing

  18. IT Policy, Procedures and Guidance University College, Oxford

    E-Print Network [OSTI]

    Henderson, Gideon

    IT Policy, Procedures and Guidance University College, Oxford Patrick Baird IT and Web Fellow Andy Hamilton IT Manager Helene Augar College Registrar #12;Summary This policy and guidance document. Transgressions (Junior Members) 14 14. Flexible Hours and Working at Home (Staff) 15 15. Revisions to this Policy

  19. Technical guidance for siting criteria development

    SciTech Connect (OSTI)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01T23:59:59.000Z

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  20. D & D screening risk evaluation guidance

    SciTech Connect (OSTI)

    Robers, S.K.; Golden, K.M.; Wollert, D.A.

    1995-09-01T23:59:59.000Z

    The Screening Risk Evaluation (SRE) guidance document is a set of guidelines provided for the uniform implementation of SREs performed on decontamination and decommissioning (D&D) facilities. Although this method has been developed for D&D facilities, it can be used for transition (EM-60) facilities as well. The SRE guidance produces screening risk scores reflecting levels of risk through the use of risk ranking indices. Five types of possible risk are calculated from the SRE: current releases, worker exposures, future releases, physical hazards, and criticality. The Current Release Index (CRI) calculates the current risk to human health and the environment, exterior to the building, from ongoing or probable releases within a one-year time period. The Worker Exposure Index (WEI) calculates the current risk to workers, occupants and visitors inside contaminated D&D facilities due to contaminant exposure. The Future Release Index (FRI) calculates the hypothetical risk of future releases of contaminants, after one year, to human health and the environment. The Physical Hazards Index (PHI) calculates the risks to human health due to factors other than that of contaminants. Criticality is approached as a modifying factor to the entire SRE, due to the fact that criticality issues are strictly regulated under DOE. Screening risk results will be tabulated in matrix form, and Total Risk will be calculated (weighted equation) to produce a score on which to base early action recommendations. Other recommendations from the screening risk scores will be made based either on individual index scores or from reweighted Total Risk calculations. All recommendations based on the SRE will be made based on a combination of screening risk scores, decision drivers, and other considerations, as determined on a project-by-project basis.

  1. Academic Guidance 3b 2013-2014 Student Plagiarism Guide -Page 1 of 8 ACADEMIC GUIDANCE 3b

    E-Print Network [OSTI]

    Jones, Graeme A.

    are conducting your studies with integrity and adopting the principles of good practice that are required in HEIsAcademic Guidance 3b 2013-2014 Student Plagiarism Guide - Page 1 of 8 ACADEMIC GUIDANCE 3b: PLAGIARISM: A Student Guide 2013-2014 This document is available in hard copy and on the University intranet

  2. Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

    SciTech Connect (OSTI)

    O, J.M.; Higgins, J.; Stephen Fleger - NRC

    2011-09-19T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

  3. EECBG Program Notice 09-002B - Guidance for Energy Efficiency...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    B - Guidance for Energy Efficiency and Conservation Block Grant Grantees on financing programs EECBG Program Notice 09-002B - Guidance for Energy Efficiency and Conservation Block...

  4. SEP Program Notice 10-008D: Guidance for State Energy Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    D: Guidance for State Energy Program Grantees on Financing Programs SEP Program Notice 10-008D: Guidance for State Energy Program Grantees on Financing Programs This document...

  5. SEP Program Notice 10-008B - Guidance for State Energy Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    B - Guidance for State Energy Program Grantees on Financing Programs SEP Program Notice 10-008B - Guidance for State Energy Program Grantees on Financing Programs This document...

  6. National Environmenal Policy Act Contracting Reform Guidance: Phase 1

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The NEPA Contracting Quality Improvement Team identified several contracting improvements to reduce the cost and time for the NEPA process. The team`s February 1995 report recommended a series of steps to achieve the improvements, including issuance of contracting guidance. The guidance will be issued in three phases. This Phase I guidance implements the team`s short-term recommendations. It provides model statements of work and a sample schedule of contractor deliverables, establishes a pilot program for evaluating performance of NEPA support contractors, and describes information resources available on the DOE NEPA Web.

  7. Guidance on Dependence Assessment in SPAR-H

    SciTech Connect (OSTI)

    April M. Whaley

    2012-06-01T23:59:59.000Z

    As part of the effort to develop the SPAR-H user guidance, particular attention was paid to the assessment of dependence in order to address user questions about proper application of dependence. This paper presents a discussion of dependence from a psychological perspective and provides guidance on applying this information during the qualitative analysis of dependence to ensure more realistic and appropriate dependence assessments with the SPAR-H method. While this guidance was developed with SPAR-H in mind, it may be informative to other human reliability analysis methods that also use a THERP-based dependence approach, particularly if applied at the human failure event level.

  8. Management of radioactive material safety programs at medical facilities. Final report

    SciTech Connect (OSTI)

    Camper, L.W.; Schlueter, J.; Woods, S. [and others

    1997-05-01T23:59:59.000Z

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

  9. Guidelines for inservice testing at nuclear power plants

    SciTech Connect (OSTI)

    Campbell, P.

    1995-04-01T23:59:59.000Z

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

  10. Guidance manual for conducting technology demonstration activities

    SciTech Connect (OSTI)

    Jolley, R.L.; Morris, M.I.; Singh, S.P.N.

    1991-12-01T23:59:59.000Z

    This demonstration guidance manual has been prepared to assist Martin Marietta Energy Systems, Inc. (Energy Systems), staff in conducting demonstrations. It is prepared in checklist style to facilitate its use and assumes that Energy Systems personnel have project management responsibility. In addition to a detailed step-by-step listing of procedural considerations, a general checklist, logic flow diagram, and several examples of necessary plans are included to assist the user in developing an understanding of the many complex activities required to manage technology demonstrations. Demonstrations are pilot-scale applications of often innovative technologies to determine the commercial viability of the technologies to perform their designed function. Demonstrations are generally conducted on well-defined problems for which existing technologies or processes are less than satisfactory in terms of effectiveness, cost, and/or regulatory compliance. Critically important issues in demonstration management include, but are not limited to, such factors as communications with line and matrix management and with the US Department of Energy (DOE) and Energy Systems staff responsible for management oversight, budgetary and schedule requirements, regulatory compliance, and safety.

  11. Transmission line environmental assessment guidance document

    SciTech Connect (OSTI)

    Jackson, J.; Pentecost, E.; Muzzarelli, J.

    1994-01-01T23:59:59.000Z

    Since 1939, U.S. utility companies have been required to obtain a Presidential Permit to construct electric transmission lines that cross a U.S. border and connect with a foreign utility. The purpose of this document is to provide Presidential Permit applicants with two types of guidance: (1) on the type of environmental and project descriptive information needed to assess the potential impacts of the proposed and alternative actions and (2) on compliance with applicable federal and state regulations. The main three chapters present information on the purpose and content of this document (Chapter 1); legislative, regulatory, and consultation requirements for transmission line interconnect projects (Chapter 2); and identification of basic transmission system design parameters and environmental data requirements for analysis of potential impacts of the proposed action (Chapter 3). Chapter 3 also includes information on possible techniques or measures to mitigate impacts. Appendix A presents an overview of NEPA requirements and DOE`s implementing procedures. Appendix B summarizes information on legislation that may be applicable to transmission line projects proposed in Presidential Permit applications.

  12. Using the NEPA Requirements and Guidance - Search Index

    Office of Environmental Management (EM)

    file, right click on it, select "Extract all", extract it to any location on your computer or USB drive. 2. Locate and Open the extracted folder "NEPA Requirements and Guidance...

  13. Cumulative Effects Guidance 2007 MnDOT Environmental

    E-Print Network [OSTI]

    Minnesota, University of

    relevant for actions requiring an environmental impact statement § Analysis for projects processed as EACumulative Effects Guidance 2007 MnDOT Environmental Stewardship & Streamlining Workshop Presented by Dave Gamble Federal Highway Administration Resource Center Environmental Technical Service Team #12

  14. Retooling and Manufacturing Program Guidance Using State Energy...

    Broader source: Energy.gov (indexed) [DOE]

    Revolving Loan Funds and Loan Loss Reserves Program Year 2008 State Energy Program Formula SEP Program Notice 10-008B - Guidance for State Energy Program Grantees on Financing...

  15. Energy Department Releases New Guidance for Strengthening Cybersecurit...

    Broader source: Energy.gov (indexed) [DOE]

    News Media Contact (202) 586-4940 WASHINGTON - As part of the Obama Administration's commitment to a strong and secure power grid, the Energy Department today released new guidance...

  16. CEQ Extends Comment Period on Revised Draft Guidance on Consideration...

    Broader source: Energy.gov (indexed) [DOE]

    comment period on its revised draft guidance on consideration of greenhouse gas (GHG) emissions and the effects of climate change in NEPA reviews. The comment period now ends on...

  17. Guidance to Completing the Self-Directed RBSM Interview Form

    Broader source: Energy.gov [DOE]

    This guidance package is meant to be a companion piece for the self-directed RBSM Interview Form and describes the basic mechanics of the RBSM process. Examples are provided to clarify the review...

  18. axon guidance receptors: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Index 1 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  19. axon guidance molecule: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    J. 15 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  20. axon guidance gene: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Index 1 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  1. axon guidance molecules: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    J. 15 The axon guidance receptor gene ROBO1 is a candidate gene for developmental dyslexia CiteSeer Summary: Dyslexia, or specific reading disability, is the most common...

