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Sample records for nrc guidance nrc

  1. UPDATING THE NRC GUIDANCE FOR HUMAN FACTORS ENGINEERING REVIEWS.

    SciTech Connect (OSTI)

    O HARA,J.M.; BROWN,W.S.; HIGGINS,J.C.; PERSENSKY,J.J.; LEWIS,P.M.; BONGARRA,J.

    2002-09-15

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) aspects of nuclear plants. NUREG-0800 (Standard Review Plan), Chapter 18, ''Human Factors Engineering,'' is the principal NRC staff guidance document. Two main documents provide the review criteria to support the evaluations. The HFE Program Review Model (NUREG-0711) addresses the design process from planning to verification and validation to design implementation. The Human-System Interface Design Review Guidelines (NUREG-0700) provides the guidelines for the review of the HFE aspects of human-system interface technology, such as alarms, information systems, controls, and control room design. Since these documents were published in 1994 and 1996 respectively, they have been used by NRC staff, contractors, nuclear industry organizations, as well as by numerous organizations outside the nuclear industry. Using feedback from users and NRC research conducted in recent years, both documents have been revised and updated. This was done to ensure that they remain state-of-the-art evaluation tools for changing nuclear industry issues and emerging technologies. This paper describes the methodology used to revise and update the documents and summarizes the changes made to each and their current contents. Index Terms for this report are: Control system human factors, Ergonomics, Human factors, Nuclear power generation safety.

  2. The Status of NRC Decommissioning Guidance on Intentional Soil Mixing

    SciTech Connect (OSTI)

    Watson, B.A.

    2007-07-01

    In 1997, the U.S. Nuclear Regulatory Commission (NRC) published the License Termination Rule (LTR) as Subpart E of 10 CFR Part 20, which established the license termination criteria for unrestricted use and the controls for restricted use. By 2003, the NRC staff's experience with the LTR revealed some important implementation issues impacting the decommissioning of sites, and these were addressed to the Commission (SECY-03-0069). In 2004, the staff provided the Commission with its analysis of a ninth issue, intentional soil mixing (SECY-04-0035). The Commission approved the staff's recommendations, with comments. In the draft revision of Supplement 1 to NUREG-1757, 'Consolidated Decommissioning Guidance', the staff endorsed the current practice of allowing intentional soil mixing to meet the waste acceptance criteria of offsite disposal facilities and the limited use of this practice to demonstrate compliance with the LTR criteria. The staff recommended including a provision that the staff would consider intentional mixing on a case-by-case basis, provided that the resulting contaminated area footprint is not increased and clean soil from outside the footprint is not mixed with contaminated soil to lower the concentrations. In addition, the staff would consider only those rare cases in which the mixing of clean soil is the only viable option for achieving the dose levels of the LTR. In 2005, the staff issued draft Supplement 1 to NUREG-1757 for public comment. The staff evaluated the public comments, including those from a number of States, and revised the guidance. The staff subsequently summarized the public comments on the draft guidance for the Commission (SECY-06-0143) in early 2006. This paper will discuss the public comments related to intentional mixing, the Commission's comments in its staff requirements memorandum, and the revision to the guidance in NUREG-1757 incorporating the current NRC decommissioning policy for intentional soil mixing. (authors)

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

    SciTech Connect (OSTI)

    Jacques Hugo; J. J. Persensky

    2012-07-01

    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.

  4. The impact of NRC guidance on concentration averaging on low level waste sealed source disposal - 11424

    SciTech Connect (OSTI)

    Whitworth, Julia; Stewart, Bill; Cuthbertson, Abigail

    2011-01-20

    As part of its ongoing efforts to revise the Nuclear Regulatory Commission's (NRC) current position on blending to be risk-informed and performance based and its current review of the low-level waste classification codified in 10 CFR 61.55, the Nuclear Regulatory Commission (NRC) has stated that it may review the 1995 'Branch Technical Position on Concentration Averaging and Encapsulation' (BTP), which is still commonly used today. Such a review will have timely advantages, given the lack of commercial disposal availability within the United States for radioactive sealed sources that are in wide beneficial use across the country. The current application of the BTP guidance has resulted in an effective cap on commercial disposal for sources larger than 1.1 TBq (30 Ci). This paper will analyze how the BTP has been implemented with respect to sealed sources, what the implications have been for commercial disposal availability, and whether alternative packaging configurations could be considered for disposal.

  5. Overview of NRC review process

    SciTech Connect (OSTI)

    Tokar, M.; Kane, J.D.

    1989-11-01

    This paper describes the NRC staff`s review of the Prototype License Application Safety Analysis Report (PLASAR) for an Earth-Mounded Concrete Bunker low-level waste disposal facility. Described are the objectives of the review, the resources (e.g., background guidance documents and staff technical disciplines) used, and the products produced. Evaluation conclusions are summarized.

  6. NRC Recommendations | Department of Energy

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

    NRC Recommendations NRC Recommendations 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_nas_report_hirsch.pdf (229.89 KB) More Documents & Publications Systems Analysis Workshop Welcome & Introductions Hydrogen Infrastructure Market Readiness Workshop: Preliminary Results 2013 Biological Hydrogen Production Workshop Summary

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

    SciTech Connect (OSTI)

    Walker, Stuart

    2013-07-01

    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)

  8. Status of the NRC Decommissioning Program

    SciTech Connect (OSTI)

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

    2003-02-24

    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.

  9. SQA CGD NRC Vendor Workshop | Department of Energy

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

    SQA CGD NRC Vendor Workshop SQA CGD NRC Vendor Workshop This is guidance presented by the United States Nuclear Regulatory Commission. The slides describe the process for design & analysis software. The topics included in these slides are: regulatory framework, programs, requirements, design & dedication guidance, methodology, implementation, attributes and implementation. SQA CGD NRC Vendor Workshop (3.37 MB) More Documents & Publications Commercial Grade Dedication RM Technical

  10. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    SciTech Connect (OSTI)

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

    2002-02-25

    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.

  11. NRC | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    NRC NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts

  12. ARM - Campaign Instrument - nrc-convair580

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

    Send Campaign Instrument : National Research Council - Canada CONVAIR 580 (NRC-CONVAIR580) Instrument Categories Airborne Observations Campaigns Indirect and...

  13. NRC - regulator of nuclear safety

    SciTech Connect (OSTI)

    1997-05-01

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

  14. NRC Solomons RFQ | Open Energy Information

    Open Energy Info (EERE)

    navigation, search OpenEI Reference LibraryAdd to library Legal Document- OtherOther: NRC Solomons RFQLegal Abstract Example Request for Qualification for Enhanced Use Lease....

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

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

    Organization | Department of Energy NRC Leadership Expectations and Practices for Sustaining a High Performing Organization NRC Leadership Expectations and Practices for Sustaining a High Performing Organization May 16, 2012 Presenter: William C. Ostendorff, NRC Commissioner Topics Covered: NRC Mission Safety Culture NRC Oversight NRC Inspection Program Technical Qualification Continuous Learning NRC Leadership Expectations and Practices for Sustaining a High Performing Organization (4.15

  16. NRC antitrust licensing actions, 1978--1996

    SciTech Connect (OSTI)

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

    1997-09-01

    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.

  17. DOE/NRC F 742 | Department of Energy

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

    DOE/NRC F 742 Form is used for nuclear material control and accountability. MATERIAL BALANCE REPORT (12.55 KB) More Documents & Publications DOE/NRC F 740M Material Balance Report DOE/NRC F 742C

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

    Office of Environmental Management (EM)

    Nuclear safety information sharing agreement between NRC and DOE's Office of Environment, Health, Safety and Security Nuclear safety information sharing agreement between NRC and ...

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

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

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

  20. Use of Barrier Analysis in NRC Staff's Performance Assessment...

    Office of Environmental Management (EM)

    Use of Barrier Analysis in NRC Staff's Performance Assessment Reviews Use of Barrier Analysis in NRC Staff's Performance Assessment Reviews Cynthia Barr and George Alexander United...

  1. 1996 NRC annual report. Volume 13

    SciTech Connect (OSTI)

    1997-10-01

    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.

  2. NRC Licensing Status Summary Report for NGNP

    SciTech Connect (OSTI)

    Moe, Wayne Leland; Kinsey, James Carl

    2014-11-01

    The Next Generation Nuclear Plant (NGNP) Project, initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy (DOE) pursuant to provisions of the Energy Policy Act of 2005, is based on research and development activities supported by the Department of Energy Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. The NGNP will be licensed for construction and operation by the Nuclear Regulatory Commission (NRC). However, not all elements of current regulations (and their related implementation guidance) can be applied to HTGR technology at this time. Certain policies established during past LWR licensing actions must be realigned to properly accommodate advanced HTGR technology. A strategy for licensing HTGR technology was developed and executed through the cooperative effort of DOE and the NRC through the NGNP Project. The purpose of this report is to provide a snapshot of the current status of the still evolving pre-license application regulatory framework relative to commercial HTGR technology deployment in the U.S. The following discussion focuses on (1) describing what has been accomplished by the NGNP Project up to the time of this report, and (2) providing observations and recommendations concerning actions that remain to be accomplished to enable the safe and timely licensing of a commercial HTGR facility in the U.S.

  3. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    1998-02-01

    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).

  4. REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

    SciTech Connect (OSTI)

    D.W. Markman

    1999-09-17

    Preliminary design concepts for the proposed Subsurface Repository at Yucca Mountain indicate extensive reliance on modern, computer-based, digital control technologies. The purpose of this analysis is to investigate the degree to which the U. S. Nuclear Regulatory Commission (NRC) has accepted and approved the use of digital control technology for safety-related applications within the nuclear power industry. This analysis reviews cases of existing digitally-based control systems that have been approved by the NRC. These cases can serve as precedence for using similar types of digitally-based control technologies within the Subsurface Repository. While it is anticipated that the Yucca Mountain Project (YMP) will not contain control systems as complex as those required for a nuclear power plant, the review of these existing NRC approved applications will provide the YMP with valuable insight into the NRCs review process and design expectations for safety-related digital control systems. According to the YMP Compliance Program Guidance, portions of various NUREGS, Regulatory Guidelines, and nuclear IEEE standards the nuclear power plant safety related concept would be applied to some of the designs on a case-by-case basis. This analysis will consider key design methods, capabilities, successes, and important limitations or problems of selected control systems that have been approved for use in the Nuclear Power industry. An additional purpose of this analysis is to provide background information in support of further development of design criteria for the YMP. The scope and primary objectives of this analysis are to: (1) Identify and research the extent and precedence of digital control and remotely operated systems approved by the NRC for the nuclear power industry. Help provide a basis for using and relying on digital technologies for nuclear related safety critical applications. (2) Identify the basic control architecture and methods of key digital control

  5. NRC Notice: Antifreeze Agents in Fire Water Sprinkler Systems

    Energy Savers [EERE]

    were identified in NRC Information Notice (IN) 2015-02, Antifreeze Agents in Fire Water Sprinkler Systems, (http:pbadupws.nrc.govdocsML1432ML14323A 176.pdf). This IN was...

  6. 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) ...

  7. 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.

  8. DOE/NRC Forms | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    DOE/NRC Forms U.S. Department of Energy / U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards System Links to NMMSS Forms DOE Forms 741 742 742c 749 NRC Forms http://www.nrc.gov/reading-rm/doc-collections/forms/

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

    SciTech Connect (OSTI)

    Not Available

    1994-03-01

    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.

  10. 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

  11. Sample Form DOE NRC 740M

    National Nuclear Security Administration (NNSA)

    CONCISE NOTE DOE/NRC FORM 740M (6-2008) MANDATORY DATA COLLECTION AUTHORIZED BY 10 CFR 30, 40, 50, 70, 72, 74, 75, 150, Public Laws 83-703, 93-438, 95-91 Estimated burden per response to comply with this mandatory collection request: 45 minutes. This information is required to satisfy the provisions of the US/IAEA Safeguards Agreement. Send comments regarding burden estimate to the Records and FOIA Privacy Services Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001,

  12. DOE Awards Contract for the Nuclear Regulatory Commission (NRC...

    Office of Environmental Management (EM)

    The NRC Licensed Facilities contract is for managing Spent Nuclear Fuel (SNF) storage facilities ... protection, waste management, safeguards and security, information management, ...

  13. Microsoft PowerPoint - NRC Managent Persectives_Marissa Bailey...

    National Nuclear Security Administration (NNSA)

    facilities, independent spent fuel storage facilities, decommissioning sites and uranium mills. Foster interactions between NRC licensees and the IAEA as needed. ...

  14. Operating Experience Level 3, NRC Notice: Antifreeze Agents in...

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

    October 2015 OE-3 2015-04: NRC Notice: Antifreeze Agents in Fire Water Sprinkler Systems This Operating Experience Level 3 (OE-3) document provides information about safety...

  15. Procedures for meeting NRC antitrust responsibilities

    SciTech Connect (OSTI)

    Toalston, A.L.; Messier, M.E.; Lambe, W.M.; Nicholson, P.R.