  2. Toxic Chemical Release Inventory reporting ``Qs & As``. Environmental Guidance

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    This document offers guidance on toxic chemical release inventory reporting, pursuant to Section 313 of the Emergency Planning and Community Right-to-Know Act (EPCRA) at DOE sites.

  3. FEMP (Federal Energy Management Program) presents alternative financing guidance memoranda

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    Utility financing of energy efficient measures becomes easier to accomplish with the two new alternative financing guidance memoranda, released April 17, 1998, that address the use of utility incentives for Federal facilities. The memoranda have been approved by the Alternative Financing Guidance Committee on the Interagency Energy Management Task Force. The memoranda include: (1) Policy Statement No. 001: Authority to Sole Source Utility Service Contracts as Referenced in Section 152 of the Energy Policy Act (EPACT) of 1992; and (2) Policy Statement No. 002: Congressional Notification for Utility Projects Under the Authority of Section 152 of the Energy Policy Act (EPACT) of 1992. The purpose for developing the financing memoranda was to address specific issues within current Federal procurement regulations that require clarification or guidance. This new guidance will allow for increased use of utility incentives as a means of financing energy efficient and life cycle cost-effective projects in Federal facilities.

  4. SUBJECT: Guidance on the Major Source Determination for Certain Hazardous Air FROM: John S. Seitz, Director

    E-Print Network [OSTI]

    . The following compounds are the POM listed in the guidance: Naphthalene Acenaphthene Acenaphthylene Fluorene

  5. Route guidance information for elderly passengers: route naming methods

    E-Print Network [OSTI]

    Higgins, Laura Lynne

    1993-01-01T23:59:59.000Z

    ROUTE GUIDANCE INFORMATION FOR ELDERLY PASSENGERS: ROUTE NAMING METHODS A Thesis by LAURA LYNNE HIGGINS Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER... OF SCIENCE December 1993 Major Subject: Industrial Engineering ROUTE GUIDANCE INFORMATION FOR ELDERLY BUS PASSENGERS: ROUTE NAMING METHODS A Thesis by LAURA LYNNE HIGGINS Submitted to Texas A&M University in partial fulfillment of the requirements...

  6. Report on Lessons Learned from the NP 2010 Early Site Permit Program FINAL REPORT

    SciTech Connect (OSTI)

    none,

    2008-03-26T23:59:59.000Z

    This report provides a summary of lessons learned from the demonstration of the licensing process for three Early Site Permit (ESP) applications supported as part of the Department of Energy’s (DOE) Nuclear Power 2010 (NP 2010) program. The ESP process was established by the Nuclear Regulatory Commission (NRC) to enable completion of the site evaluation component of nuclear power plant licensing under 10 CFR Part 52 before a utility makes a decision to build a plant. Early Site Permits are valid for 10 to 20 years and can be renewed for an additional 10 to 20 years. NRC review of an ESP application addresses site safety issues, environmental protection issues, and plans for coping with emergencies. Successful completion of the ESP process will establish that a site is suitable for possible future construction and operation of a nuclear power plant. Most importantly, an ESP resolves significant site-related safety and environmental issues early in the decision process and helps achieve acceptance by the public. DOE competitively selected Dominion Nuclear Energy North Anna, LLC (Dominion); System Energy Resources, Inc. (an Entergy subsidiary); and Exelon Generation Company, LLC (Exelon) in 2002 to demonstrate the ESP process and provided cost-shared support through the NP 2010 program. Dominion pursued an ESP for the North Anna site in Virginia; System Energy Resources, Inc. pursued an ESP for the Grand Gulf site in Mississippi; and Exelon pursued an ESP for the Clinton site in Illinois. After successfully demonstrating the process, the NRC issued an ESP for Clinton on March 17, 2007; Grand Gulf on April 5, 2007; and North Anna on November 27, 2007. As with all successful projects, there are lessons to be learned from the NP 2010 early site permitting demonstration that can help improve future implementation guidance documents and regulatory review standards. In general, these lessons pertain to the effectiveness of the regulatory process, experience related to guidance for developing and reviewing ESP applications, issues involving ESP plant parameters, and suggestions for future ESP applicants. The development, submittal, and issuance of these first ESPs under DOE’s NP 2010 program started the momentum to exercise NRC’s new 10 CFR Part 52 licensing process. Several key questions that define critical issues regarding the effectiveness of regulations pertaining to ESPs have been identified and summarized in this report. However, the final resolution of whether the ESP component of the Part 52 process significantly contributes to the predictability in nuclear power plant licensing requires more experience and time, such as the completion of the ongoing combined Construction and Operating License (COL) process for the North Anna and Grand Gulf sites. The three ESP project participants prepared and submitted to DOE lessons learned reports from their experience in developing, submitting, and receiving an ESP. This document summarizes these reports, which are appended hereto. The Nuclear Energy Institute (http://www.nei.org/) and NRC (http://www.nrc.gov/) have also prepared reports regarding their perspectives on lessons learned during the ESP process. Their documents can be accessed on their respective web sites. Following is a summary of the lessons learned from the NP 2010 ESP projects. Effectiveness of the ESP Process: In general, the ESP process is expected (subject to demonstration of the ESP finality provisions in the North Anna and Grand Gulf ESPs) to provide high value for applicants as a site banking and risk mitigation strategy. However, several aspects of the initial process, such as NRC hearings and determining an acceptable approach to the NRC’s Emergency Planning requirements, proved challenging for the applicants. Project Execution: Initial regulatory and industry guidance for planning and executing an ESP application program proved to be insufficient to address NRC’s document review expectations. However, continuous communication between NRC and the applicants helped establish an acceptable framework

  7. DIMACS Center Rutgers University

    E-Print Network [OSTI]

    Hopkins University Andrew Patrick, NRC Canada Norman Sadeh, Carnegie Mellon University Working Group University Mark Ackerman, University of Michigan Fabian Monrose, Johns Hopkins University Andrew Patrick, NRC Canada Norman Sadeh, Carnegie Mellon University Workshop: Cryptography: Theory Meets Practice Dates

  8. MARSAME Appendix B B. SOURCES OF BACKGROUND RADIOACTIVITY

    E-Print Network [OSTI]

    : · The Nuclear Regulatory Commission (NRC) provides information concerning background radioactivity in Background as a Residual Radioactivity Criterion for Decommissioning NUREG-1501 (NRC 1994). · The United Nations Scientific

  9. UnitedStates EnvironmentalProtection

    E-Print Network [OSTI]

    ),theDOEOfficeofEnvironmentalRes- toration and WasteManagement(EM),and the NuclearRegulatoryCommission(NRC)Officeof Nuclear radioactivematerialsandsitesin theNRC'sSite Decommissioning Management Program (SDMP). Contents of Report Thereport includesan

  10. P&RA CoP TE Mtg Attendees List _2014-12-23.xlsx

    Office of Environmental Management (EM)

    AgencyCompany Affliation 1 George Alexander NRC 2 Alaa Aly INTERA 3 Bob Andrews INTERA 4 Cynthia Barr NRC 5 Debbie Barr DOE LM 6 Craig Benson University of Wisconsin-Madison 7...

  11. US Energy Sector Vulnerabilities to Climate Change

    Broader source: Energy.gov (indexed) [DOE]

    docsML1117ML11174A137.pdf. USNRC. 2012. "Power Reactor Status Reports for 2012." NRC Library. http:www.nrc.govreading-rmdoc- collectionsevent-statusreactor-status2012...

  12. U.S. Department Of Energy Commends Industry Consortia for Making...

    Office of Environmental Management (EM)

    (NRC). This application marks the second to the NRC in nearly 30 years to build a new nuclear reactor. Specifically, TVA's application seeks approval to build and operate two...

  13. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    ABBREVIATIONS AAB Accident Analysis Branch (NRC) ApplicationF, Nischan, US NRC. Accident Analysis Branch, U. S. Nuclear2. L 2 is placed in the Accident Analysis Branch (AAB); with

  14. Summary of comments received on staff draft proposed rule on radiological criteria for decommissioning

    SciTech Connect (OSTI)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C. [Advanced Systems Technology, Inc., Rockville, MD (United States)

    1994-08-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC licensed facilities. The NRC obtained comments on the scope, issues, and approaches through a series of workshops (57 FR 58727), Generic Environmental Impact Statement (GEIS) scoping meetings (58 FR 33570), a dedicated electronic bulletin board system (58 FR 37760), and written submissions. A summary of workshop and scope-meeting comments was published as NUREG/CR-6156. On February 2, 1994, the Commission published in the Federal Register (59 FR 4868) a notice that the NRC staff had prepared a ``staff draft`` proposed rule on radiological criteria for decommissioning. Copies of the staff draft were distributed to the Agreement States, participants in the earlier meetings, and other interested parties for comment. This report summarizes the comments identified from the 96 docketed letters received on the staff draft. No analysis or response is included in this report. The comments reflect a broad spectrum of viewpoints. Two subjects on which the commenters were in general agreement were (1) that the enhanced participatory rulemaking should proceed, and (2) that the forthcoming GEIS and guidance documents are needed for better understanding of the draft rule.

  15. CONTAIN independent peer review

    SciTech Connect (OSTI)

    Boyack, B.E. [Los Alamos National Lab., NM (United States); Corradini, M.L. [Univ. of Wisconsin, Madison, WI (United States). Nuclear Engineering Dept.; Denning, R.S. [Battelle Memorial Inst., Columbus, OH (United States); Khatib-Rahbar, M. [Energy Research Inc., Rockville, MD (United States); Loyalka, S.K. [Univ. of Missouri, Columbia, MO (United States); Smith, P.N. [AEA Technology, Dorchester (United Kingdom). Winfrith Technology Center

    1995-01-01T23:59:59.000Z

    The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code`s targeted applications include support for containment-related experimental programs, light water and advanced light water reactor plant analysis, and analytical support for resolution of specific technical issues such as direct containment heating. The NRC decided that a broad technical review of the code should be performed by technical experts to determine its overall technical adequacy. For this purpose, a six-member CONTAIN Peer Review Committee was organized and a peer review as conducted. While the review was in progress, the NRC issued a draft ``Revised Severe Accident Code Strategy`` that incorporated revised design objectives and targeted applications for the CONTAIN code. The committee continued its effort to develop findings relative to the original NRC statement of design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications were considered by the Committee in assigning priorities to the Committee`s recommendations. The Committee determined some improvements are warranted and provided recommendations in five code-related areas: (1) documentation, (2) user guidance, (3) modeling capability, (4) code assessment, and (5) technical assessment.

  16. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  17. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  18. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  19. Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney disposal site. The site is in Mesa County near Grand Junction, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects public health and safety and the environment. Before each disposal site may be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Cheney disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete and the NRC formally accepts this plan. This document describes the long-term surveillance program the DOE will implement to ensure that the Cheney disposal site performs as designed. The program is based on site inspections to identify potential threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  20. Long-term surveillance plan for the Gunnison, Colorado disposal site

    SciTech Connect (OSTI)

    NONE

    1996-04-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  1. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    NONE

    1997-09-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  2. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  3. COL Application Content Guide for HTGRs: Revision to RG 1.206, Part 1 - Status Report

    SciTech Connect (OSTI)

    Wayne Moe

    2012-08-01T23:59:59.000Z

    A combined license (COL) application is required by the Nuclear Regulatory Commission (NRC) for all proposed nuclear plants. The information requirements for a COL application are set forth in 10 CFR 52.79, “Contents of Applications; Technical Information in Final Safety Analysis Report.” An applicant for a modular high temperature gas-cooled reactor (HTGR) must develop and submit for NRC review and approval a COL application which conforms to these requirements. The technical information necessary to allow NRC staff to evaluate a COL application and resolve all safety issues related to a proposed nuclear plant is detailed and comprehensive. To this, Regulatory Guide (RG) 1.206, “Combined License Applications for Nuclear Power Plants” (LWR Edition), was developed to assist light water reactor (LWR) applicants in incorporating and effectively formatting required information for COL application review (Ref. 1). However, the guidance prescribed in RG 1.206 presumes a LWR design proposal consistent with the systems and functions associated with large LWR power plants currently operating under NRC license.

  4. DEVELOPMENT OF HFE SECTIONS OF DG-1145.

    SciTech Connect (OSTI)

    HIGGINS,J.C.; OHARA, J.M.; BONGARRA, J.

    2007-03-26T23:59:59.000Z

    For the licensing of the current fleet of commercial nuclear power plants (NPPs), the Nuclear Regulatory Commission (NRC) used two key documents, NUREG-0800 and Regulatory Guide (RG) 1.70. RG 1.70 provided guidance to applicants on the contents needed in their Safety Analysis Reports (SARs) submitted as part of their application to construct or operate an NPP. NUREG-0800, the NRC Standard Review Plan (SRP), provides guidance to the NRR staff reviewers on performing their safety reviews of these applications. As part of the preparation for a new wave of improved NPP designs the NRC is in the process of updating the SRP and is also developing a new RG designated as draft RG or DG-1145, ''Combined License Applications for Nuclear Power Plants (LWR Edition).'' This will eventually become RG 1.206 and will take the place of RG 1.70. This will provide guidance for combined license (COL) applicants, as well as for other 10CFR Part 52 variations that are permitted.

  5. Human Factors Engineering Program Review Model (NUREG-0711)Revision 3: Update Methodology and Key Revisions

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.; Fleger, S.

    2012-07-22T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. NUREG-0711 is the first document to be addressed. We present the methodology used to update NUREG-0711 and summarize the main changes made. Finally, we discuss the current status of the update program and the future plans.

  6. REVIEWING PERFORMANCE ASSESSMENTS SUPPORTING

    E-Print Network [OSTI]

    Robert J. Lewis

    2010-01-01T23:59:59.000Z

    Purpose: To summarize current NRC policy and guidance, which should assist in making informed decisions regarding land disposal of unique low-level radioactive waste streams, including disposal of significant quantities of depleted uranium until a new regulation is implemented. Background: In September 2009, NRC staff conducted two public workshops soliciting early public input on major issues associated with a potential rulemaking for land disposal of unique waste streams including, but not limited to, significant quantities of depleted uranium. During these workshops, a number of stakeholders expressed interest or concern with the review of performance assessments supporting land disposal of unique waste streams prior to completion of the rulemaking process. Discussion: The enclosure contains a summary of existing guidance for reviewing performance assessments with a focus on issues associated with the safe disposal of unique waste streams. NRC staff is providing this guidance to the Agreement States for their information, and for distribution to their licensees, as appropriate. If you have any questions regarding this correspondence, please contact me at 301-415-3340 or the individuals named below.

  7. graduate school college of engineering

    E-Print Network [OSTI]

    and professionally." Emily McCarthy, PhD, 2010 NRC Postdoctoral Research Associate, Remote Sensing Division, Naval

  8. Microsoft PowerPoint - Nuclear Material Import Export License...

    National Nuclear Security Administration (NNSA)

    Commission (NRC) importexport license? - Licenses for imports - Licenses for exports - Export license monitoring Highlights of importsexports in 2014 - Nuclear...

  9. Implications of Export/Import Reporting Requirements in the

    E-Print Network [OSTI]

    natural/depleted uranium and thorium currently require no notification to the USG. It appears the NRC may

  10. Regulatory and technical reports: (Abstract index journal). Compilation for first quarter 1997, January--March

    SciTech Connect (OSTI)

    Sheehan, M.A.

    1997-06-01T23:59:59.000Z

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. This compilation is published quarterly and cummulated annually. Reports consist of staff-originated reports, NRC-sponsored conference reports, NRC contractor-prepared reports, and international agreement reports.

  11. MINOR for Natural Resources Conservation Conserving Earth's biological diversity and safeguarding the benefits or "ecosystem services"

    E-Print Network [OSTI]

    Schweik, Charles M.

    . Environmental Resources NRC 390E Evolution and Conservation (3cr-sprg) NRC 575 Case Studies in Conservation NRC for Natural Resources Conservation Conserving Earth's biological diversity and safeguarding the benefits resources conservation. In this minor, students learn about the ecology of terrestrial and aquatic

  12. MARSSIM Workgroup Contact Information Kathryn Snead** (Office) 202-343-9228

    E-Print Network [OSTI]

    -251-7449 301-251-7422 george.powers@nrc.gov Attn: George E. Powers Research/DRA/ETB U.S. NRC 21 Church Street:CSB-2A07M Rockville, MD 20850 George E. Powers Research/DRA/ETB U.S. NRC Mail Stop: CSB-2A07M Washington

  13. ENVIRSCI Upper Level & Praxis Courses updated 2/27/13 1

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    Orinithology BIOLOGY 548 Mammology CE-ENGIN 370 Introduction to Environmental & Water Resources ENVIRDES ENVIRSCI 465 Principles of Environmental Site Assessment ENVIRSCI 575 Environmental Soil Chemistry GEO Environmental Biotechnology NRC 534 Forest Measurements NRC 564 Wildlife Habitat Management NRC 565 Dynamics

  14. Safety of magnetic fusion facilities: Volume 2, Guidance

    SciTech Connect (OSTI)

    NONE

    1995-07-01T23:59:59.000Z

    This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment.

  15. Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

    SciTech Connect (OSTI)

    O`Hara, J.M.; Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J. [Carlow International Inc., Falls Church, VA (United States)

    1994-07-01T23:59:59.000Z

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

  16. O:\\A76\\FAIR\\Fair Act 2008\\Guidance\\PDF\\GUIDE TO INVENTORY SUBMISSION...

    Office of Environmental Management (EM)

    O:A76FAIRFair Act 2008GuidancePDFGUIDE TO INVENTORY SUBMISSION ATTCH 2.pdf.prn.pdf&0; O:A76FAIRFair Act 2008GuidancePDFGUIDE TO INVENTORY SUBMISSION ATTCH...

  17. O:\\A76\\FAIR\\Fair Act 2008\\Guidance\\PDF\\COLLECTION TOOL TRAINING...

    Energy Savers [EERE]

    COLLECTION TOOL TRAINING.pdf.prn.pdf&0; O:A76FAIRFair Act 2008GuidancePDFCOLLECTION TOOL TRAINING.pdf.prn.pdf&0; O:A76FAIRFair Act 2008GuidancePDFCOLLECTION TOOL...

  18. Draft Guidance for Section 242 of the Energy Policy Act of 2005...

    Office of Environmental Management (EM)

    Draft Guidance for Section 242 of the Energy Policy Act of 2005 - Hydroelectric Production Incentive Program - July 2014 Draft Guidance for Section 242 of the Energy Policy Act of...

  19. MaGKeyS : a haptic guidance keyboard system for facilitating sensorimotor training and rehabilitation

    E-Print Network [OSTI]

    Lewiston, Craig Edwin

    2009-01-01T23:59:59.000Z

    The Magnetic Guidance Keyboard System (MaGKeyS) embodies a new haptic guidance technology designed to facilitate sensorimotor training and rehabilitation. MaGKeyS works by employing active magnetic force to guide finger ...