    1985-05-01

    This report describes the procedures used by NRC staff to implement the antitrust review and enforcement prescribed in Sections 105 and 186 of the Atomic Energy Act of 1954, as amended (the Act), as covered largely by the Commission's Rules and Regulations in 10 CFR Parts 2.101, 2.102, 2.200, 50.33a, 50.80, and 50.90. These procedures set forth the steps and criteria the staff applies in the antitrust review of construction permit and operating license applications and the amendments to those applications that deal with changes in ownership. In addition, the procedures describe how the staff enforces compliance by licensees when antitrust conditions have been appended to construction permits and operating licenses.

  16. NRC regualtory agenda. Semiannual report, July 1997--December 1997

    SciTech Connect (OSTI)

    1998-02-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition.

  17. UPDATING THE NRC STANDARD REVIEW PLAN - CHAPTER 8 - ELECTRICAL SYSTEMS

    SciTech Connect (OSTI)

    SULLIVAN,K.

    2007-06-24

    The Standard Review Plan (SRP) (Reference 2), provides guidance to the regulatory staff of the Nuclear Regulatory Commission (NRC) on performing their safety reviews of applications to construct or operate nuclear power plants, and applications to approve standard designs and sites for nuclear power plants. Chapter 8 of the SRP provides guidance related to the review of station electrical distribution systems described by the applicant in its Design Control Document (DCD) or Safety Analysis Report (SAR). As part of the 2006-2007 SAR update, all sections in this Chapter (8.1, 8.2, 8.3.1, 8.3.2, Appendix 8A, and Appendix 8B) were revised to incorporate new analyses, design approaches, and the lessons learned from the review of the AP 1000 design certification and to assure consistency with the draft Regulatory Guide DG-1145, ''Combined License Applications for Nuclear Power Plants (LWR Edition)''.

  18. Taking Science to School: NRC Recommendations for K-8 Science...

    Office of Scientific and Technical Information (OSTI)

    Taking Science to School: NRC Recommendations for K-8 Science Back to the OSTI News Listing for 2006 (AIP Bulletin) Based on the most recent research on learning and cognitive ...

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

    National Nuclear Security Administration (NNSA)

    Agenda as of February 2, 2012 Agenda Highlights: 2012 DOE-NRC NMMSS Annual User Training Date Morning Sessions (8:30 am - 12 pm) Afternoon Sessions (1:00 pm - 5:00 pm) Monday May...

  20. NRC Effort on Regulatory Approaches for Control of Solid Materials

    SciTech Connect (OSTI)

    Huffert, A. M.

    2003-02-27

    The U.S. Nuclear Regulatory Commission's (NRC's) regulations that set standards for protection of the public against radiation do not currently contain specific requirements for the control of solid materials with small or no amounts of radioactivity. Absent a National standard, NRC routinely evaluates, on a case-by-case basis, licensee requests to release solid materials when they are obsolete or no longer useful during operations, or when the facility is being shut down during decommissioning. As part of its continuing examination regarding the control of solid materials, NRC sponsored and received a report from the National Academies' (NA's) National Research Council that reviewed technical bases, policies, and precedents, and made several recommendations for moving forward on this issue. NRC evaluated the NA report and developed a set of options for proceeding with a process for examining approaches for control of solid materials. This paper explains the option that NRC chose and summarizes NRC's technical basis development and related National and international activities.

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

    National Nuclear Security Administration (NNSA)

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

  2. NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

    SciTech Connect (OSTI)

    McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.; Mohseni, Aby

    2013-07-01

    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 (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but largely

  3. Recent NRC research activities addressing valve and pump issues

    SciTech Connect (OSTI)

    Morrison, D.L.

    1996-12-01

    The mission of the U.S. Nuclear Regulatory Commission (NRC) is to ensure the safe design, construction, and operation of commercial nuclear power plants and other facilities in the U.S.A. One of the main roles that the Office of Nuclear Regulatory Research (RES) plays in achieving the NRC mission is to plan, recommend, and implement research programs that address safety and technical issues deemed important by the NRC. The results of the research activities provide the bases for developing NRC positions or decisions on these issues. Also, RES performs confirmatory research for developing the basis to evaluate industry responses and positions on various regulatory requirements. This presentation summarizes some recent RES supported research activities that have addressed safety and technical issues related to valves and pumps. These activities include the efforts on determining valve and motor-operator responses under dynamic loads and pressure locking events, evaluation of monitoring equipment, and methods for detecting and trending aging of check valves and pumps. The role that RES is expected to play in future years to fulfill the NRC mission is also discussed.

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

    SciTech Connect (OSTI)

    Chakraborti, Sayan; Stone, Lynn; Hyatt, Jeannette

    2013-07-01

    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

  5. Microsoft PowerPoint - 5_Pat Smith_NMMSS_2013_Presentation_NRC Reconciliation.pptx

    National Nuclear Security Administration (NNSA)

    Reconciliation Pat Smith PSI NRC Lead NRC Reconciliation  NRC Reconciliation requirements per NUREG/BR-0007, Rev. 6  All RIS's must submit an MSR (Material Summary Report) (Form 742, 742C) to NMMSS under the following conditions: - A RIS has a reportable quantity as of their inventory date - A RIS has shipped or received a reportable quantity during the material balance reporting period NRC Reconciliation  All NRC licensees are required to report their physical inventory to NMMSS each

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

    SciTech Connect (OSTI)

    Ultroska, D.

    1984-08-01

    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.

  7. Radioactive Dose Assessment and NRC Verification of Licensee Dose Calculation.

    Energy Science and Technology Software Center (OSTI)

    1994-09-16

    Version 00 PCDOSE was developed for the NRC to perform calculations to determine radioactive dose due to the annual averaged offsite release of liquid and gaseous effluent by U.S commercial nuclear power facilities. Using NRC approved dose assessment methodologies, it acts as an inspector's tool for verifying the compliance of the facility's dose assessment software. PCDOSE duplicates the calculations of the GASPAR II mainframe code as well as calculations using the methodologices of Reg. Guidemore » 1.109 Rev. 1 and NUREG-0133 by optional choice.« less

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

    National Nuclear Security Administration (NNSA)

    Agenda as of February 2, 2012 Agenda Highlights: 2012 DOE-NRC NMMSS Annual User Training Date Morning Sessions (8:30 am - 12 pm) Afternoon Sessions (1:00 pm - 5:00 pm) Monday May 21, 2012 SAMS 7.x Software Training NMMSS Overview Training for New Users Reactor Subcommittee Foreign Obligations Subcommittee Hands-on NMMSS Training Tuesday May 22, 2012 NMMSS/NMMT/LANMAS Plenary Session Program Status NNSA/NRC Management Perspectives Nuclear Nonproliferation Initiatives U.S.-Australian Cooperation

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

    SciTech Connect (OSTI)

    Lewis, Stuart R.; Cooper, Susan E.; Najafi, Bijan; Collins, Erin; Hannaman, Bill; Kohlhepp, Kaydee; Grobbelaar, Jan; Hill, Kendra; Hendrickson, Stacey M. Langfitt; Forester, John Alan; Julius, Jeff

    2010-03-01

    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

  10. Risk-informed inservice test activities at the NRC

    SciTech Connect (OSTI)

    Fischer, D.; Cheok, M.; Hsia, A.

    1996-12-01

    The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety.

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

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

    Standards and Technology > Center Alumni > The Energy Materials Center at Cornell Jennifer Schaefer NRC Postdoctoral Fellow - National Institute of Standards and Technology Formerly a graduate student with the Archer Group, Jennifer received her PhD in 2014

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

    SciTech Connect (OSTI)

    McConnell, M. W.

    2012-07-01

    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

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

    Broader source: Energy.gov [DOE]

    DOE today urged the NRC to conclude that DOE has the legal authority to withdraw the pending Yucca Mountain license application.  DOE argued that the NRC should review and reverse the contrary...

  14. 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) PDF...

  15. Evaluation of NRC maintenance team inspection reports for managing aging

    SciTech Connect (OSTI)

    Fresco, A.; Gunther, W.

    1991-01-01

    A nuclear power plant's maintenance program is the principal vehicle through which age-related degradation is managed. Over the past two years, the NRC (Nuclear Regulatory Commission) has evaluated the maintenance program of every nuclear power plant in the U.S. The reports issued on these in-depth team inspections have been reviewed to ascertain the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear power plant systems, structures, and components. Selected results of this review are presented in this paper, including examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue are also discussed. 6 refs., 1 tab.

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

    SciTech Connect (OSTI)

    Bernholdt, David E

    2012-06-01

    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.

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

    SciTech Connect (OSTI)

    Walker, Stuart

    2008-01-15

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

  18. Peer Review of NRC Standardized Plant Analysis Risk Models

    SciTech Connect (OSTI)

    Anthony Koonce; James Knudsen; Robert Buell

    2011-03-01

    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.

  19. NRC's 13th Annual Congress highlights the mainstream of recycling

    SciTech Connect (OSTI)

    White, K.M.

    1994-12-01

    The theme of the National Recycling Coalition's (NRC, Washington, DC) recent 13th Annual Congress and Exposition in Portland, OR, was ''Jump into the Mainstream: Recycle,'' which is an action organizers of the show set out to prove is currently happening across this country. Indeed, this year's congress was designed to demonstrate how far recycling has jumped into the mainstream of American life, and show attendees what it will take to make recycling succeed in the future. Lending testament to recycling's increasing visibility, the most dominant topic at this year's show was the creation of national recycling policy. Through this agenda, and other programs that surfaced at the congress, NRC is hoping to move closer to its goal of making recycling as mainstream as taking out the garbage. NRC's board of directors unanimously voted to adopt a draft advocacy message that promotes recycling initiatives at the national level, but rejected a proposed demand-side initiative that would have established post-consumer-content recycling rates for certain materials, with product-specific, minimum-content standards as an alternative method of compliance. The initiative had called for glass, metal, paper, plastic, and wood used in primary and secondary packaging to achieve a 50% post-consumer recycling rate by the year 2000. As an alternative method of compliance, individual companies could meet the following post-consumer, minimum-content standards for products: glass, metal, paper, plastic, and wood packaging: 40% by 2000; newsprint and tissue paper: 50% by 2000; and printing and writing papers: 25% by 2000.

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

    SciTech Connect (OSTI)

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

    2012-01-13

    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).

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

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    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.

  2. 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.; Pan, Y.

    2012-07-01

    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)

  3. Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

    SciTech Connect (OSTI)

    BLACK, D.M.

    1999-08-11

    This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria--HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.

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

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

    Social Media and the NRC: What We're Doing, Why We're Doing It, and What Else We Might Do Social Media and the NRC: What We're Doing, Why We're Doing It, and What Else We Might Do ...

  5. NRC Regulatory Agenda quarterly report, July--September 1993. Volume 12, No. 3

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    The NRC Regulator Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter.

  6. Operating Experience Level 3, NRC Notice: Antifreeze Agents in Fire Water Sprinkler Systems

    Broader source: Energy.gov [DOE]

    This Operating Experience Level 3 (OE-3) document provides information about safety concerns identified by the Nuclear Regulatory Commission (NRC) that could potentially apply to work performed at Department of Energy (DOE) facilities. These concerns were identified in NRC Information Notice (IN) 2015-02, Antifreeze Agents in Fire Water Sprinkler Systems.

  7. NRC regulatory agenda: Semiannual report, July--December 1996. Volume 15, Number 2

    SciTech Connect (OSTI)

    1997-03-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued semiannually.

  8. Nuclear safety information sharing agreement between NRC and DOE’s Office of Environment, Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Nuclear safety information sharing agreement between NRC and DOE’s Office of Environment, Health, Safety and Security.

  9. Ongoing NRC Efforts on Regulatory Approaches for Control of Solid Materials

    SciTech Connect (OSTI)

    Huffert, A. M.

    2002-02-28

    Specific requirements for the release of solid materials with small or no amounts of radioactivity are not currently contained in 10 CFR Part 20, which constitutes the U.S. Nuclear Regulatory Commission's (NRC's) regulations that set standards for protection of the public against radiation. NRC has approached these matters on a case-by-case basis, in the absence of a national standard for the release of solid materials. Currently, NRC is examining its approach for the control of solid material, including the development of a technical information base for decision-making purposes. As part of this process, NRC has sponsored a National Academy of Sciences (NAS) study to review technical bases, policies, and precedents for controlling the release of solid materials, and to recommend whether NRC should continue its existing approach, establish a national standard by rulemaking, or consider other alternatives. This paper explains the status of NRC's technical basis and the next steps in NRC's decision-making process, as they relate to the NAS study.

  10. DOE Replies Support NRC Commissioners and Authority to Withdraw Yucca Application

    Broader source: Energy.gov [DOE]

    In a reply brief filed with the NRC today, DOE explained that the arguments that it lacked authority to withdraw the pending Yucca Mountain license application are uniformly without merit. DOE's...

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

    National Nuclear Security Administration (NNSA)

    used as fuel or targets in a research or test reactor (RTR) * HEU is defined as uranium ... used as fuel or targets in a research or test reactor (RTR), the NRC reported on: - ...

  12. NRC regulatory agenda: Semiannual report, January--June 1997. Volume 16, Number 1

    SciTech Connect (OSTI)

    1997-08-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1997. Section 1, ``Rules,`` includes (A) rules on which final action has been taken since December 31, 1996, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ``Petitions for Rulemaking,`` includes (A) petitions denied or incorporated into final rules since December 31, 1996; (B) petitions incorporated into proposed rules; and (C) petitions pending staff review.

  13. 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 - How to ...

  14. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    SciTech Connect (OSTI)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

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

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

    | Department of Energy Does Not Oppose Petitions to Intervene in Yucca Mountain NRC Proceeding DOE Does Not Oppose Petitions to Intervene in Yucca Mountain NRC Proceeding March 30, 2010 - 9:57am Addthis The U.S. Department of Energy yesterday filed with the Nuclear Regulatory Commission a response to Petitions to Intervene filed by several parties seeking to oppose the Department's motion to withdraw its license application for a nuclear waste repository at Yucca Mountain. DOE said it is

  16. 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.

    2013-07-01

    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

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

    National Nuclear Security Administration (NNSA)

    Overview of DOE and NRC Reporting to NMMSS Similarities, Differences, and Challenges John Ballard, DOE Reconciliation Mary McConnell, NRC Reconciliation LINK Technologies Reporting to NMMSS Regulatory Compliance DOE Reporting Requirements NRC Reporting Requirements Resources 2 Regulatory Compliance DOE regulatory questions? - Contact Pete Dessaules DOE NMMSS Program Manager 301-903-4525 pete.dessaules@nnsa.doe.gov NRC regulatory questions? - Contact Brian Horn NRC NMMSS Program Manager

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

    SciTech Connect (OSTI)

    1995-06-01

    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.

  19. NRC TLD direct radiation monitoring network: Progress report, July--September 1997. Volume 17, Number 3

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1998-01-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated by the NRC in cooperation with participating states to provide continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. Ambient radiation levels result from naturally occurring radionuclides present in the soil, cosmic radiation constantly bombarding the earth from outer space, and the contribution, if any, from the monitored facilities and other man-made sources. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the third quarter of 1996. A complete listing of the site facilities monitored is included. In some instances, two power reactor facilities are monitored by the same set of dosimeters (e.g., Kewaunee and Point Beach).

  20. General statement of policy and procedures for NRC enforcement actions: Enforcement policy. Revision 1

    SciTech Connect (OSTI)

    1998-05-01

    This document includes the US Nuclear Regulatory Commission`s (NRC`s or Commission`s) revised General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy) as it was published in the Federal Register on May 13, 1998 (63 ER 26630). The Enforcement Policy is a general statement of policy explaining the NRC`s policies and procedures in initiating enforcement actions, and of the presiding officers and the Commission in reviewing these actions. This policy statement is applicable to enforcement matters involving the radiological health and safety of the public, including employees` health and safety, the common defense and security, and the environment.

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

    SciTech Connect (OSTI)

    Not Available

    1984-09-01

    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.

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

    SciTech Connect (OSTI)

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

    1996-12-01

    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.

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

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1997-03-01

    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.

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

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1995-03-01

    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.

  5. NRC regulatory agenda: Semiannual report, January--June 1995. Volume 14, Number 1

    SciTech Connect (OSTI)

    1995-09-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1995. Section 1, ``Rules,`` includes (A) rules on which final action has been taken since December 30, 1994, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ``Petitions for Rulemaking,`` includes (A) petitions denied or incorporated into final rules since December 30, 1994; (B) petitions incorporated into proposed rules; (C) petitions pending staff review, and (D) petitions with deferred action.

  6. Web-Based Training on Reviewing Dose Modeling Aspects of NRC Decommissioning and License Termination Plans

    SciTech Connect (OSTI)

    LePoire, D.; Cheng, J.J.; Kamboj, S.; Arnish, J.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

    2008-01-15

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course was developed in 2006 and 2007 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The objective of this course is to train NRC headquarters and regional office staff on how to review sections of a licensee's DP or LTP that pertain to dose modeling. The DP generally refers to the decommissioning of non-reactor facilities, while the LTP refers specifically to the decommissioning of reactors. This review is part of the NRC's licensing process, in which the NRC determines if a licensee has provided a suitable technical basis to support derived concentration guideline levels (DCGLs)1 or dose modeling analyses performed to demonstrate compliance with dose-based license termination rule criteria. This type of training is one component of an organizational management system. These systems 'use a range of practices to identify, create, represent, and distribute knowledge for reuse, awareness and learning'. This is especially important in an organization undergoing rapid change or staff turnover to retain organizational information and processes. NRC is committed to maintaining a dynamic program of training, development, and knowledge transfer to ensure that the NRC acquires and maintains the competencies needed to accomplish its mission. This paper discusses one specific project

  7. Comparison Evaluation of the PFP FSAR and NRC Regulatory Guide 3.39 with DOE-STD-3009-94

    SciTech Connect (OSTI)

    OSCARSON, E.E.

    2000-07-28

    One of the Plutonium Finishing Plant's (PFP) current Authorization Basis (AB) documents is the Final Safety Analysis Report (FSAR). This FSAR (HNF-SD-CP-SAR-02 1) was prepared to the format and content guidance specified in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 3.39, Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants (RG 3.39). In April 1992, the US Department of Energy (DOE) issued DOE Order 5480.23 which established the FSAR requirements for DOE nonreactor nuclear facilities. In 1994, DOE issued DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, which is a format and content guide addressing the preparation of FSARs in accordance with DOE Order 5480.23. During the initial preparation and issuance of the PFP FSAR the format and content guidance contained in NRC Regulatory Guide 3.39 was utilized, since it was the most applicable guidance at the time for the preparation of Safety Analysis Reports for plutonium processing plants. With the adoption of DOE Order 5480.23 and DOE-STD-3009-94, DOE required the preparation of SARs to meet the format and content of those DOE documents. The PFP was granted an exemption to continue with RG 3.39 format for future FSAR revisions. PFP modifications and additions have required PFP FSAR modifications that have typically been prepared to the same NRC Regulatory Guide 3.39 format and content, to provide consistency with the PFP FSAR. This document provides a table comparison between the 3009 and RG 3.39 formats to validate the extent of PFP FSAR compliance with the intent of DOE Order 5480.23 and DOE-STD-3009-94. This evaluation was initially performed on Revisions 1 and 1A of the PFP FSAR. With the preparation of a Revision 2 draft to the FSAR, sections with significant changes were reevaluated for compliance and the tables were updated, as appropriate. The tables resulting from this

  8. Results from the NRC AP600 testing program at the Oregon State University APEX facility

    SciTech Connect (OSTI)

    Reyes, J.N. Jr.; Bessette, D.E.; DiMarzo, M.

    1996-03-01

    The Department of Nuclear Engineering at Oregon State University (OSU) is performing a series of confirmatory tests for the U.S. Nuclear Regulatory Commission. These tests are being conducted in the Advanced Plant Experiment (APEX) facility which is a 1/4 length scale and 1/192 volume scale integral system simulation of the Westinghouse Advanced Passive 600 MWe (AP600) plant. The purpose of the testing program is to examine AP600 passive safety system performance, particularly during long term cooling. Thus far, OSU has successfully performed ten integral system tests for the NRC. This paper presents a description of the APEX facility and summarizes the important results of the NRC test program at OSU.

  9. The NRC's SPAR Models: Current Status, Future Development, and Modeling Issues

    SciTech Connect (OSTI)

    Robert F. Buell

    2008-09-01

    Probabilistic risk assessments (PRAs) play an increasingly important role in the regulatory framework of the U.S. nuclear power industry. The Nuclear Regulatory Commission (NRC) relies on a set of plant-specific Standardized Plant Analysis Risk (SPAR) models to provide critical risk-based input to the regulatory process. The Significance Determination Process (SDP), Management Directive 8.3 - NRC Incident Investigation Program, Accident Sequence Precursor (ASP) and Mitigating Systems Performance Index (MSPI) programs are among the regulatory initiatives that receive significant input from the SPAR models. Other uses of the SPAR models include: Screening & Resolution of Generic Safety Issues, License Amendment reviews and Notice of Enforcement Discretion (NOEDs). This paper presents the current status of SPAR model development activities, future development objectives, and issues related to the development, verification and maintenance of the SPAR models.

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

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

    Nuclear Regulatory Commission Input to DOE Request for Information/RFI (Federal Register / Vol. 75, No. 180 / Friday, September 17, 2010/Pages 57006-57011 / Notices) / Smart Grid Implementation Input - NRC Contact: Kenn A. Miller, Office of Nuclear Reactor Regulation, 301-415-3152 Comments relevant to the following two sections of the RFI: "Long Term Issues: Managing a Grid with High Penetration of New Technologies" and "Reliability and Cyber-Security," Page 57010. Nuclear

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

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

    What Else We Might Do | Department of Energy Social Media and the NRC: What We're Doing, Why We're Doing It, and What Else We Might Do Social Media and the NRC: What We're Doing, Why We're Doing It, and What Else We Might Do Social Media and the NRC: What We're Doing, Why We're Doing It, and What Else We Might Do (123.05 KB) More Documents & Publications Social Media for Natural Disaster Response and Recovery Marketing & Driving Demand: Social Media Tools & Strategies - January

  12. NRC (Nuclear Regulatory Commission) staff evaluation of the General Electric Company Nuclear Reactor Study (''Reed Report'')

    SciTech Connect (OSTI)

    1987-07-01

    In 1975, the General Electric Company (GE) published a Nuclear Reactor Study, also referred to as ''the Reed Report,'' an internal product-improvement study. GE considered the document ''proprietary'' and thus, under the regulations of the Nuclear Regulatory Commission (NRC), exempt from mandatory public disclosure. Nonetheless, members of the NRC staff reviewed the document in 1976 and determined that it did not raise any significant new safety issues. The staff also reached the same conclusion in subsequent reviews. However, in response to recent inquiries about the report, the staff reevaluated the Reed Report from a 1987 perspective. This re-evaluation, documented in this staff report, concluded that: (1) there are no issues raised in the Reed Report that support a need to curtail the operation of any GE boiling water reactor (BWR); (2) there are no new safety issues raised in the Reed Report of which the staff was unaware; and (3) although certain issues addressed by the Reed Report are still being studied by the NRC and the industry, there is no basis for suspending licensing and operation of GE BWR plants while these issues are being resolved.

  13. NRC staff review of licensee responses to pressure-locking and thermal-binding issue

    SciTech Connect (OSTI)

    Rathbun, H.J.

    1996-12-01

    Commercial nuclear power plant operating experience has indicated that pressure locking and thermal binding represent potential common mode failure mechanisms that can cause safety-related power-operated gate valves to fail in the closed position, thus rendering redundant safety-related systems incapable of performing their safety functions. In Generic Letter (GL) 95-07, {open_quotes}Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves,{close_quotes} the U.S. Nuclear Regulatory Commission (NRC) staff requested that nuclear power plant licensees take certain actions to ensure that valves susceptible to pressure locking or thermal binding are capable of performing their safety functions within the current licensing bases of the facility. The NRC staff has received summary information from licensees in response to GL 95-07 describing actions they have taken to prevent the occurrence of pressure locking and thermal binding. The NRC staff has developed a systematic process to help ensure uniform and consistent review of licensee submittals in response to GL 95-07.

  14. Approach to compliance with the NRC substantially complete containment requirement at the potential repository at Yucca Mountain

    SciTech Connect (OSTI)

    Stahl, D.; Nesbit, S.P.; Berkowitz, L.

    1995-12-01

    An approach to compliance with the U.S. Nuclear Regulatory Commission (NRC) substantially complete containment (SCC) requirement found in the Title 10 Part 60 of the Code of Federal Regulations (CFR) was developed by the Department of Energy (DOE). The approach is consistent with the regulation and is based on a new performance goal of a mean waste-package lifetime well in excess of 1,000 years. The NRC considers that achieving the DOE goal would be a reasonable implementation of the SCC requirement. The NRC has asked several additional questions. The DOE has responded to these questions and the DOE and the NRC are engaged in an ongoing dialog to resolve them.

  15. The 1997 NRC IST workshops and the status of questions and issues directed to the ASME O and M committee

    SciTech Connect (OSTI)

    DiBiasio, A.M.

    1998-05-01

    This paper describes the results of the four NRC Inservice Testing (IST) Workshops which were held in early 1997 pertaining to NRC Inspection Procedure P 73756, Inservice Testing of Pumps and Valves. It also presents the status of the ASME code committees` resolution of certain questions forwarded to the ASME by the NRC. These questions relate to code interpretations, inconsistencies in the code, and industry concerns that are most appropriately resolved through the ASME consensus process. The ASME committees reviewed the questions at their December 1997 and March 1998 code meetings. Of particular interest are those questions for which the ASME code committees did not agree with the NRC response. These questions, as well as those which the committees provided some additional insight or input, are presented in this paper.