  20. Spreading The Word: Capital Market Consequences of Business Press Coverage of Management Earnings Guidance

    E-Print Network [OSTI]

    Twedt, Brady J

    2013-06-21T23:59:59.000Z

    This study investigates the role of the business press in disseminating management earnings guidance news to capital market participants. Using a unique sample of over 55,000 articles that relate specifically to management guidance, I find that 48...

  1. Last Updated: August 2008 Data Protection Guidance: Student Finance

    E-Print Network [OSTI]

    Mumby, Peter J.

    Last Updated: August 2008 Data Protection Guidance: Student Finance Student finance information The University will not release any information to third parties without consent. From time to time the Finance Protection Authority Form, these are available from Finance Services and only relate to information

  2. TREE SEEDING BPG NOTE 10 Best Practice Guidance

    E-Print Network [OSTI]

    achieved by tree planting, using tree stock grown from seed or cuttings in the nursery. However for reclaimed brownfield land, taking account of modern guidance on site preparation and recent research on tree is comparatively inexpensive, and woodland so created can be cheaper than using the equivalent nursery stock. I

  3. DETERMINATION OF GUIDANCE VALUES FOR CLOSED LANDFILL GAS EMISSIONS

    E-Print Network [OSTI]

    Boyer, Edmond

    DETERMINATION OF GUIDANCE VALUES FOR CLOSED LANDFILL GAS EMISSIONS O. BOUR*, S. BERGER**, C Gambetta, 74 000 Annecy SUMMARY: In order to promote active landfill gas collection and treatment or natural attenuation, it is necessary to identify trigger values concerning landfill gas emissions

  4. SPAR-H Step-by-Step Guidance

    SciTech Connect (OSTI)

    April M. Whaley; Dana L. Kelly; Ronald L. Boring; William J. Galyean

    2012-06-01T23:59:59.000Z

    Step-by-step guidance was developed recently at Idaho National Laboratory for the US Nuclear Regulatory Commission on the use of the Standardized Plant Analysis Risk-Human Reliability Analysis (SPAR-H) method for quantifying Human Failure Events (HFEs). This work was done to address SPAR-H user needs, specifically requests for additional guidance on the proper application of various aspects of the methodology. This paper overviews the steps of the SPAR-H analysis process and highlights some of the most important insights gained during the development of the step-by-step directions. This supplemental guidance for analysts is applicable when plant-specific information is available, and goes beyond the general guidance provided in existing SPAR-H documentation. The steps highlighted in this paper are: Step-1, Categorizing the HFE as Diagnosis and/or Action; Step-2, Rate the Performance Shaping Factors; Step-3, Calculate PSF-Modified HEP; Step-4, Accounting for Dependence, and; Step-5, Minimum Value Cutoff.

  5. TICLE: using multimedia multimodal guidance to enhance learning q

    E-Print Network [OSTI]

    Scarlatos, Lori

    TICLE: using multimedia multimodal guidance to enhance learning q Lori L. Scarlatos Department Tangible Interfaces for Collaborative Learning Environments (TICLE) explores new ways that multimedia can a TICLE system, and describes one implementation: a multimedia multimodal system that responds to children

  6. Guidance Note 052 RISK ASSESSMENTS FOR HAZARDOUS CHEMICALS

    E-Print Network [OSTI]

    Guidance Note 052 RISK ASSESSMENTS FOR HAZARDOUS CHEMICALS as required under the CONTROL OF SUBSTANCES HAZARDOUS TO HEALTH REGULATIONS (COSHH) and the DANGEROUS SUBSTANCES AND EXPLOSIVE ATMOSPHERES Involving the Use of Hazardous Chemicals. COSHH requires health risks to be assessed and controlled

  7. Guidance Document Quick Guide to Assess Risk for Hazardous Chemicals

    E-Print Network [OSTI]

    Guidance Document Quick Guide to Assess Risk for Hazardous Chemicals The following outline provides) or other sources of information. In cases where substances with significant or unusual potential hazards of experience and the degree of potential hazard associated with the proposed experiment, it may be necessary

  8. Soil Vapor Extraction System Optimization, Transition, and Closure Guidance

    SciTech Connect (OSTI)

    Truex, Michael J.; Becker, Dave; Simon, Michelle A.; Oostrom, Martinus; Rice, Amy K.; Johnson, Christian D.

    2013-02-08T23:59:59.000Z

    Soil vapor extraction (SVE) is a prevalent remediation approach for volatile contaminants in the vadose zone. A diminishing rate of contaminant extraction over time is typically observed due to 1) diminishing contaminant mass, and/or 2) slow rates of removal for contamination in low-permeability zones. After a SVE system begins to show indications of diminishing contaminant removal rate, SVE performance needs to be evaluated to determine whether the system should be optimized, terminated, or transitioned to another technology to replace or augment SVE. This guidance specifically addresses the elements of this type of performance assessment. While not specifically presented, the approach and analyses in this guidance could also be applied at the onset of remediation selection for a site as a way to evaluate current or future impacts to groundwater from vadose zone contamination. The guidance presented here builds from existing guidance for SVE design, operation, optimization, and closure from the U.S. Environmental Protection Agency, U.S. Army Corps of Engineers, and the Air Force Center for Engineering and the Environment. The purpose of the material herein is to clarify and focus on the specific actions and decisions related to SVE optimization, transition, and/or closure.

  9. Guidance on Confidentiality in Student Health and Welfare

    E-Print Network [OSTI]

    Henderson, Gideon

    Guidance on Confidentiality in Student Health and Welfare Executive Summary The law has long manner. This would include information about a student's physical or mental health or financial Health and Welfare, and summarized below, confidential information should be shared with others only

  10. Climate policy and competitiveness: Policy guidance and quantitative evidence

    E-Print Network [OSTI]

    Climate policy and competitiveness: Policy guidance and quantitative evidence Jared C. Carbone NicholasRivers July 2014 Abstract When considering adoption of a domestic climate change policy survey the literature on the quantitative impacts of unilateral climate change policy derived from

  11. Pre-Employment Screening: How New EEOC Guidance Affects

    E-Print Network [OSTI]

    Weaver, Harold A. "Hal"

    Pre-Employment Screening: How New EEOC Guidance Affects Criminal Background Checks & Potentially Increases Employer Risks An HRWebAdvisor Webinar by Mark A. de Bernardo, Esq. Jackson Lewis LLP #12;HRWebAdvisor Webinar: Pre-Employment Screening 2 Our webinars are designed to be accurate

  12. Massachusetts Policy Guidance for Regulating Solar Energy Systems

    Broader source: Energy.gov [DOE]

    This policy guidance was established to summarize, explain, and help communities apply four of the Massachusetts statutes that apply to solar energy systems. These statutes include: Chapter 40A Section 3 (solar exemptions), Chapter 40A Section 9B (solar access), Chapter 187 Section 1A (solar easements), and Chapter 40C (Historic Districts).

  13. Chemical-Terrorism Vulnerability Information Guidance Document January 7, 2011

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Chemical-Terrorism Vulnerability Information Guidance Document January 7, 2011 The following) section on Chemical-Terrorism Vulnerability Information (CVI) 6 CFR 27.400. The Program Manager's comments.215; Not currently applicable (2) Site Security Plans under §27.225; Not currently applicable (3) Documents relating

  14. Long-term surveillance plan for the Burro Canyon disposal cell Slick Rock, Colorado

    SciTech Connect (OSTI)

    NONE

    1997-03-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Burro Canyon disposal cell in San Miguel County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Burro Canyon disposal cell. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete at the Burro Canyon disposal cell and the NRC formally accepts this LTSP. Attachment 1 contains the concurrence letters from NRC. This LTSP describes the long-term surveillance program the DOE has implemented to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. Ground water monitoring will not be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low yield from the uppermost aquifer. The LTSP is based on the UMTRA Project`s long-term surveillance program guidance and meets the requirements of 10 CFR 40.27(b) and 40 CFR 192.03.

  15. UBC Clinical Guidance Notes December 17, 2012 1 | P a g e Table of Contents

    E-Print Network [OSTI]

    Michelson, David G.

    UBC Clinical Guidance Notes December 17, 2012 1 | P a g e Table of Contents PART A: UBC Clinical: Acronyms and Glossary #12;UBC Clinical Guidance Notes December 17, 2012 2 | P a g e UBC Clinical Research clinical Research Ethics Boards' policies and guidance concerning clinical research ethics at UBC

  16. Standard Review Plan Maintenance Program implementing procedures document

    SciTech Connect (OSTI)

    NONE

    1996-11-01T23:59:59.000Z

    The implementing Procedures Document (IPD) was developed by the Inspection Program Projects Branch, Office of Nuclear Reactor Regulation, with assistance from Pacific Northwest National Laboratory, for the Standard Review Plan Maintenance Program (SRP-MP). The SRP-MP was established to maintain the Standard Review Plan (SRP) on an on-going basis. The IPD provides guidance, including an overall approach and procedures, for SRP-MP tasks. The objective of the IPD is to ensure that modifications to SRP need to reflect current NRC requirements and guidance are identified and that a consistent methodology is used to develop and revise SRP sections.

  17. Review of Quantitative Software Reliability Methods

    SciTech Connect (OSTI)

    Chu, T.L.; Yue, M.; Martinez-Guridi, M.; Lehner, J.

    2010-09-17T23:59:59.000Z

    The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on deterministic engineering criteria. In its 1995 probabilistic risk assessment (PRA) policy statement, the Commission encouraged the use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. Although many activities have been completed in the area of risk-informed regulation, the risk-informed analysis process for digital systems has not yet been satisfactorily developed. Since digital instrumentation and control (I&C) systems are expected to play an increasingly important role in nuclear power plant (NPP) safety, the NRC established a digital system research plan that defines a coherent set of research programs to support its regulatory needs. One of the research programs included in the NRC's digital system research plan addresses risk assessment methods and data for digital systems. Digital I&C systems have some unique characteristics, such as using software, and may have different failure causes and/or modes than analog I&C systems; hence, their incorporation into NPP PRAs entails special challenges. The objective of the NRC's digital system risk research is to identify and develop methods, analytical tools, and regulatory guidance for (1) including models of digital systems into NPP PRAs, and (2) using information on the risks of digital systems to support the NRC's risk-informed licensing and oversight activities. For several years, Brookhaven National Laboratory (BNL) has worked on NRC projects to investigate methods and tools for the probabilistic modeling of digital systems, as documented mainly in NUREG/CR-6962 and NUREG/CR-6997. However, the scope of this research principally focused on hardware failures, with limited reviews of software failure experience and software reliability methods. NRC also sponsored research at the Ohio State University investigating the modeling of digital systems using dynamic PRA methods. These efforts, documented in NUREG/CR-6901, NUREG/CR-6942, and NUREG/CR-6985, included a functional representation of the system's software but did not explicitly address failure modes caused by software defects or by inadequate design requirements. An important identified research need is to establish a commonly accepted basis for incorporating the behavior of software into digital I&C system reliability models for use in PRAs. To address this need, BNL is exploring the inclusion of software failures into the reliability models of digital I&C systems, such that their contribution to the risk of the associated NPP can be assessed.

  18. Regulatory and technical reports (abstract index journal): Annual compilation for 1994. Volume 19, Number 4

    SciTech Connect (OSTI)

    NONE

    1995-03-01T23:59:59.000Z

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order. These precede the following indexes: secondary report number index, personal author index, subject index, NRC originating organization index (staff reports), NRC originating organization index (international agreements), NRC contract sponsor index (contractor reports), contractor index, international organization index, and licensed facility index. A detailed explanation of the entries precedes each index.

  19. Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR).

  20. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    SciTech Connect (OSTI)

    Lloyd, R C; Moffitt, N E; Gore, B F; Vo, T V; Vehec, T A [Pacific Northwest Lab., Richland, WA (United States)

    1993-02-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant.

  1. Auxiliary feedwater system risk-based inspection guide for the Ginna Nuclear Power Plant

    SciTech Connect (OSTI)

    Pugh, R.; Gore, B.F.; Vo, T.V.; Moffitt, N.E. (Pacific Northwest Lab., Richland, WA (United States))

    1991-09-01T23:59:59.000Z

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Ginna was selected as the eighth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Ginna plant. 23 refs., 1 fig., 1 tab.

  2. Regulatory analysis technical evaluation handbook. Final report

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    The purpose of this Handbook is to provide guidance to the regulatory analyst to promote preparation of quality regulatory analysis documents and to implement the policies of the Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission (NUREG/BR-0058 Rev. 2). This Handbook expands upon policy concepts included in the NRC Guidelines and translates the six steps in preparing regulatory analyses into implementable methodologies for the analyst. It provides standardized methods of preparation and presentation of regulatory analyses, with the inclusion of input that will satisfy all backfit requirements and requirements of NRC`s Committee to Review Generic Requirements. Information on the objectives of the safety goal evaluation process and potential data sources for preparing a safety goal evaluation is also included. Consistent application of the methods provided here will result in more directly comparable analyses, thus aiding decision-makers in evaluating and comparing various regulatory actions. The handbook is being issued in loose-leaf format to facilitate revisions. NRC intends to periodically revise the handbook as new and improved guidance, data, and methods become available.

  3. LLW Notes, Volume 12, Number 8

    SciTech Connect (OSTI)

    Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

    1997-12-31T23:59:59.000Z

    Contents include articles entitled: Chem-Nuclear documents new plan for Barnwell; Nebraska releases technical analysis of LLRW facility; Southeast Compact suspends funding for NC facility development; NC governor and Southeast Compact differ on proposed MOU; Midwest Compact to return export fees; State legislators` group revises radioactive waste policy; Internal documents discuss administration`s policy on Ward Valley; BLM issues EA for Ward Valley testing; California DHS, NRC criticize DOI`s testing protocols; Army removes training mines from Ward Valley site; The 1997 gubernatorial elections and a look ahead to 1998; Court throws out case challenging Pennsylvania`s siting law; DOE files notice of appeal in WCS suit; Central Compact moves to dismiss ``Veto`` authority suit; Congress exempts NAS from FACA; Judge sets schedule for Ward Valley case; Court won`t order DOE to accept spent fuel by deadline; NRC chairman expresses concern re CERCLA reauthorization; Senators question EPA`s guidance on remediation; EPA issues guidance, criticizes NRC decommissioning rule; Members of Congress clarify FUSRAP transfer; HLW legislation passes House by wide margin; Takings legislation passes House; Energy and water bill signed into law; and Senate confirms 5 of 6 DOE appointees.

  4. Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177

    SciTech Connect (OSTI)

    Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre; Day, Neil; Gambone Rodriguez, Kimberly; Cruz, Luis; Sotomayor-Rivera, Alexis; Vechioli, Lucieann; Vera, John; Pstrak, David [United States Nuclear Regulatory Commission, Mail Stop EBB-03D-02M, 6003 Executive Boulevard, Rockville, MD 20852 (United States)

    2012-07-01T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (?49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leaving the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)

  5. NGNP Project Regulatory Gap Analysis for Modular HTGRs

    SciTech Connect (OSTI)

    Wayne Moe

    2011-09-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) Project Regulatory Gap Analysis (RGA) for High Temperature Gas-Cooled Reactors (HTGR) was conducted to evaluate existing regulatory requirements and guidance against the design characteristics specific to a generic modular HTGR. This final report presents results and identifies regulatory gaps concerning current Nuclear Regulatory Commission (NRC) licensing requirements that apply to the modular HTGR design concept. This report contains appendices that highlight important HTGR licensing issues that were found during the RGA study. The information contained in this report will be used to further efforts in reconciling HTGR-related gaps in the NRC licensing structure, which has to date largely focused on light water reactor technology.

  6. Planning guidance for the Chemical Stockpile Emergency Preparedness Program

    SciTech Connect (OSTI)

    Shumpert, B.L.; Watson, A.P.; Sorensen, J.H. [and others] and others

    1995-02-01T23:59:59.000Z

    This planning guide was developed under the direction of the U.S. Army and the Federal Emergency Management Agency (FEMA) which jointly coordinate and direct the development of the Chemical Stockpile Emergency Preparedness Program (CSEPP). It was produced to assist state, local, and Army installation planners in formulating and coordinating plans for chemical events that may occur at the chemical agent stockpile storage locations in the continental United States. This document provides broad planning guidance for use by both on-post and off-post agencies and organizations in the development of a coordinated plan for responding to chemical events. It contains checklists to assist in assuring that all important aspects are included in the plans and procedures developed at each Chemical Stockpile Disposal Program (CSDP) location. The checklists are supplemented by planning guidelines in the appendices which provide more detailed guidance regarding some issues. The planning guidance contained in this document will help ensure that adequate coordination between on-post and off-post planners occurs during the planning process. This planning guide broadly describes an adequate emergency planning base that assures that critical planning decisions will be made consistently at every chemical agent stockpile location. This planning guide includes material drawn from other documents developed by the FEMA, the Army, and other federal agencies with emergency preparedness program responsibilities. Some of this material has been developed specifically to meet the unique requirements of the CSEPP. In addition to this guidance, other location-specific documents, technical studies, and support studies should be used as needed to assist in the planning at each of the chemical agent stockpile locations to address the specific hazards and conditions at each location.

  7. Long-Term Stewardship Baseline Report and Transition Guidance

    SciTech Connect (OSTI)

    Kristofferson, Keith

    2001-11-01T23:59:59.000Z

    Long-term stewardship consists of those actions necessary to maintain and demonstrate continued protection of human health and the environment after facility cleanup is complete. As the Department of Energy’s (DOE) lead laboratory for environmental management programs, the Idaho National Engineering and Environmental Laboratory (INEEL) administers DOE’s long-term stewardship science and technology efforts. The INEEL provides DOE with technical, and scientific expertise needed to oversee its long-term environmental management obligations complexwide. Long-term stewardship is administered and overseen by the Environmental Management Office of Science and Technology. The INEEL Long-Term Stewardship Program is currently developing the management structures and plans to complete INEEL-specific, long-term stewardship obligations. This guidance document (1) assists in ensuring that the program leads transition planning for the INEEL with respect to facility and site areas and (2) describes the classes and types of criteria and data required to initiate transition for areas and sites where the facility mission has ended and cleanup is complete. Additionally, this document summarizes current information on INEEL facilities, structures, and release sites likely to enter long-term stewardship at the completion of DOE’s cleanup mission. This document is not intended to function as a discrete checklist or local procedure to determine readiness to transition. It is an overarching document meant as guidance in implementing specific transition procedures. Several documents formed the foundation upon which this guidance was developed. Principal among these documents was the Long-Term Stewardship Draft Technical Baseline; A Report to Congress on Long-Term Stewardship, Volumes I and II; Infrastructure Long-Range Plan; Comprehensive Facility Land Use Plan; INEEL End-State Plan; and INEEL Institutional Plan.