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

    National Nuclear Security Administration (NNSA)

    3 Recognitions Brian Horn, NRC Pete Dessaules, DOE/NNSA NRC requirements for Inventory Reporting and Reconciliation  Report Inventory to NMMSS * < 30 days - IAEA selected facilities, Cat-1 sites * < 45 days - Cat-2 sites * < 60 days - Reactors, Cat-3 sites, >350 gram licensees * Prior to March 31 st - licensees authorized < 350 grams fissile * As of Sept. 30 th - Foreign obligated source material holdings  Reconcile inventory with NMMSS within 30 days of submission 2

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

    National Nuclear Security Administration (NNSA)

    STATE OF NMMSS Brian Horn, NRC Peter Dessaules, DOE/NNSA Overview  NMMSS has had a highly successful year in which it reduced reconciliation and closing times, improved report products, and delivered commitments to DOE/NNSA, NRC, and other government agencies on schedule.  This would not be possible without your efforts. 2 Mission Statement  NMMSS is the U.S. Government's official information system containing current and historical accounting data and other related nuclear material

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

    National Nuclear Security Administration (NNSA)

    U.S. NRC Nuclear Export Controls: Implementing the NSG Trigger List Gary R. Langlie Licensing Officer Office of International Programs May 11-14, 2015 NRC's Mission 2 License and regulate the Nation's civilian use of byproduct, source, and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment. Legal Basis * Atomic Energy Act of 1954, as amended * Nuclear Non-Proliferation Act of 1978 * Treaties,

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

    SciTech Connect (OSTI)

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

    2003-01-01

    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.

  20. 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.

    1993-12-01

    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.

  1. Comparisons of ANS, ASME, AWS, and NFPA standards cited in the NRC standard review plan, NUREG-0800, and related documents

    SciTech Connect (OSTI)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Spiesman, J.B.

    1995-11-01

    This report provides the results of comparisons of the cited and latest versions of ANS, ASME, AWS and NFPA standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC`s Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review.

  2. Managing aging in nuclear power plants: Insights from NRC`s Maintenance Team Inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.

    1992-12-31

    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 sixty-seven of the reports issued on these in-depth team inspections have been 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 structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports 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.

  3. Managing aging in nuclear power plants: Insights from NRC's Maintenance Team Inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.

    1992-01-01

    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 sixty-seven of the reports issued on these in-depth team inspections have been 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 structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports 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.

  4. 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.

    2009-10-09

    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.

  5. Going the Distance? NRC's Response to the National Academy of Science's Transportation Study

    SciTech Connect (OSTI)

    Easton, E.P.; Bajwa, C.S.

    2008-07-01

    In February 2006, the National Academy of Sciences (NAS) published the results of a 3 1/2-year study, titled Going the Distance, that examined the safety of transporting spent nuclear fuel (SNF) and high level waste (HLW) in the United States. NAS initiated this study to address what it perceived to be a national need for an independent, objective, and authoritative analysis of SNF and HLW transport in the United States. The study was co-sponsored by the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Energy (DOE), the U.S. Department of Transportation (DOT), the Electric Power Research Institute and the National Cooperative Highway Research Program. This paper addresses some of the recommendations made in the NAS study related to the performance of SNF transportation casks in long duration fires, the use of full-scale package testing, and the need for an independent review of transportation security prior to the commencement of large scale shipping campaigns to an interim storage site or geologic repository. In conclusion: The NRC believes that the current regulations in 10 CFR Part 71 for the design of SNF and HLW transportation packages provide a very high level of protection to the public for very severe accidents and credible threat scenarios. As recommended by the NAS study, additional studies of accidents involving severe fires have been completed. These studies have confirmed that spent fuel casks would be expected to withstand very severe fires without the release of any fission products from the spent fuel. Additionally, changes in rail operating procedures such as the use of dedicated trains and prohibition on the co-location of SNF and flammable liquids in rail tunnels can further reduce the already low probability of severe rail accident fires involving SNF and HLW. (authors)

  6. 1995 revisions to the DOT/NRC transport regulations and their impact on nuclear power plants

    SciTech Connect (OSTI)

    Grella, A.W.

    1996-10-01

    On September 28, 1995, the U.S. Department of Transportation (DOT) and the U.S. Nuclear Regulatory Commission (NRC) published major amendments to the nuclear transportation regulations of the US. The amendments culminated an approximate 8-year effort of the two agencies to conform US regulations (to the extent practicable) to the international transport standards of the International Atomic Energy Agency (IAEA) Safety Series N. 6, {open_quotes}Regulations For The Safe Transport of Radioactive Material{close_quotes}, 1985 Edition (Revised 1990). This paper identifies the major revisions to the regulations which have taken place and discusses not only their probable future impacts but also identifies certain issues and early impacts which have been emerging since publication of the final rules late in 1995. The discussion is summarized with respect to these impacts and issues on transportation of radioactive material by the nuclear power industry. Many of the revisions which are more minor in nature are also identified. The generic effective date for mandatory compliance with the revised regulations was April 1, 1996, however two of the major revisions of interest to the utilities have later effective dates for mandatory compliance. The use of the so-called {open_quotes}NRC-Certified Type A LSA Packages{close_quotes} are authorized until April 1, 1999 and mandatory compliance with the new radiation protection program requirements of 49 CFR 172 Subpart I is not until October 1, 1997. This paper is based to a large extent on the EPRI report bearing the same title as this paper, which is currently in draft.

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

    SciTech Connect (OSTI)

    Struckmeyer, R.

    1996-03-01

    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. A commentary on the 1995 DOT/NRC amendments to the U.S. nuclear transportation regulations

    SciTech Connect (OSTI)

    Grella, A.

    1996-07-01

    This article discusses the major revisions (1995 DOT/NRC ammendments) to the US Nuclear Transportation regulations and their probable impacts on transportation. Areas covered include the following: the LSA and SCO definitions and packaging; radiation protection programs; mandatory use of SI units; changes an additions to the table of A1/A2 radionuclide values; and additional type B package hypothetical accident parameters.

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

    SciTech Connect (OSTI)

    Geelhood, Kenneth J.

    2011-12-31

    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.

  10. A regulator`s perspective on NRC`s participation in the operations & maintenance committees

    SciTech Connect (OSTI)

    Wessman, R.H.

    1996-12-01

    As a regulator fairly new to the American Society of Mechanical Engineers (ASME) Operations and Maintenance (O&M) Committee process, the author does not have a personal historical perspective as do many of the longer-term, and highly respected, members of the O&M Committee. However, as Branch Chief of the Mechanical Engineering Branch, Division of Engineering, in the Office of Nuclear Reactor Regulation at the NRC for just over two years, he has responsibility for the regulatory agency`s review of licensee actions involving the products that come from the efforts of the O&M Committee, as well as responsibility for portions of the activities of interest to other ASME Code groups such as Section III, Section XI, and Qualification of Mechanical Equipment. As a result, the author has learned a great deal about the code process in a short time. Here he gives his perspectives on the process and provides a few thoughts on the direction for the future.

  11. Data Quality Assurance Program Plan for NRC Division of Risk Analysis Programs at the INL

    SciTech Connect (OSTI)

    Sattison, Martin B.; Wierman, Thomas E.; Vedros, Kurt G.; Germain, Shawn W. St.; Eide, Steven A.; Sant, Robert L.

    2009-07-01

    The Division of Risk Analysis (DRA), Office of Nuclear Regulatory Research (RES), must ensure that the quality of the data that feed into its programs follow Office of Management and Budget (OMB) and U.S. Nuclear Regulatory Commission (NRC) guidelines and possibly other standards and guidelines used in nuclear power plant risk analyses. This report documents the steps taken in DRAs Data Quality Improvement project (Job Control Number N6145) to develop a Data Quality Assurance Program Plan. These steps were 1. Conduct a review of data quality requirements 2. Review current data programs, products, and data quality control activities 3. Review the Institute of Nuclear Power Operation (INPO) Equipment Performance and Information Exchange (EPIX) data quality programs and characterize the EPIX data quality and uncertainty 4. Compare these programs, products, and activities against the requirements 5. Develop a program plan that provides assurance that data quality is being maintained. It is expected that the Data Quality Assurance Program Plan will be routinely implemented in all aspects of future data collection and processing efforts and that specific portions will be executed annually to provide assurance that data quality is being maintained.

  12. ISDAC - NRC Convair-580 Flight Hours Date Flight From To Start

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

    - NRC Convair-580 Flight Hours Date Flight From To Start End hrs 03/21/08 F01-Test-01 Ottawa Ottawa 16:15Z 18:15Z 2.2 03/22/08 F02-Test-02 Ottawa Ottawa 12:45Z 15:50Z 3.3 03/28/08 F03-Transit-01 Ottawa, ON Kenora, ON 12:23Z 15:44Z 3.6 03/28/08 F04-Transit-02 Kenora, ON Calgary, AB 16:30Z 19:36Z 3.3 03/28/08 F05-Transit-03 Calgary, AB Comox, BC 20:24Z 22:17Z 2.1 03/29/08 F06-Transit-04 Comox, BC Whitehorse, YK 17:43Z 20:50Z 3.3 03/29/08 F07-Transit-05 Whitehorse, YK Fairbanks 21:51Z 23:42Z 2.1

  13. 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.

    1997-04-01

    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.

  14. Transition from Consultation to Monitoring-NRC's Increasingly Focused Review of Factors Important to F-Area Tank Farm Facility Performance - 13153

    SciTech Connect (OSTI)

    Barr, Cynthia; Grossman, Christopher; Alexander, George; Parks, Leah; Fuhrmann, Mark; Shaffner, James; McKenney, Christepher; Pabalan, Roberto; Pickett, David; Dinwiddie, Cynthia

    2013-07-01

    In consultation with the NRC, DOE issued a waste determination for the F-Area Tank Farm (FTF) facility in March 2012. The FTF consists of 22 underground tanks, each 2.8 to 4.9 million liters in capacity, used to store liquid high-level waste generated as a result of spent fuel reprocessing. The waste determination concluded stabilized waste residuals and associated tanks and auxiliary components at the time of closure are not high-level and can be disposed of as LLW. Prior to issuance of the final waste determination, during the consultation phase, NRC staff reviewed and provided comments on DOE's revision 0 and revision 1 FTF PAs that supported the waste determination and produced a technical evaluation report documenting the results of its multi-year review in October 2011. Following issuance of the waste determination, NRC began to monitor DOE disposal actions to assess compliance with the performance objectives in 10 CFR Part 61, Subpart C. To facilitate its monitoring responsibilities, NRC developed a plan to monitor DOE disposal actions. NRC staff was challenged in developing a focused monitoring plan to ensure limited resources are spent in the most cost-effective manner practical. To address this challenge, NRC prioritized monitoring areas and factors in terms of risk significance and timing. This prioritization was informed by NRC staff's review of DOE's PA documentation, independent probabilistic modeling conducted by NRC staff, and NRC-sponsored research conducted by the Center for Nuclear Waste Regulatory Analyses in San Antonio, TX. (authors)

  15. 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

    1999-07-01

    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.

  16. Uranium-Loaded Water Treatment Resins: 'Equivalent Feed' at NRC and Agreement State-Licensed Uranium Recovery Facilities - 12094

    SciTech Connect (OSTI)

    Camper, Larry W.; Michalak, Paul; Cohen, Stephen; Carter, Ted

    2012-07-01

    Community Water Systems (CWSs) are required to remove uranium from drinking water to meet EPA standards. Similarly, mining operations are required to remove uranium from their dewatering discharges to meet permitted surface water discharge limits. Ion exchange (IX) is the primary treatment strategy used by these operations, which loads uranium onto resin beads. Presently, uranium-loaded resin from CWSs and mining operations can be disposed as a waste product or processed by NRC- or Agreement State-licensed uranium recovery facilities if that licensed facility has applied for and received permission to process 'alternate feed'. The disposal of uranium-loaded resin is costly and the cost to amend a uranium recovery license to accept alternate feed can be a strong disincentive to commercial uranium recovery facilities. In response to this issue, the NRC issued a Regulatory Issue Summary (RIS) to clarify the agency's policy that uranium-loaded resin from CWSs and mining operations can be processed by NRC- or Agreement State-licensed uranium recovery facilities without the need for an alternate feed license amendment when these resins are essentially the same, chemically and physically, to resins that licensed uranium recovery facilities currently use (i.e., equivalent feed). NRC staff is clarifying its current alternate feed policy to declare IX resins as equivalent feed. This clarification is necessary to alleviate a regulatory and financial burden on facilities that filter uranium using IX resin, such as CWSs and mine dewatering operations. Disposing of those resins in a licensed facility could be 40 to 50 percent of the total operations and maintenance (O and M) cost for a CWS. Allowing uranium recovery facilities to treat these resins without requiring a license amendment lowers O and M costs and captures a valuable natural resource. (authors)

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

    SciTech Connect (OSTI)

    First, M.W.

    1991-02-01

    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)

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

    SciTech Connect (OSTI)

    Not Available

    2004-09-01

    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.

  19. Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans.

    SciTech Connect (OSTI)

    LePoire, D.; Arnish, J.; Cheng, J. J.; Kamboj, S.; Richmond, P.; Chen, S. Y.; Barr, C.; McKenney, C.; Environmental Science Division; NRC

    2007-01-01

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course is being developed in 2006 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The training course consists of the core and advanced modules tailored to specific NRC job functions. Topics for individual modules include identifying the characteristics of simple and complex sites, identifying when outside expertise or consultation is needed, demonstrating how to conduct acceptance and technical reviews of dose modeling, and providing details regarding the level of justification needed for realistic scenarios for both dose modeling and derivation of DCGLs. Various methods of applying probabilistic uncertainty analysis to demonstrate compliance with dose-based requirements are presented. These approaches include: (1) modeling the pathways of radiological exposure and estimating doses to receptors from a combination of contaminated media and radionuclides, and (2) using probabilistic analysis to determine an appropriate set of input parameters to develop derived concentration guideline limits or DCGLs (DCGLs are media- and nuclide-specific concentration limits that will meet dose-based, license termination rule criteria found in 10 CFR Part 20, Subpart E). Calculation of operational (field) DCGL's from media- and nuclide-specific DCGLs and use of operational DCGLs in conducting

  20. Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans

    SciTech Connect (OSTI)

    LePoire, D.; Arnish, J.; Cheng, J.J.; Kamboj, S.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

    2007-07-01

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course is being developed in 2006 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The training course consists of the core and advanced modules tailored to specific NRC job functions. Topics for individual modules include identifying the characteristics of simple and complex sites, identifying when outside expertise or consultation is needed, demonstrating how to conduct acceptance and technical reviews of dose modeling, and providing details regarding the level of justification needed for realistic scenarios for both dose modeling and derivation of DCGLs. Various methods of applying probabilistic uncertainty analysis to demonstrate compliance with dose-based requirements are presented. These approaches include 1) modeling the pathways of radiological exposure and estimating doses to receptors from a combination of contaminated media and radionuclides, and 2) using probabilistic analysis to determine an appropriate set of input parameters to develop derived concentration guideline limits or DCGLs (DCGLs are media- and nuclide-specific concentration limits that will meet dose-based, license termination rule criteria found in 10 CFR Part 20, Subpart E). Calculation of operational (field) DCGL's from media- and nuclide-specific DCGLs and use of operational DCGLs in conducting

  1. NRC Waste Incidental to Reprocessing Program: Overview of Consultation and Monitoring Activities at the Idaho National Laboratory and the Savannah River Site - What We Have Learned - 12470

    SciTech Connect (OSTI)

    Suber, Gregory

    2012-07-01

    In 2005 the U.S. Nuclear Regulatory Commission (NRC) began to implement a new set of responsibilities under the Ronald W. Reagan National Defense Authorization Act (NDAA) of Fiscal Year 2005. Section 3116 of the NDAA requires the U.S. Department of Energy (DOE) to consult with the NRC for certain non-high level waste determinations and also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2005, the NRC staff began consulting with DOE and completed reviews of draft waste determinations for salt waste at the Savannah River Site. In 2006, a second review was completed on tank waste residuals including sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center Tank Farm at the Idaho National Laboratory. Monitoring Plans were developed for these activities and the NRC is actively monitoring disposal actions at both sites. NRC is currently in consultation with DOE on the F-Area Tank Farm closure and anticipates entering consultation on the H-Area Tank Farm at the Savannah River Site. This paper presents, from the NRC perspective, an overview of how the consultation and monitoring process has evolved since its conception in 2005. It addresses changes in methods and procedures used to collect and develop information used by the NRC in developing the technical evaluation report and monitoring plan under consultation and the implementation the plan under monitoring. It will address lessons learned and best practices developed throughout the process. The NDAA has presented significant challenges for the NRC and DOE. Past and current successes demonstrate that the NDAA can achieve its intended goal of facilitating tank closure at DOE legacy defense waste sites. The NRC believes many of the challenges in performing the WD reviews have been identified and addressed. Lessons learned have been collected and documented throughout the review process. Future success will be contingent on each agencies commitment to

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

    National Nuclear Security Administration (NNSA)

    Inspection Summary Plant: Oyster Creek Region: I Inspection Date: 5/18 - 5/19/2010  Violation: None  Observations: (minor) - Issue Report clarity - Missing move sheet signature that we self identified in the FASA - SNM in the flammable materials section of the warehouse is not a violation but is not a good practice  Comments: - NRC Inspector preferred not doing this during an outage, but doing it when there are Reactor Services available to move the bridge and perform 10-15 bundle spot

  3. 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

    2012-07-01

    '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

  4. 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; Mintz, Todd; He, Xihua; Pabalan, Roberto; Miller, Larry

    2013-07-01

    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

  5. Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX

    SciTech Connect (OSTI)

    Langenbuch, S.; Schmidt, K.-D.; Velkov, K.

    2004-10-15

    The OECD/NRC boiling water reactor (BWR) turbine trip benchmark has been calculated by the coupled thermal-hydraulic neutronics system code ATHLET-QUABOX/CUBBOX developed by Gesellschaft fuer Anlagen- und Reaktorsicherheit. The results obtained for all three exercises and for the additional four hypothetical cases are presented. The physical phenomena determining the BWR pressure transient are studied and explained. The sensitivity of results to variations of the initial steady-state conditions and of parameters of the two-phase flow model is discussed. A comparison is also performed for exercise 2 between the reactor core model with 33 thermal-hydraulic channels (THCs) as specified and a reactor core model with 764 THCs using a 1:1 mapping scheme.

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

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    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.

  7. 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

    2011-03-01

    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.

  8. Use of Circadian Lighting System to improve night shift alertness and performance of NRC Headquarters Operations Officers

    SciTech Connect (OSTI)

    Baker, T.L.; Morisseau, D.; Murphy, N.M.

    1995-04-01

    The Nuclear Regulatory Commission`s (NRC) Headquarters Operations Officers (HOOs) receive and respond to events reported in the nuclear industry on a 24-hour basis. The HOOs have reported reduced alertness on the night shift, leading to a potential deterioration in their on-shift cognitive performance during the early morning hours. For some HOOs, maladaptation to the night shift was also reported to be the principal cause of: (a) reduced alertness during the commute to and from work, (b) poor sleep quality, and (c) personal lifestyle problems. ShiftWork Systems, Inc. (SWS) designed and installed a Circadian Lighting System (CLS) at both the Bethesda and Rockville HOO stations with the goal of facilitating the HOOs physiological adjustment to their night shift schedules. The data indicate the following findings: less subjective fatigue on night shifts; improved night shift alertness and mental performance; higher HOO confidence in their ability to assess event reports; longer, deeper and more restorative day sleep after night duty shifts; swifter adaptation to night work; and a safer commute, particularly for those with extensive drives.

  9. NRC_Letter.pdf

    Office of Legacy Management (LM)

  10. NRC Form 741

    National Nuclear Security Administration (NNSA)

    A 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 4 YYY XXX 1 31 20 50397.00 2335.00 03 31 2008 1 FAB FUEL ELE -1 1 20 309 J 2 M 377609.00 4.7962 18111.00 2 3 4 FAB FUEL ELE -2 FAB FUEL ELE -3 FAB FUEL ELE -4 1 1 1 20 20 20 309 309 309 J J J 2 2 2 M M M 42114.00 377855.00 41992.00 107 107 3.1913 4.7960 3.1911 1344.00 18122.00 1340.00 30 30 20358 Example 1-a

  11. 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.

    1994-08-01

    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.

  12. 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.

    2012-08-01

    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.

  13. NRC Fact-Finding Task Force report on the ATWS event at Salem Nuclear Generating Station, Unit 1, on February 25, 1983

    SciTech Connect (OSTI)

    Not Available

    1983-03-01

    An NRC Region I Task Force was established on March 1, 1983 to conduct fact finding and data collection with regard to the circumstances which led to an anticipated transient without scram (ATWS) event at the Public Service Electric and Gas Company's Salem Generating Station, Unit 1 on February 25, 1983. The charter of the Task Force was to determine the factual information pertinent to management and administrative controls which should have ensured proper operation of the reactor trip breakers in the solid state protection system. This report documents the findings of the Task Force along with its conclusions.

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

    National Nuclear Security Administration (NNSA)

    Use of NMMSS Data in Support of the American Medical Isotopes Production Act of 2012 Peter Habighorst Nuclear Regulatory Commission Background * Section 3175 of the act requires: - Chairman of NRC, after consulting with other relevant agencies, to submit to Congress by January 2, 2014 a report detailing certain U.S. exports of High Enriched Uranium (HEU)* * Uranium enriched to 20% or more in U-235 2 Information in report * "Current" disposition of U.S. exports of HEU used as fuel or

  15. May 20, 2015 Webinar - Guidance for Conducting Technical Analyses...

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

    Performance & RIsk Assessment (P&RA) Community of Practice (CoP) Webinar - May 20, 2015 - Guidance for Conducting Technical Analyses for 10 CFR Part 61 by Mr. Chris Grossman (NRC) ...

  16. Validation of seismic soil-structure interaction analysis methods: EPRI (Electric Power Research Institute)/NRC (Nuclear Regulatory Commission) cooperation in Lotung, Taiwan, experiments

    SciTech Connect (OSTI)

    Kot, C.A.; Srinivasan, M.G.; Hsieh, B.J.; Tang, Y.K.; Kassawara, R.P.

    1986-10-31

    The cooperative program between NRC/ANL and EPRI on the validation of soil-structure interaction analysis methods with actual seismic response data is described. A large scale-model of a containment building has been built by EPRI/Taipower in a highly seismic region of Taiwan. Vibration tests were performed, first on the basemat before the superstructure was built and then on the completed structure. Since its completion, the structure has experienced many earthquakes. The site and structural response to these earthquakes have been recorded with field (surface and downhole) and structural instrumentation. The validation program involves blind predictions of site and structural response during vibration tests and a selected seismic event, and subsequent comparison between the predictions and measurements. The predictive calculations are in progress. The results of the correlation are expected to lead to the evaluation of the methods as to their conservatisms and sensitivities.

  17. 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.; Hudson, N.

    2012-07-01

    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)

  18. Bar coded air sample tracking and bar coded loose surface contamination sample tracking: How it can assist in compliance with the DOE`s new 10 CFR 835 and the NRC`s new 10 CFR 20 regulations

    SciTech Connect (OSTI)

    Bailey, W.H.

    1994-12-31

    The paper describes advance sample tracking and processing techniques which utilize bar code technology for field data collection and count room analysis. Techniques described by the paper include bar coded area air sampling, bar coded portable breathing zone air sampling, and bar coded loose surface contamination sampling. Bar coded sample tracking is explored to demonstrate how it can assist in compliance with new DOE 10 CFR 835 and NRC 10 CFR 20 requirements. Operation of portable bar code readers is explored to provide insight to the advantages of bar coded sample tracking and corresponding sample trending analyses. Case studies involving bar coded sample tracking systems which are in use at NRC facilities, DOE sites, and decommission projects are discussed.

  19. HUMAN FACTORS GUIDANCE FOR CONTROL ROOM EVALUATION

    SciTech Connect (OSTI)

    OHARA,J.; BROWN,W.; STUBLER,W.; HIGGINS,J.; WACHTEL,J.; PERSENSKY,J.J.

    2000-07-30

    The Human-System Interface Design Review Guideline (NUREG-0700, Revision 1) was developed by the US Nuclear Regulatory Commission (NRC) to provide human factors guidance as a basis for the review of advanced human-system interface technologies. The guidance consists of three components: design review procedures, human factors engineering guidelines, and a software application to provide design review support called the ``Design Review Guideline.'' Since it was published in June 1996, Rev. 1 to NUREG-0700 has been used successfully by NRC staff, contractors and nuclear industry organizations, as well as by interested organizations outside the nuclear industry. The NRC has committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool in the face of emerging and rapidly changing technology. This paper addresses the current research to update of NUREG-0700 based on the substantial work that has taken place since the publication of Revision 1.

  20. 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.

    1994-07-01

    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.

  1. 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

    1994-08-01

    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.

  2. Standards, Guidance and Practices for Improved Data Quality

    SciTech Connect (OSTI)

    Martin B. Sattison

    2010-06-01

    Since the mid 1980s, the Idaho National Laboratory (INL) has been involved with numerous projects to collect operational reactor data, develop data tools, and trend and analyze that data for the U.S. Nuclear Regulatory Commission (NRC). Because the data are used in subsequent risk analyses, the NRC must have confidence in the quality of the data delivered. The NRC tasked the INL to establish a comprehensive data quality assurance program. A key element of that effort was to establish a set of requirements based on industry and government standards, guidance and good practices. This paper discusses where these were found, the process of extracting the requirements and recommendations from the source materials, and the consolidation of them into a concise set of 22 standards, guidance and practices for technical data quality. While this set was created specifically for the data programs within the NRC’s Office of Research, they have broad application to many high-technology industries.

  3. 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)

    1996-05-01

    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.