  8. Studying Wind Energy/Bird Interactions: A Guidance Document

    SciTech Connect (OSTI)

    Anderson, R. [California Energy Commission (US); Morrison, M. [California State Univ., Sacramento, CA (US); Sinclair, K. [Dept. of Energy/National Renewable Energy Lab. (US); Strickland, D. [WEST, Inc. (US)

    1999-12-01T23:59:59.000Z

    This guidance document is a product of the Avian Subcommittee of the National Wind Coordinating Committee (NWCC). The NWCC was formed to better understand and promote responsible, credible, and comparable avian/wind energy interaction studies. Bird mortality is a concern and wind power is a potential clean and green source of electricity, making study of wind energy/bird interactions essential. This document provides an overview for regulators and stakeholders concerned with wind energy/bird interactions, as well as a more technical discussion of the basic concepts and tools for studying such interactions.

  9. ICDF Complex Waste Profile and Verification Sample Guidance

    SciTech Connect (OSTI)

    W. M. Heileson

    2006-10-01T23:59:59.000Z

    This guidance document will assist waste generators who characterize waste streams destined for disposal at the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) Complex. The purpose of this document is to develop a conservative but appropriate way to (1) characterize waste for entry into the ICDF; (2) ensure compliance with the waste acceptance criteria; and (3) facilitate disposal at the ICDF landfill or evaporation pond. In addition, this document will establish the waste verification process used by ICDF personnel to ensure that untreated waste meets applicable ICDF acceptance limits

  10. Technical background document for draft soil screening level guidance

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    The document provides technical details of the derivation of the September 30, 1993, draft Soil Screening Levels (SSLs) Guidance for Superfund (PB93-963508). The document is presented in two sections. Section I defines SSL and provides background information on the development of SSLs and their application and implementation at Superfund sites, including sampling schemes for measuring SSL attainment. It also provides draft SSLs developed for 30 chemicals. Section II provides the technical basis for the development of SSLs addressing direct ingestion of soil, inhalation of volatiles and fugitive dust, and the soil-to-ground-water exposure pathway, including the assumptions and theories used the their development.

  11. POLICY GUIDANCE MEMORANDUM #12 Payment of Expenses for Professional

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagementOPAM5 Accretion-of-Duties POLICY GUIDANCE MEMORANDUM

  12. POLICY GUIDANCE MEMORANDUM #13 Reemployment Priority List Selections |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagementOPAM5 Accretion-of-Duties POLICY GUIDANCE MEMORANDUMDepartment of

  13. POLICY GUIDANCE MEMORANDUM #14 Establishing a Residence for a Relocation

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagementOPAM5 Accretion-of-Duties POLICY GUIDANCE MEMORANDUMDepartment

  14. POLICY GUIDANCE MEMORANDUM #16 OPM Managers' Satisfaction Survey |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2:Introduction toManagementOPAM5 Accretion-of-Duties POLICY GUIDANCE

  15. GC GUIDANCE ON ELECTRIC VEHICLE RECHARGING STATIONS | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport inEnergy0.pdfTechnologiesNATIONAL ENVIRONMENTALnatural gas as aGC GUIDANCE ON

  16. GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2: FinalOffers3.pdf0-45.pdf0 Budget Fossil EnergyFull Text ManagementDOE REALGC GUIDANCE ON

  17. POLICY GUIDANCE MEMORANDUM #10 Category Rating | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferAprilOverviewEfficiencyofHSSPIA - I-Manage STARSDepartmentThis guidance is

  18. Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral GuidanceEnergy LaunchingGrowing

  19. Guidance for Fiscal Year 2015 Facilities Information Management System Data

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral GuidanceEnergy LaunchingGrowingValidations |

  20. Guidance on Ex Parte Communications | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral GuidanceEnergyServices » Petroleum

  1. Guidance on Inherently Governmental Functions | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12 OPAMGeneral GuidanceEnergyServices »

  2. SEP/EECBG Reporting Guidance FAQs | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy atLLC - FE DKT. 10-160-LNG - ORDER 2913 |DepartmentEECBG Reporting Guidance

  3. POLICY GUIDANCE MEMORANDUM #21 Family Members | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking ofOilNEWResponse(Expired) | Department of Energy 9 Guidance onAnnual1

  4. POLICY GUIDANCE MEMORANDUM #23 Permanent and Nonpermanent Positions,

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking ofOilNEWResponse(Expired) | Department of Energy 9 GuidanceAppointments,

  5. Privacy Impact Assessment Template and Guidance | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 RussianBy: ThomasDepartment ofThis weekSpecificThat SaveFor optimalGuidance is

  6. Guidance on Inherently Governmental Functions | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking of Blythe Solar Power Project Ground BreakingWater EfficiencyExGuidance on

  7. Misuse_Government_IT_CommunicationResources_Guidance.pdf | Department of

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015of 2005 atthe DistrictIndependentDepartment4.docfromImpact |Guidance on

  8. Security Policy, Guidance & Reports | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative JC3 RSS September 9,AwardGrads &Alternative Fuel| DepartmentPolicy, Guidance &

  9. Guidance on New Construction under an Energy Savings Performance Contract |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(Fact Sheet), GeothermalGrid Integration andGuidance on Life-Cycle CostDepartment

  10. Washington State Department of Transportation Bridge Maintenance and Inspection Guidance for Protected Terrestrial Species

    E-Print Network [OSTI]

    Carey, Marion

    2007-01-01T23:59:59.000Z

    impacts from routine maintenance and inspection activities.expanded their Highway Maintenance Environmental Complianceand one specific to maintenance activities. The guidance is

  11. Guidance on the Elements Necessary to Qualify as an Energy Conservatio...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    the Elements Necessary to Qualify as an Energy Conservation Measure Under an ESPC Guidance on the Elements Necessary to Qualify as an Energy Conservation Measure Under an ESPC...

  12. Enforcement Guidance Supplement 99-03, Limitation of 10 CFR 830...

    Broader source: Energy.gov (indexed) [DOE]

    function. These features included the following: (1) failure to perform required surveillance of Enforcement Guidance Supplement EGS 99-03 Appendix E - Operational Procedures...

  13. Webinar: Guidance for Filling Out a Detailed H2A Production Case Study

    Broader source: Energy.gov [DOE]

    Video recording and text version of the webinar titled, Guidance for Filling Out a Detailed H2A Production Case Study, originally presented on July 9, 2013.

  14. Lessons and Guidance on Securing financing for RE/EE projects...

    Open Energy Info (EERE)

    and guidance from these experiences emphasize the development of clear and robust business plans in order to attract investors, the careful consideration and use of carbon...

  15. DOE Guidance on the Elements Necessary to Qualify as an Energy...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    measure" (ECM) for the purpose of a federal energy savings performance contract (ESPC). espcecmbundlingguidance.pdf More Documents & Publications Guidance on New...

  16. LEDS Tool: Step-By-Step Guidance to a Long-Term Framework for...

    Open Energy Info (EERE)

    OpenEI Keyword(s): LEDS Guidance Developing Implementing Process Language: "English, Spanish; Castilian" is not in the list of possible values (Abkhazian, Achinese, Acoli,...

  17. Learning to perform a new movement with robotic assistance: comparison of haptic guidance and visual demonstration

    E-Print Network [OSTI]

    Liu, J; Cramer, SC; Reinkensmeyer, DJ

    2006-01-01T23:59:59.000Z

    perform a new movement with robotic assistance: comparisonMechanical guidance with a robotic device is a candidatereproduce the path without robotic demonstration. Results:

  18. Guidance for State Energy Program Grantees on Sub-Recipient Monitoring...

    Broader source: Energy.gov (indexed) [DOE]

    Guidance for energy efficiency and conservation block grants grantees on sub-recipient monitoring. eecbg10-019subgranteemonitoringguidance.pdf More Documents & Publications...

  19. Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

    SciTech Connect (OSTI)

    Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

    2013-12-17T23:59:59.000Z

    At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC’s assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and 1988. All of the reports reviewed were the regulator’s assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants.

  20. Accepting Mixed Waste as Alternate Feed Material for Processing and Disposal at a Licensed Uranium Mill

    SciTech Connect (OSTI)

    Frydenland, D. C.; Hochstein, R. F.; Thompson, A. J.

    2002-02-26T23:59:59.000Z

    Certain categories of mixed wastes that contain recoverable amounts of natural uranium can be processed for the recovery of valuable uranium, alone or together with other metals, at licensed uranium mills, and the resulting tailings permanently disposed of as 11e.(2) byproduct material in the mill's tailings impoundment, as an alternative to treatment and/or direct disposal at a mixed waste disposal facility. This paper discusses the regulatory background applicable to hazardous wastes, mixed wastes and uranium mills and, in particular, NRC's Alternate Feed Guidance under which alternate feed materials that contain certain types of mixed wastes may be processed and disposed of at uranium mills. The paper discusses the way in which the Alternate Feed Guidance has been interpreted in the past with respect to processing mixed wastes and the significance of recent changes in NRC's interpretation of the Alternate Feed Guidance that sets the stage for a broader range of mixed waste materials to be processed as alternate feed materials. The paper also reviews the le gal rationale and policy reasons why materials that would otherwise have to be treated and/or disposed of as mixed waste, at a mixed waste disposal facility, are exempt from RCRA when reprocessed as alternate feed material at a uranium mill and become subject to the sole jurisdiction of NRC, and some of the reasons why processing mixed wastes as alternate feed materials at uranium mills is preferable to direct disposal. Finally, the paper concludes with a discussion of the specific acceptance, characterization and certification requirements applicable to alternate feed materials and mixed wastes at International Uranium (USA) Corporation's White Mesa Mill, which has been the most active uranium mill in the processing of alternate feed materials under the Alternate Feed Guidance.