  4. 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 NUCLEAll I-IEOULATOIJY COMMISSION REGION i 631 PARK A"LH"I KIN0 OF PR"ISIA. PCNNIVLVANIA ID40' Gentlemen: Subject: Inspectfon 81-15 _ "-- .,; .z .;; Thts refers to the closeout safety \nspectlon conducted by Ms. M. Campbell of this office on August 27, 1961, of activities formerly authorized by NRC

  5. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    *** Company Name and Address License Number RIS 10012007 09302008 20 E4 A 1 COMPANY NAME RIS A 2 1 1 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) ...

  6. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    .A *** Company Name and Address License Number RIS A 10012007 09302008 20 E4 A 2 1 1 1 COMPANY NAME RIS A 3 1 1 2 2 DATE SIGNATURE (See instructions for provisions on ...

  7. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    *** Company Name and Address License Number RIS A 10012007 09302008 20 E4 1 1 1 Company 1 RIS A 2 1 1 COMPANY NAME RIS A 3 1 1 DATE SIGNATURE (See instructions for ...

  8. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    .a *** Company Name and Address License Number RIS 10012007 09302008 20 E4 A 1 COMPANY NAME RIS A 2 1 1 1 1 COMPANY NAME RIS A 3 1 1 DATE SIGNATURE (See instructions for ...

  9. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    2*** Company Name and Address License Number RIS A 10012007 09302008 20 E4 1 1 1 COMPANY NAME RIS A 2 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) ...

  10. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    Example 4 *** Company Name and Address License Number RIS A 10012007 09302008 20 E4 1 1 1 A 2 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) TITLE ...

  11. NRC Licensing Strategy Development for the NGNP

    SciTech Connect (OSTI)

    Mark R. Holbrook; Trevor Cook

    2008-09-01

    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.

  12. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    1 *** Company Name RIS 09/30/2008 A E4 864 1 1 90% J 1 STANDARD 5

  13. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    2 *** Company Name RIS 09/30/2008 A E4 864 1 1 90% J 1 STANDARD 3

  14. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    3.A *** Company Name RIS 09/30/2008 A E4 864 2 2 90 J 1 STANDARDS 2 2 2 2

  15. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    EXAMPLE 4 *** Company Name RIS 09/30/2008 A 864 0 0 90 J 1 1 A 864 0 0 90 J 2 2 1* 1* E4 E2 E1 864 0 90 J 3 2 A 0 4 *Reporting itemized inventory Total U U-235 E1 = 0.4 0.001 E2 = 0.4 0.11 E4 = 0.4 0.39 Total: 1.2 0.501

  16. Guidance for Developing Principal Design Criteria for Advanced (Non-Light Water) Reactors

    SciTech Connect (OSTI)

    Holbrook, Mark; Kinsey, Jim

    2015-03-01

    In July 2013, the US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) established a joint initiative to address a key portion of the licensing framework essential to advanced (non-light water) reactor technologies. The initiative addressed the “General Design Criteria for Nuclear Power Plants,” Appendix A to10 Code of Federal Regulations (CFR) 50, which were developed primarily for light water reactors (LWRs), specific to the needs of advanced reactor design and licensing. The need for General Design Criteria (GDC) clarifications in non-LWR applications has been consistently identified as a concern by the industry and varied stakeholders and was acknowledged by the NRC staff in their 2012 Report to Congress1 as an area for enhancement. The initiative to adapt GDC requirements for non-light water advanced reactor applications is being accomplished in two phases. Phase 1, managed by DOE, consisted of reviews, analyses and evaluations resulting in recommendations and deliverables to NRC as input for NRC staff development of regulatory guidance. Idaho National Laboratory (INL) developed this technical report using technical and reactor technology stakeholder inputs coupled with analysis and evaluations provided by a team of knowledgeable DOE national laboratory personnel with input from individual industry licensing consultants. The DOE national laboratory team reviewed six different classes of emerging commercial reactor technologies against 10 CFR 50 Appendix A GDC requirements and proposed guidance for their adapted use in non-LWR applications. The results of the Phase 1 analysis are contained in this report. A set of draft Advanced Reactor Design Criteria (ARDC) has been proposed for consideration by the NRC in the establishment of guidance for use by non-LWR designers and NRC staff. The proposed criteria were developed to preserve the underlying safety bases expressed by the original GDC, and recognizing that advanced reactors may take

  17. Guidance

    Broader source: Energy.gov [DOE]

    This site provides a centralized topical resource for enforceable DOE and federal health, safety and security requirements and related guidance documents. DOE’s guidance documents support understanding, ensure technical and management capabilities and collaborative improvement efforts.

  18. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2008-01-12

    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

  19. RH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-11-07

    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

  20. 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.

    1994-08-01

    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).

  1. May 20, 2015 Webinar - Guidance for Conducting Technical Analyses for 10

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

    CFR Part 61 | Department of Energy 20, 2015 Webinar - Guidance for Conducting Technical Analyses for 10 CFR Part 61 May 20, 2015 Webinar - Guidance for Conducting Technical Analyses for 10 CFR Part 61 Performance & RIsk Assessment (P&RA) Community of Practice (CoP) Webinar - May 20, 2015 - Guidance for Conducting Technical Analyses for 10 CFR Part 61 by Mr. Chris Grossman (NRC) Agenda - May 20, 2015 - P&RA CoP Webinar (52.52 KB) Presentation - Guidance for Conducting Technical

  2. Guidance Systems Division ,

    Office of Legacy Management (LM)

    M. Campbell of this office on August 27, 1961, of activities formerly authorized by NRC License No. STB-424 and to the clscussions of our findings held by f4s. Campbell with ...

  3. Implementation of NUREG-1318 guidance within the Yucca Mountain Project

    SciTech Connect (OSTI)

    La Monica, L.B.; Waddell, J.D.; Hardin, E.L.

    1990-04-01

    The US Department of Energy`s Yucca Mountain Project is implementing a quality assurance program that fulfills the requirements of the US Nuclear Regulatory Commission (NRC). Additional guidance for this program was provided in NUREG 1318, ``Technical Position on Items and Activities in the High-Level Waste Geologic Repository Program Subject to Quality Assurance Requirements`` for identification of items and activities important to public radiological safety and waste isolation. The process and organization for implementing this guidance is discussed. 3 refs., 2 figs.

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

    SciTech Connect (OSTI)

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

    1996-08-01

    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).

  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.

    2009-10-01

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

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

    for restoration of offsite power following a loss-of-grid ... generation such as wind and solar will have to be ... grid stability and operating parameters in accordance ...

  7. DOE Petitions for NRC Review in Yucca Mountain Proceeding

    Broader source: Energy.gov [DOE]

    The United States Department of Energy today filed with the Nuclear Regulatory Commission a petition requesting that the Commission review and reverse an order by the NRC’s Atomic Safety and...

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

    SciTech Connect (OSTI)

    mubayi v.

    2013-09-22

    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.

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

    Open Energy Info (EERE)

    government agencies and companies, the institute researches, develops and tests new hydrogen and fuel cell systems. Additionally, the Advanced Testing and Validation Centre...

  10. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    A M 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 4 1 31 20 -1405.00 -93.00 2 32 50 1042.00 03 31 ...

  11. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    A A M 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 2 1 32 50 -1042.00 2 32 50 1002.00 03 31 2008 004 ...

  12. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    A B 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT FOREIGN COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 2 YYY RRRR 04 05 2008 1 AH31 1 EG 309 J ...

  13. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    A A 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT FOREIGN COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 2 YYY RRRR 03 31 2008 1 AH31 1 EG 309 J ...

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

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

    0M DOENRC F 740M DOENRC Concise Note (Preprinted) DOE F 740-MX (10.4 KB) More Documents & Publications o:informsfixformsnrc740m.wpf DOENRC F 742 PHYSICAL INVENTORY LISTING

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

    National Nuclear Security Administration (NNSA)

    ... The course will include the following topics, among others: Completion of data input forms: transaction, material balance, inventory, and concise notes Demonstration of the use of ...

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

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

    Form is used in the control of nuclear material. It is a companion to DOENRC Form 742, "MATERIAL BALANCE REPORT." PHYSICAL INVENTORY LISTING (31.76 KB) More Documents & ...

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

    National Nuclear Security Administration (NNSA)

    Legal Basis * Atomic Energy Act of 1954, as amended * Nuclear Non-Proliferation Act of 1978 * Treaties, Conventions and Agreements including: - Nuclear Non-Proliferation Treaty - ...

  18. DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear...

    Energy Savers [EERE]

    an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process ...

  19. DOE Awards Contract for the Nuclear Regulatory Commission (NRC) Licensed

    Office of Environmental Management (EM)

    Compliance | Department of Energy Awards $3.7 Million to Spur Investment in Commercial Energy Code Compliance DOE Awards $3.7 Million to Spur Investment in Commercial Energy Code Compliance June 28, 2016 - 10:02am Addthis Projects aim to provide field-tested data, develop repeatable methodologies for improving compliance and benchmarking The Building Technologies Office (BTO) has selected three projects to receive a total of $3.7 million to study the effects of improving the implementation

  20. DOE-NRC-Nuclear-Safety-Info-Sharing-Agreement.pdf

    Office of Environmental Management (EM)

    Energy DOE-Japan Collaboration Expands with U.S. Embassy Fellows DOE-Japan Collaboration Expands with U.S. Embassy Fellows February 13, 2013 - 12:00pm Addthis Dr. Robert Sindelar, a researcher with Savannah River National Laboratory, arrived in Japan in early February to begin work as a U.S. Embassy Science Fellow, advising Japanese officials on decontamination and environmental cleanup. Dr. Robert Sindelar, a researcher with Savannah River National Laboratory, arrived in Japan in early

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

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

    that the arguments that it lacked authority to withdraw the pending Yucca Mountain license application are uniformly without merit. DOE's reply brief is available here. In a...

  2. Nuclear Material Transaction Report NRC 741_1

    National Nuclear Security Administration (NNSA)

    B 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 0 YYY XXX 04 01 2008 BASED ON SHIPPER'S VALUES Example 1-b

  3. Nuclear Material Transaction Report NRC 741_1

    National Nuclear Security Administration (NNSA)

    D 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 4 YYY XXX 1 31 20 -50397.00 -2335.00 2 31 20 50300.00 2330.00 04 23 2008 Example 1-d 002 1 FAB FUEL ELE -2 -1 20 309 J -377609.00 4.7962 -18111.00 101 004 103 2 3 4 FAB FUEL ELE -2 FAB FUEL ELE -4 FAB FUEL ELE -4 1 -1 1 20 20 20 309 309 309 J J J 377509.00 -41992.00 42002.00 4.7962 3.1911 3.1911 18000.00 -1340.00 1450.0

  4. Nuclear Material Transaction Report NRC741_1

    National Nuclear Security Administration (NNSA)

    C 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 4 YYY XXX 1 31 20 -50397.00 -2335.00 2 31 20 50300.00 2330.00 04 16 2008 Example 1-c 002 1 FAB FUEL ELE -2 -1 20 309 J -377609.00 4.7962 -18111.00 101 004 103 2 3 4 FAB FUEL ELE -2 FAB FUEL ELE -4 FAB FUEL ELE -4 1 -1 1 20 20 20 309 309 309 J J J 377509.00 -41992.00 42002.00 -107 107 4.7962 3.1911 3.1911 18000.00 -1340.00 1450.00 -30 3

  5. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    A A 1 1 1 1 FOREIGN COMPANY NAME COMPANY ADDRESS CITY, COUNTRY CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 3 RRRR XXX 1 33 20 210.00 68.00 03 31 2008 1 FOREIGN 1 EG 309 J 177999.00 3.2800 5838.00 2 3 FOREIGN FOREIGN 1 1 EG EG 309 309 J J 177834.00 177910.00 3.2900 3.2880 5851.00 5850.00 3061 Example 4-a

  6. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    A B 1 1 1 1 FOREIGN COMPANY NAME COMPANY ADDRESS CITY, COUNTRY CONTACT COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 3 RRRR XXX 1 33 20 210.00 68.00 04 05 2008 1 FOREIGN 1 EG 309 J 177999.00 3.2800 5838.00 2 3 FOREIGN FOREIGN 1 1 EG EG 309 309 J J 177834.00 177910.00 3.2900 3.2880 5851.00 5850.00 Example 4-b

  7. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    XXX VVV 000001 A A 1 1 1 1 COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT WASTE COMPANY NAME COMPANY ADDRESS CITY, STATE ZIP CODE CONTACT 1 VVV XXX 03 31 2008 1 LD WASTE 1 20 776 J 8.00 93.000 7.00 2041 Example 5-a 227

  8. Microsoft PowerPoint - Guidance May DOE PA CoP Meeting_final...

    Office of Environmental Management (EM)

    Division of Decommissioning, Uranium Recovery, and Waste Programs Office of Nuclear Material Safety and Safeguards christopher.grossman@nrc.gov 301-415-0140 Interagency Performance ...

  9. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    O'Hara, J.M.