  1. Palliative Airway Stenting Performed Under Radiological Guidance and Local Anesthesia

    SciTech Connect (OSTI)

    Profili, Stefano; Manca, Antonio [University of Sassari, Department of Radiology (Italy); Feo, Claudio F. [Istituto di Clinica Chirurgica, University of Sassari, Department of Surgery (Italy)], E-mail: cffeo@uniss.it; Padua, Guglielmo [University of Sassari, Department of Anesthesiology (Italy); Ortu, Riccardo [SS Annunziata Hospital, Service of Pneumology (Italy); Canalis, Giulio C.; Meloni, Giovanni B. [University of Sassari, Department of Radiology (Italy)

    2007-02-15T23:59:59.000Z

    Purpose. To assess the effectiveness of airway stenting performed exclusively under radiological guidance for the palliation of malignant tracheobronchial strictures. Methods. We report our experience in 16 patients with malignant tracheobronchial stricture treated by insertion of 20 Ultraflex self-expandable metal stents performed under fluoroscopic guidance only. Three patients presented dysphagia grade IV due to esophageal malignant infiltration; they therefore underwent combined airway and esophageal stenting. All the procedures were performed under conscious sedation in the radiological room; average procedure time was around 10 min, but the airway impediment never lasted more than 40 sec. Results. We obtained an overall technical success in 16 cases (100%) and clinical success in 14 patients (88%). All prostheses were successfully placed without procedural complications. Rapid clinical improvement with symptom relief and normalization of respiratory function was obtained in 14 cases. Two patients died within 48 hr from causes unrelated to stent placement. Two cases (13%) of migration were observed; they were successfully treated with another stent. Tumor overgrowth developed in other 2 patients (13%); however, no further treatment was possible because of extensive laryngeal infiltration. Conclusions. Tracheobronchial recanalization with self-expandable metal stents is a safe and effective palliative treatment for malignant strictures. Airway stenting performed exclusively under fluoroscopic view was rapid and well tolerated.

  2. Guidance for Human-system Interfaces to Automatic Systems

    SciTech Connect (OSTI)

    O'Hara, J.M.; Higgins, J.; Stephen Fleger; Valerie Barnes

    2010-09-27T23:59:59.000Z

    Automation is ubiquitous in modern complex systems, and commercial nuclear- power plants are no exception. Automation is applied to a wide range of functions, including monitoring and detection, situation assessment, response planning, and response implementation. Automation has become a 'team player' supporting personnel in nearly all aspects of system operation. In light of its increasing use and importance in new- and future-plants, guidance is needed to conduct safety reviews of the operator's interface with automation. The objective of this research was to develop such guidance. We first characterized the important HFE aspects of automation, including six dimensions: Levels, functions, processes, modes, flexibility, and reliability. Next, we reviewed literature on the effects of all of these aspects of automation on human performance, and on the design of human-system interfaces (HSIs). Then, we used this technical basis established from the literature to identify general principles for human-automation interaction and to develop review guidelines. The guidelines consist of the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration.

  3. International Conference on Machine Control & Guidance 2008 1 Generation and Analysis of Digital Terrain Models with

    E-Print Network [OSTI]

    1st International Conference on Machine Control & Guidance 2008 1 Generation and Analysis of Digital Terrain Models with Parallel Guidance Systems for Precision Agriculture Görres GRENZDÖRFFER models at no or little additional cost. In the paper the achievable data accuracy under different

  4. Lagoon of Venice ecosystem: Seasonal dynamics and environmental guidance with uncertainty analyses and error subspace

    E-Print Network [OSTI]

    Leonard, John J.

    Lagoon of Venice ecosystem: Seasonal dynamics and environmental guidance with uncertainty analyses the seasonal ecosystem dynamics of the Lagoon of Venice and provide guidance on the monitoring and management stochastic ecosystem modeling components are developed to represent prior uncertainties in the Lagoon

  5. Guidance for Preparing Research Proposals Involving Diagnostic Use of Ionizing Radiation in Human Use Research

    E-Print Network [OSTI]

    Kay, Mark A.

    Guidance for Preparing Research Proposals Involving Diagnostic Use of Ionizing Radiation in Human Use Research Introduction This guidance has been prepared by the Clinical Radiation Safety Committee of ionizing radiation. CRSCo serves under California Department of Health Services regulations and Nuclear

  6. Defense Transuranic Waste Program. Transuranic waste transportation assessment and guidance report

    SciTech Connect (OSTI)

    Not Available

    1985-08-01T23:59:59.000Z

    The Transportation Assessment and Guidance Report (TAGR) is designed to provide DOE-managed defense sites with guidance and citable analyses addressing National Environmental Policy Act (NEPA) requirements for qualifying and transporting transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico.

  7. Guidance for Controlling Potential Risks to Workers Exposed to Class B Biosolids

    E-Print Network [OSTI]

    Guidance for Controlling Potential Risks to Workers Exposed to Class B Biosolids This guidance is intended only for controlling health risks to workers from Class B biosolids during handling and land;1 Introduction Biosolids are the organic residues resulting from the treatment of commercial, industrial

  8. Design of route guidance information for elderly bus passengers

    E-Print Network [OSTI]

    Cheng, Pei Pei

    1992-01-01T23:59:59.000Z

    to read, and easier to understand by the elderly population. ~ab t' The objectives of the thesis were to: 1. Discover difficulties elderly people may have with utilizing route guidance information provided by a bus system at the present time. 2... 92t 10 05 10 45 12. 03 I?23 I 23 205 2 45 3 2$ 4 05 4 4S 5 25 40$ 4 47 7'l7 5 27 6 11 64d 7 28 5 DS 848 921 10 07 ID 47 4 12. DI 12 44 I 24 2 04 249 3 24 4 04 44II S 26 I 04 4;44 S3S I 19 656 7 36 5 16 d 56 9...

  9. SPAR-H Step-by-Step Guidance

    SciTech Connect (OSTI)

    W. J. Galyean; A. M. Whaley; D. L. Kelly; R. L. Boring

    2011-05-01T23:59:59.000Z

    This guide provides step-by-step guidance on the use of the SPAR-H method for quantifying Human Failure Events (HFEs). This guide is intended to be used with the worksheets provided in: 'The SPAR-H Human Reliability Analysis Method,' NUREG/CR-6883, dated August 2005. Each step in the process of producing a Human Error Probability (HEP) is discussed. These steps are: Step-1, Categorizing the HFE as Diagnosis and/or Action; Step-2, Rate the Performance Shaping Factors; Step-3, Calculate PSF-Modified HEP; Step-4, Accounting for Dependence, and; Step-5, Minimum Value Cutoff. The discussions on dependence are extensive and include an appendix that describes insights obtained from the psychology literature.

  10. Office of Legacy Management. Information and Records Management. Transition Guidance

    SciTech Connect (OSTI)

    none,

    2004-03-01T23:59:59.000Z

    The Office of Legacy Management (LM) is an integral part of the U.S. Department of Energy’s (DOE’s) strategy to ensure that legacy liabilities of former nuclear weapons production sites are properly managed following the completion of environmental cleanup activities. LM will work with each site using an integrated team approach to ensure a successful transition. Part of this process will include transition of Government records and information. The Office of Legacy Management Information and Records Management Transition Guidance focuses on LM’s goal to preserve and protect legacy records and information. This guidance document establishes a framework for the transfer of records management responsibilities for sites transferring to LM. It describes the requirements, responsibilities, and procedures for the efficient and cost-effective transfer of custody, ownership, and management of records and other information products from the transfer site to LM. Records management practices are critical to the functions of Federal agencies because records provide information about, or evidence of, the organization, functions, policies, decisions, procedures, operations, or other activities. Therefore, the information generated by an agency is created, maintained, and dispositioned through records management processes that ensure the appropriate preservation and retrieval of essential information. Because of their intrinsic value, best practices to preserve information and records should be utilized when records are transferred from one organization to another. As the transfer program completes cleanup activities at closure sites, a transitional process will facilitate the transparent shift in the management of site records activities to LM. The roles and responsibilities of the transfer site and/or program and LM described in this document are a necessary foundation for cooperation and coordination and are essential to the successful transition of records and information responsibilities. The DOE Office of the Chief Information Officer (OCIO) has a central role in DOE records management by providing guidance, expertise, and coordination to all DOE offices and organizations and coordination with the National Archives and Records Administration (NARA). LM and the transfer site will complete an integrated transition plan which will integrate all transition elements including information and records. As part of the overall transition plan, an Information and Records Transition Plan will be developed consistent with the integrated transition plan for the site transfer and included as an attachment. The Information and Records Management Transition Plan will be developed to assist both organizations in organizing the tasks; establishing a timetable and milestones for their completion; and identifying manpower, funding and other resources that will be needed to complete the ownership transfer. In addition, the plan will provide a valuable exchange of institutional knowledge that will assist LM in meeting the obligations of responsibly managing legacy records. Guidance for the development of the plan is included in this document. Records management concerns that may arise during site closure, such as management support, contract language and agreements, interactions with the OCIO and NARA, resource and budget considerations, and procedures to safeguard records are addressed. Guidelines and criteria for records management transition activities are also provided. These include LM expectations for the inventory, scheduling, and disposition of records; the management and transfer of electronic files, including databases and software; records finding aids, indices, and recordkeeping systems; and the process for the transfer of hard copy and electronic records to LM.