    2009-11-30

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  10. Safeguards Guidance for Prismatic Fueled High Temperature Gas...

    National Nuclear Security Administration (NNSA)

    ... Administration NPT Treaty on the Non-Proliferation of Nuclear Weapons NRC U.S. Nuclear ... IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). ...

  11. Safeguards Guidance for Independent Spent Fuel Storage Installations...

    National Nuclear Security Administration (NNSA)

    ... Administration NPT Treaty on the Non-Proliferation of Nuclear Weapons vii NRC United ... IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). ...

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

    SciTech Connect (OSTI)

    1996-02-01

    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.

  13. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-02-28

    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.

  14. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2003-04-30

    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 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 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 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 provides the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

  15. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2002-03-04

    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.

  16. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    None, None

    2008-09-11

    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 pplication." 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 U.S. Department of Energy (DOE) or 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. In accordance with 10 CFR Part 71, 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 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

  17. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    None, None

    2007-12-13

    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 U.S. Department of Energy (DOE) or 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.In accordance with 10 CFR Part 71, 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 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

  18. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    None, None

    2006-04-25

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package TransporterModel 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 U.S. Department of Energy (DOE) or 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 ofapproval 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.In accordance with 10 CFR Part 71, 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 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

  19. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    None, None

    2009-06-01

    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 U.S. Department of Energy (DOE) or 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. In accordance with 10 CFR Part 71, 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 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

  20. ADMINISTRATIVE CHANGE TO NNSA SD G-1027, "GUIDANCE ON USING RELEASE...

    National Nuclear Security Administration (NNSA)

    ... as "the sum of the products of the gamma ray energies and the gamma ray fractions (MeV)". ... activities certified by NRC under section 1701 of the Atomic Energy Act. d. Equivalency. ...

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

    SciTech Connect (OSTI)

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

    2010-01-31

    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.

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

    SciTech Connect (OSTI)

    Donald Helton; Hossein Esmaili; Robert Buell

    2011-03-01

    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.

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

    SciTech Connect (OSTI)

    Hsu, Y Y; Lee, R

    1983-04-01

    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)

  4. THE NRC HAS ISSUED Ati ACTION PLAN FOR CLEANUP OF 46 SfTES that...

    Office of Legacy Management (LM)

    paflies; implementation of the plan in p&cuar ,&s ,-:, may require the ... Aberdeen, Md.; Army Arsenal, Water- town, Pa.; Babcock 8 Wilcox. Parks Township and Apollo. ...

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

    National Nuclear Security Administration (NNSA)

    October 2014 NMMSS News is sponsored by the Department of Energy and the Nuclear Regulatory Commission. MARK YOUR CALENDAR NMMSS 2015 Annual Users Training Meeting The Nuclear Materials Management and Safeguards System (NMMSS) 2015 Annual Users Training Meeting will be held May 11-14, 2015, in Las Vegas, Nevada. The NMMSS is the U.S. Government's official information system containing current and historical accounting data and other related nuclear material information collected from both

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

    Office of Environmental Management (EM)

    Forecasts | Department of Energy NOAA Teams Up with Department of Energy & Industry to Improve Wind Forecasts NOAA Teams Up with Department of Energy & Industry to Improve Wind Forecasts July 2, 2014 - 3:51pm Addthis The growth of wind-generated power in the United States is creating greater demand for improved wind forecasts. To address this need, the Department of Energy is working with NOAA and industry on the Wind Forecast Improvement Project, funded and led by DOE. "Our

  7. Materials reliability. Technical activities, 1990. (NAS-NRC Assessment Panel, January 31-February 1, 1991)

    SciTech Connect (OSTI)

    McHenry, H.I.

    1990-12-01

    Selected Highlights of the Materials Reliability Division are as follows: Composites NDE: A high resolution ultrasonic system has been developed for inspecting thick polymer-matrix composites; NDE Instruments: Field trials were conducted on two prototype ultrasonic NDE instruments. A formability sensor system was delivered to the Ford Motor Company for evaluation at their Dearborn stamping plant. An ultrasonic system for roll-by inspection of railroad wheels is being evaluated at the American Association of Railroads test track in Pueblo, Colorado; Elastic Waves in Composites: A powerful technique using a time-dependent Green's function method has been developed for studying propagation of elastic waves and their scattering from discontinuities in anisotropic solids; Electronic Packaging: Computer programs have been developed to convert coordinate points on solder joint surfaces obtained by x-ray laminography and optical inspection into finite element meshes for stress analysis; Thermomechanical Processing: The continuous cooling transformation (CCT) characteristics and the high-temperature, high strain-rate flow properties were measured for microalloyed SAE 1141 forging steel; Charpy Standards: Over 1000 industrial customers were supplied with Charpy V-notch reference specimens and calibration services for certification of Charpy impact test machines to ASTM Standard E23; Cryogenic Testing: A 5 MN (1 million pound-force) servohydraulic testing machine was refurbished and equipped with a cryostat and dewar capable of testing specimens 2 m long and 50 cm in diameter in liquid helium; Aluminum-Lithium Alloys: A cooperative program with NASA indicated that aluminum-lithium alloys have sufficient oxygen compatibility for use in cryogenic tankage for the Advanced Launch System; Automated Welding: An intelligent welding program was initiated for the U.S. Navy in conjunction with Babcock and Wilcox and INEL.

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

    National Nuclear Security Administration (NNSA)

    HEU used as fuel or targets in research or test reactors and including: - Location of HEU ... * Prepare a list of all research and test reactors to which the US has exported HEU ...

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

    SciTech Connect (OSTI)

    First, M.W.

    1991-02-01

    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. Current and anticipated uses of the thermal hydraulics codes at the NRC

    SciTech Connect (OSTI)

    Caruso, R.

    1997-07-01

    The focus of Thermal-Hydraulic computer code usage in nuclear regulatory organizations has undergone a considerable shift since the codes were originally conceived. Less work is being done in the area of {open_quotes}Design Basis Accidents,{close_quotes}, and much more emphasis is being placed on analysis of operational events, probabalistic risk/safety assessment, and maintenance practices. All of these areas need support from Thermal-Hydraulic computer codes to model the behavior of plant fluid systems, and they all need the ability to perform large numbers of analyses quickly. It is therefore important for the T/H codes of the future to be able to support these needs, by providing robust, easy-to-use, tools that produce easy-to understand results for a wider community of nuclear professionals. These tools need to take advantage of the great advances that have occurred recently in computer software, by providing users with graphical user interfaces for both input and output. In addition, reduced costs of computer memory and other hardware have removed the need for excessively complex data structures and numerical schemes, which make the codes more difficult and expensive to modify, maintain, and debug, and which increase problem run-times. Future versions of the T/H codes should also be structured in a modular fashion, to allow for the easy incorporation of new correlations, models, or features, and to simplify maintenance and testing. Finally, it is important that future T/H code developers work closely with the code user community, to ensure that the code meet the needs of those users.

  11. Proceedings of the second NRC/ASME symposium on pump and valve testing

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    The 1992 Symposium on Pump and Valve 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 motoroperated 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 in this document have been cataloged separately.

  12. Proceedings of the second NRC/ASME symposium on pump and valve testing errata. Supplement 1

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    This supplement provides revisions to papers included in NUREG/CP-0123, and the papers which were not included in the initial publication of NUREG/CP-0123. The 1992 Symposium on Pump and Valve Testing, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provided 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 provided an opportunity to discuss the need to improve 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 or ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers have been cataloged separately.

  13. Proceedings of the second NRC/ASME symposium on pump and valve testing errata

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    This supplement provides revisions to papers included in NUREG/CP-0123, and the papers which were not included in the initial publication of NUREG/CP-0123. The 1992 Symposium on Pump and Valve Testing, jointly sponsored by the Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers and by the Nuclear Regulatory Commission, provided 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 provided an opportunity to discuss the need to improve 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 or ideas and perspectives regarding the improvement of inservice testing of pumps and valves at nuclear power plants. Individual papers have been cataloged separately.

  14. A safety assessment of the use of graphite in nuclear reactors licensed by the US NRC

    SciTech Connect (OSTI)

    Schweitzer, D.G.; Gurinsky, D.H.; Kaplan, E.; Sastre, C.

    1987-09-01

    This report reviews existing literature and knowledge on graphite burning and on stored energy accumulation and releases in order to assess what role, if any, a stored energy release can have in initiating or contributing to hypothetical graphite burning scenarios in research reactors. It also addresses the question of graphite ignition and self-sustained combustion in the event of a loss-of-coolant accident (LOCA). The conditions necessary to initiate and maintain graphite burning are summarized and discussed. From analyses of existing information it is concluded that only stored energy accumulations and releases below the burning temperature (650/sup 0/C) are pertinent. After reviewing the existing knowledge on stored energy it is possible to show that stored energy releases do not occur spontaneously, and that the maximum stored energy that can be released from any reactor containing graphite is a very small fraction of the energy produced during the first few minutes of a burning incident. The conclusions from these analyses are that the potential to initiate or maintain a graphite burning incident is essentially independent of the stored energy in the graphite, and depends on other factors that are unique for these reactors, research reactors, and for Fort St. Vrain. In order to have self-sustained rapid graphite oxidation in any of these reactors, certain necessary conditions of geometry, temperature, oxygen supply, reaction product removal, and a favorable heat balance must be maintained. There is no new evidence associated with either the Windscale Accident or the Chernobyl Accident that indicates a credible potential for a graphite burning accident in any of the reactors considered in this review.

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

    National Nuclear Security Administration (NNSA)

    concerning documentation and observation of fuel locations - Water in the fuel pool was of good water quality - Fuel history sheets were very helpful in tracking fuel ...

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

    National Nuclear Security Administration (NNSA)

    20 days after starting, and reconciled the same day as received at NMMSS Global Laser enrichment and Paducah (SYS) -each submitted inventory less than 52 days after ...

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

    National Nuclear Security Administration (NNSA)

    ... qualified government contractors, and medical centers to Cf-252 sealed sources * ... DOE - Sales performed through the DOE Isotope Program - Production and loans funded by ...

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

    National Nuclear Security Administration (NNSA)

    ... during the current year. (b) Prior to permitting an individual to participate in a ... individual. (c) In complying with the requirements of paragraphs (a) or (b) of this ...

  19. Key results for the NRC`s Short Cracks in Piping and Piping Welds Research Program

    SciTech Connect (OSTI)

    Wilkowski, G.; Krishnaswamy, P.; Brust, F.

    1995-04-01

    The overall objective of the Short Cracks in Piping and Piping Welds Program is to verify and improve engineering analyses to predict the fracture behavior of circumferentially cracked pipe under quasi-static loading with particular attention to crack lengths typically used in LBB or flaw evaluation criteria. The USNCRC program at Battelle was initiated in March 1990 and is scheduled to be completed in December 1994. This paper discusses key results from the overall program with particular emphasis on the efforts since the last WRSIM meeting. The program consists of eight technical tasks as listed below: task 1 short through-wall-cracked (TWC) pipe evaluations; task 2 short surface-cracked (SC) pipe evaluations; task 3 bi-metallic weld crack evaluations; task 4 dynamic strain aging and crack instabilities; task 5 fracture evaluations of anisotropic pipe; task 6 crack-opening-area evaluations; task 7 NRCPIPE code improvements; task 8 additional efforts. Task 8 is a collection of new efforts initiated during the coarse of the program. A list of the full-scale pipe experiments in this program is given in Table 1. All of the experiments have been completed. The most recent accomplishments in each of the tasks listed above are discussed below. The details of all the results in the eight tasks are published in the semiannual reports as well as topical reports from the program.

  20. Minutes from 12 December 2006 DOE/NRC Video Teleconference Call...

    Office of Environmental Management (EM)

    12 December 2006 DOENRC Video Teleconference Call on Section 3116 Implementation Activities Attendees: Representatives from DOE-Savannah River (DOE-SR), DOE-Headquarters (DOE-HQ),...

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

    National Nuclear Security Administration (NNSA)

    ... or property or the common defense and security, and is otherwise in the public ... a 500 - year timeframe. (b) Waste classification and near-surface disposal. (1) ...

  2. Re-evaluation of superheat conditions postulated in NRC Information Notice 84-90

    SciTech Connect (OSTI)

    Alsammarae, A.; Kruger, D.; Beutel, D.; Spisak, M.

    1994-08-01

    Information Notice 84-90, ''Main Steam Line Break Effect on Environmental Qualification of Equipment,'' describes a potential problem regarding existing plant analyses and Equipment Qualification (EQ) related to a postulated Main Steam Line Break (MSLB) with releases of superheated stream. This notice states that certain methodologies for computing mass and energy releases for a postulated MSLB did not account for heat transfer from the steam generator tube bundles if they were uncovered. Due to this potential change in the original environmental analysis, the EQ of various components may not consider the thermal environment which could result from superheated steam. Subsequent technical assessments may determine that the existing qualification basis for equipment/components does not envelop the postulated superheat condition. Corrective actions need to be taken to demonstrate that the affected equipment is qualified.

  3. 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.