  11. Low-Level Waste Regulation: Putting Principles Into Practice - 13297 - The Richard S. Hodes, M.D., Honor Lecture Award

    SciTech Connect (OSTI)

    Kennedy, James E. [Low-Level Waste Branch Division of Waste Management and Environmental Protection, U.S. Nuclear Regulatory Commission, Washington, DC, 20555-0001 (United States)] [Low-Level Waste Branch Division of Waste Management and Environmental Protection, U.S. Nuclear Regulatory Commission, Washington, DC, 20555-0001 (United States)

    2013-07-01T23:59:59.000Z

    In carrying out its mission to ensure the safe use of radioactive materials for beneficial civilian purposes while protecting people and the environment, the U.S. Nuclear Regulatory Commission (NRC) adheres to its Principles of Good Regulation. The Principles-Independence, Openness, Efficiency, Clarity, and Reliability-apply to the agency as a whole in its decision-making and to the individual conduct of NRC employees. This paper describes the application of the Principles in a real-life staff activity, a guidance document used in the NRC's low-level radioactive waste (LLW) program, the Concentration Averaging and Encapsulation Branch Technical Position (CA BTP). The staff's process to revise the document, as well as the final content of the document, were influenced by following the Principles. For example, consistent with the Openness Principle, the staff conducted a number of outreach activities and received many comments on three drafts of the document. Stakeholder comments affected the final staff positions in some cases. The revised CA BTP, once implemented, is expected to improve management and disposal of LLW in the United States. Its positions have an improved nexus to health and safety; are more performance-based than previously, thus providing licensees with options for how they achieve the required outcome of protecting an inadvertent human intruder into a disposal facility; and provide for disposal of more sealed radioactive sources, which are a potential threat to national security. (author)

  12. Comments received on proposed rule on radiological criteria for decommissioning and related documents

    SciTech Connect (OSTI)

    Page, G.; Caplin, J.; Smith, D. [and others

    1996-03-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As a part of this action, the Commission published in the Federal Register (59 FR 43200), on August 22, 1994, a proposed rule on radiological criteria for decommissioning, soliciting comments both on the rule as proposed and on certain specific items as identified in its supplementary statement of considerations. A draft Generic Environmental Impact Statement (GEIS) in support of the rule, also published in August 1994 as NUREG-1496, along with its Appendix A (NUREG-1501), were also made available for comment. A staff working draft on regulatory guidance (NUREG-1500)was also made available. This report summarizes the 1,309 comments on the proposed rule and supplementary items and the 311 comments on the GEIS as excerpted from 101 docketed letters received associated in the Federal/Register notice. Comments from two NRC/Agreement-States meetings are also summarized.

  13. Scientific Guidance, Research, and Educational Outreach for the ARM Climate Research Facility (ACRF) in the Southern Great Plains

    SciTech Connect (OSTI)

    Lamb, Peter J.

    2013-06-13T23:59:59.000Z

    Scientific Guidance, Research, and Educational Outreach for the ARM Climate Research Facility (ACRF) in the Southern Great Plains

  14. In-tank processes for destruction of organic complexants and removal of selected radionuclides

    SciTech Connect (OSTI)

    Schulz, W.W.; Kupfer, M.J.; McKeon, M.M.

    1995-02-01T23:59:59.000Z

    This report establishes the need and technical feasibility for using in-tank pretreatment processes for destruction of organic complexants and removal of {sup 90}Sr, transuranic (TRU) elements, and {sup 99}Tc from double-shell tank (DST) liquid wastes. Neither {sup 90}Sr nor {sup 99}{Tc} have to be removed from any DST solution to obtain vitrified product containing less than the Nuclear Regulatory Commission (NRC) criteria for Class C commercial low-level waste (LLW). To meet the NRC criterion for Class C LLW, TRU elements must be removed from liquid wastes in three (possibly five) DSTs. No {sup 90}Sr will have to be removed from any solution for the total vitrified waste from both DSTs and single-shell tanks to meet a goal of <7 MCi of radionuclides and a NRC ruling for Hanford Site Incidental Waste. Guidance from ALARA principles and the TWRS Environmental Impact Statement may dictate additional removal of radionuclides from DST supernatant liquids. Scavenging processes involving precipitation of strontium phosphate and/or hydrated iron oxide effectively remove {sup 90}Sr and/or TRU elements from actual DST wastes including complexant concentrate (CC) wastes. Destruction of organic complexants is not required for these scavenging processes to reduce the {sup 90}Sr and/or TRU element concentrations of DST waste solutions to or below the NRC criteria for Class C commercial LLW. However, substantially smaller amounts of scavenging agents would be required for removal of {sup 90}Sr and TRU elements from CC waste if organic complexants were destroyed. Low concentrations of added Sr(NO{sub 3}){sub 2} and Fe(NO{sub 3}){sub 3} are desirable to minimize the volume of HLW glass.

  15. Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report

    SciTech Connect (OSTI)

    Donoghue, J.E.; Donohew, J.N.; Golub, G.R.; Kenneally, R.M.; Moore, P.B.; Sands, S.P.; Throm, E.D.; Wetzel, B.A. [Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal

    1994-02-01T23:59:59.000Z

    This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC`s ``Statement of Policy for the Regulation of Advanced Nuclear Power Plants`` (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC`s preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant`s research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified.

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

    SciTech Connect (OSTI)

    NONE

    1997-05-01T23:59:59.000Z

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Mexican Hat, Utah, disposal site. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Mexican Hat disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the disposal site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Mexican Hat disposal site performs as designed. The program is based on two distinct types of activities: (1) site inspections to identify potential threats to disposal cell integrity, and (2) monitoring of selected seeps to observe changes in flow rates and water quality. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03. 18 refs., 6 figs., 1 tab.

  17. Nuclear Regulatory Commission Information Digest 1992 edition. Volume 4

    SciTech Connect (OSTI)

    Olive, K [ed.] [ed.

    1992-03-01T23:59:59.000Z

    The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, the activities NRC licenses, and general information on domestic and worldwide nuclear energy. This digest is a compilation of nuclear- and NRC-related data and is designed to provide a quick reference to major facts about the agency and industry it regulates. In general, the data cover 1975 through 1991, with exceptions noted. Information on generating capacity and average capacity factor for operating US commercial nuclear power reactors is obtained from monthly operating reports that are submitted directly to the NRC by the licensee. This information is reviewed by the NRC for consistency only and no independent validation and/or verification is performed.

  18. Application of Nuclear Regulatory Commission Regulation Equivalency to Construction of New Nuclear Facilities

    SciTech Connect (OSTI)

    BISHOP, G.E.

    1999-06-02T23:59:59.000Z

    The Spent Nuclear Fuels Project (SNFP) Office of the Department of Energy (DOE), Richland Operations Office, is charged with moving 2.100 metric tons of spent nuclear fuel elements left over from plutonium production into semi-permanent storage at DOE'S Hanford site in Washington state. In anticipation of eventual NRC regulation, the DOE decided to impose NRC requirements on new SNFP facility design and construction, specifically for the Cold Vacuum Drying Facility (CVDF) and the Canister Storage Building (CSB). The SNFP implemented this policy of ''NRC equivalency'' with the goal of achieving a level of nuclear safety equivalent to that of NRC-licensed fuel processing facilities. Appropriate features of the NRC licensing process were adopted. However, the SNFP maintained applicable DOE requirements in tandem with the NRC regulations. Project work is continuing, with the first fuel movement scheduled for November, 2000.

  19. Questions and answers based on revised 10 CFR Part 20

    SciTech Connect (OSTI)

    Borges, T.; Stafford, R.S.; Lu, P.Y. [Oak Ridge National Lab., TN (United States); Carter, D. [Nuclear Regulatory Commission, Washington, DC (United States)

    1994-05-01T23:59:59.000Z

    NUREG/CR-6204 is a collection of questions and answers that were originally issued in seven sets and which pertain to revised 10 CFR Part 20. The questions came from both outside and within the NRC. The answers were compiled and provided by NRC staff within the offices of Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, the Office of State Programs, and the five regional offices. Although all of the questions and answers have been reviewed by attorneys in the NRC Office of the General Counsel, they do not constitute official legal interpretations relevant to revised 10 CFR Part 20. The questions and answers do, however, reflect NRC staff decisions and technical options on aspects of the revised 10 CFR Part 20 regulatory requirements. This NUREG is being made available to encourage communication among the public, industry, and NRC staff concerning the major revisions of the NRC`s standards for protection against radiation.

  20. 1999 vadose zone monitoring plan and guidance for subsequent years

    SciTech Connect (OSTI)

    Horton, D.G.; Reidel, S.P.; Last, G.V.

    1998-08-01T23:59:59.000Z

    The US Department of Energy`s Hanford Site has the most diverse and largest amounts of radioactive waste in the US. The majority of the liquid waste was disposed to the soil column where much of it remains today. This document provides the rationale and general framework for vadose zone monitoring at cribs, ditches, trenches and other disposal facilities to detect new sources of contamination and track the movement of existing contamination in the vadose zone for the protection of groundwater. The document provides guidance for subsequent site-specific vadose zone monitoring plans and includes a brief description of past vadose monitoring activities (Chapter 3); the results of the Data Quality Objective process used for this plan (Chapter 4); a prioritization of liquid waste disposal sites for vadose monitoring (Chapter 5 and Appendix B); a general Monitoring and Analysis Plan (Chapter 6); a general Quality Assurance Project Plan (Appendix A), and a description of vadose monitoring activities planned for FY 1999 (Appendix C).