    1986-03-01

    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.

  4. 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

    2013-07-01

    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)

  5. The Modeling of Advanced BWR Fuel Designs with the NRC Fuel Depletion Codes PARCS/PATHS

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ward, Andrew; Downar, Thomas J.; Xu, Y.; March-Leuba, Jose A; Thurston, Carl; Hudson, Nathanael H.; Ireland, A.; Wysocki, A.

    2015-04-22

    The PATHS (PARCS Advanced Thermal Hydraulic Solver) code was developed at the University of Michigan in support of U.S. Nuclear Regulatory Commission research to solve the steady-state, two-phase, thermal-hydraulic equations for a boiling water reactor (BWR) and to provide thermal-hydraulic feedback for BWR depletion calculations with the neutronics code PARCS (Purdue Advanced Reactor Core Simulator). The simplified solution methodology, including a three-equation drift flux formulation and an optimized iteration scheme, yields very fast run times in comparison to conventional thermal-hydraulic systems codes used in the industry, while still retaining sufficient accuracy for applications such as BWR depletion calculations. Lastly, themore » capability to model advanced BWR fuel designs with part-length fuel rods and heterogeneous axial channel flow geometry has been implemented in PATHS, and the code has been validated against previously benchmarked advanced core simulators as well as BWR plant and experimental data. We describe the modifications to the codes and the results of the validation in this paper.« less

  6. The Modeling of Advanced BWR Fuel Designs with the NRC Fuel Depletion Codes PARCS/PATHS

    SciTech Connect (OSTI)

    Ward, Andrew; Downar, Thomas J.; Xu, Y.; March-Leuba, Jose A; Thurston, Carl; Hudson, Nathanael H.; Ireland, A.; Wysocki, A.

    2015-04-22

    The PATHS (PARCS Advanced Thermal Hydraulic Solver) code was developed at the University of Michigan in support of U.S. Nuclear Regulatory Commission research to solve the steady-state, two-phase, thermal-hydraulic equations for a boiling water reactor (BWR) and to provide thermal-hydraulic feedback for BWR depletion calculations with the neutronics code PARCS (Purdue Advanced Reactor Core Simulator). The simplified solution methodology, including a three-equation drift flux formulation and an optimized iteration scheme, yields very fast run times in comparison to conventional thermal-hydraulic systems codes used in the industry, while still retaining sufficient accuracy for applications such as BWR depletion calculations. Lastly, the capability to model advanced BWR fuel designs with part-length fuel rods and heterogeneous axial channel flow geometry has been implemented in PATHS, and the code has been validated against previously benchmarked advanced core simulators as well as BWR plant and experimental data. We describe the modifications to the codes and the results of the validation in this paper.

  7. 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...

  8. SEP Guidance

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

    SEP PROGRAM NOTICE 10-008C EFFECTIVE DATE (Revised): March 14, 2011 ORIGINALLY ISSUED: December 7, 2009 SUBJECT: GUIDANCE FOR STATE ENERGY PROGRAM GRANTEES ON FINANCING PROGRAMS. PURPOSE To provide guidance to the Department of Energy's (Department or DOE) State Energy Program (SEP) grantees on financing programs. This guidance supersedes SEP Program Notice 10-008B, which was issued on August 10, 2010. SCOPE The provisions of this guidance apply to grantees of SEP funds, pursuant to Formula

  9. SEAB Guidance

    Broader source: Energy.gov [DOE]

    Listed below in chronological order are the letters and memoranda issued by SEAB to the Department providing their views and guidance on the respective topics. 

  10. solicitation guidance

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

    solicitation guidance - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced

  11. Methods and criteria for safety analysis (FIN L2535)

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, ``Methods and Criteria for Safety Analysis,`` as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description.

  12. 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...

  13. Microsoft PowerPoint - 1_Pete_Deessaules_Brain_Horn_NMMSS_2014_screensaver.ppt [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    Welcome Pete Dessaules, NNSA Brian Horn, NRC

  14. Design of Safety Significant Safety Instrumented Systems Used...

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

    ... F-2 APPENDIX G. HUMAN FACTORS ENGINEERING ... H-1 H.3 Nuclear Regulatory Commission (NRC) Guidance ... and Criteria - Fundamentals of Training * ...

  15. Task 2 - Limits for High-Frequency Conducted Susceptibility Testing - CS114 (NRC-HQ-60-14-D-0015)

    SciTech Connect (OSTI)

    Wood, Richard Thomas; Ewing, Paul D.; Moses, Rebecca J.

    2015-09-01

    A principal focus of Task 2 under this project was for ORNL to evaluate the basis for susceptibility testing against high-frequency conducted interference and to establish recommendations to resolve concerns about the severity of test limits for the conducted susceptibility (CS) test, CS114, from MIL-STD-461. The primary concern about the test limit has been characterized by the EPRI EMI Working Group in the following terms: Demonstrating compliance with the CS114 test limits recommended in TR-102323 has proven to be problematic, even for components that have been tested to commercial standards and demonstrated proper operation in industrial applications [6]. Specifically, EPRI notes that the CS114 limits approved in regulatory documents are significantly higher than those invoked by the US military and similar commercial standards in the frequency range below 200 kHz. For this task, ORNL evaluated the original approach to establishing the test limit, EPRI technical findings from a review of the limit, and the regulatory basis through which the currently approved limits were accepted. Based on this analysis, strategies have been developed regarding changes to the CS114 limit that can resolve the technical concerns raised by the industry. Guided by the principles that reasonable assurance of safety must not be compromised but excessive conservatism should be reduced, recommendations on a suitable basis for a revised limit have been developed and can be incorporated into the planned Revision 2 of RG 1.180.

  16. Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513. Interim report

    SciTech Connect (OSTI)

    Williford, R.E.; Mohr, C.L.; Lanning, D.D.; Cunningham, M.E.; Rausch, W.N.

    1980-06-01

    The effects of the thermally-induced cracking and subsequent relocation of UO2 fuel pellets on the thermal and mechanical behavior of light-water reactor fuel rods during irradiation are quantified in this report. Data from the Nuclear Regulatory Commission/Pacific Northwest Laboratory Halden experiments on instrumented fuel assemblies (IFA) IFA-431, IFA-432, and IFA-513 are analyzed. Beginning-of-life in-reactor measurements of fuel center temperatures, linear heat ratings, and cladding axial elongations are used in a new model to solve for the effective thermal conductivity and elastic moduli of the cracked fuel column. The primary assumptions of the new model are that (1) the cracked fuel is in a hydrostatic state of stress in the (r,theta) plane, and that (2) there is no axial slipping between fuel and cladding. Three basic parameters are used to describe the cracked fuel: (1) the crack pattern, (2) the crack roughness, and (3) the fuel surface (gap) roughness. Recommendations are made on refining the model.

  17. Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513

    SciTech Connect (OSTI)

    Williford, R.E.; Mohr, C.L.; Lanning, D.D.; Cunningham, M.E.; Rausch, W.N.; Bradley, E.R.

    1980-04-01

    The effects of the thermally-induced cracking and subsequent relocation of UO/sub 2/ fuel pellets on the thermal and mechanical behavior of light-water reactor fuel rods during irradiation are quantified in this report. Data from the Nuclear Regulatory Commission/Pacific Northwest Laboratory Halden experiments on instrumented fuel assemblies (IFA) IFA-431, IFA-432, and IFA-513 are analyzed. Beginning-of-life in-reactor measurements of fuel center temperatures, linear heat ratings, and cladding axial elongations are used in a new model to solve for the effective thermal conductivity and elastic moduli of the cracked fuel column. The effective thermal conductivity and elastic moduli for the cracked fuel were found to be significantly reduced from the values for solid UO/sub 2/ pellets. The calculated fuel-cladding gap remained relatively constant (closed) with respect to power level, indicating that the fuel fragments do not retreat from the cladding when the power/temperature is reduced. Recommendations are made pertaining to the work required to further refine the model. 30 refs., 81 figs., 8 tabs.

  18. 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

    2013-07-01

    The analysis of the activity and radionuclide composition of water from the MR reactor pond for α,β,γ-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)

  19. 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)

    A. Project Title: Development of LWR Fuels Enhanced Accident Tolerance - Westinghouse Electric ... the currently used Zr + UO2 fuel system with and enhanced accident tolerant fuel. ...

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

    SciTech Connect (OSTI)

    1995-10-01

    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.

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

    SciTech Connect (OSTI)

    1996-10-01

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

  2. Task 1. Monitoring real time materials degradation. NRC extended In-situ and real-time Monitoring

    SciTech Connect (OSTI)

    Bakhtiari, Sasan

    2012-03-01

    The overall objective of this project was to perform a scoping study to identify, in concert with the nuclear industry, those sensors and techniques that have the most promising commercial viability and fill a critical inspection or monitoring need. Candidates to be considered include sensors to monitor real-time material degradation, characterize residual stress, monitor and inspect component fabrication, assess radionuclide and associated chemical species concentrations in ground water and soil, characterize fuel properties, and monitor severe accident conditions. Under Task 1—Monitoring Real-Time Materials Degradation—scoping studies were conducted to assess the feasibility of potential inspection and monitoring technologies (i.e., a combination of sensors, advanced signal processing techniques, and data analysis methods) that could be utilized in LWR and/or advanced reactor applications for continuous monitoring of degradation in-situ. The goal was to identify those techniques that appear to be the most promising, i.e., those that are closest to being both technically and commercially viable and that the nuclear industry is most likely to pursue. Current limitations and associated issues that must be overcome before commercial application of certain techniques have also been addressed.

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

    National Nuclear Security Administration (NNSA)

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

    National Nuclear Security Administration (NNSA)

    Regulatory Commission Report to the U.S. Congress: High Enriched Uranium Gary Langlie, Nuclear Regulatory Commission Background  American Medical Isotopes Production Act of 2012 (AMIPA) - passed as part of the National Defense Authorization Act for FY13 (NDAA), which was signed into law on January 2, 2013  AMIPA's primary focus - to improve reliability of domestic medical isotope supplies without using high enriched uranium (HEU)* and to eventually eliminate HEU exports  Section 3175 of

  5. 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

    2012-02-13

    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

  6. 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

    2010-02-26

    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.

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

    SciTech Connect (OSTI)

    Budnitz, R.J.; Apostolakis, G.; Boore, D.M.

    1997-04-01

    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.

  8. Rulemaking Guidance | Department of Energy

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

    Rulemaking Guidance Rulemaking Guidance The following rulemaking policies are available: Rulemaking Guidance on DOE Involvement in Consensus Negotiations for energy Conservation...

  9. SEP Guidance | Department of Energy

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

    Guidance SEP Guidance Guidance for State Energy Program Grantees sep_financing_guidance_2011-03-15.pdf (224.45 KB) More Documents & Publications SEP Program Notice 10-008B - Guidance for State Energy Program Grantees on Financing Programs EECBG Guidance SEP Program Notice 10-013

  10. POLICY GUIDANCE MEMORANDUM #19 Guidance on Transition to Eliminate FCIP

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

    (Expired) | Department of Energy 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 elimination of the Federal Career Intern Program (FCIP) POLICY GUIDANCE MEMORANDUM #19 Guidance on Transition to Eliminate FCIP (Expired) (4.84 MB) Responsible Contacts Ahtora Brooks Human Resource Specialists E-mail Ahtora.Brooks@Hq.Doe.Gov Phone 202-586-1239 More Documents &

  11. EECBG 2016 Guidance Documents

    Broader source: Energy.gov [DOE]

    The Energy Efficiency and Conservation Block Grant (EECBG) Program released guidance documents that explain how the recipients of EECBG funds need to report and manage those funds.

  12. 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

  13. Site Transition Guidance

    Office of Environmental Management (EM)

    Site Transition Guidance March 2010 Office of Environmental Management U.S. Department of Energy Washington D. C. 20585 Standard Review Plan (SRP) Technical Framework for EM...

  14. Guidance | Department of Energy

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

    Justice General Guidance on NEPA NEPA History NEPA Implementation NEPA and Other Laws NEPA Policy Public Participation Special Topics in NEPA Documentation All NEPA ...

  15. State Energy Program Guidance

    Broader source: Energy.gov [DOE]

    The State Energy Program (SEP) has released the following guidance documents, listed chronologically below, that explain how states must report and manage SEP program funding.

  16. Buy American Guidance Documents

    Office of Energy Efficiency and Renewable Energy (EERE)

    Projects funded by the American Recovery and Reinvestment Act of 2009 (Recovery Act) were required to follow the Buy American Provision. Below are Buy American guidance documents.

  17. 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.

  18. Commissioning guidance for ESPCs

    SciTech Connect (OSTI)

    None, None

    2009-01-18

    Guidance for facility managers describing the commissioning process in Super ESPC contracts and how these contracts can achieve the objective of meeting facility performance requirements.

  19. Office of Technical Guidance

    Broader source: Energy.gov [DOE]

    The Office of Technical Guidance develops, promulgates, and interprets national level policies, procedures, and guidance to identify (1) information that must be classified or controlled under statute or Executive order to protect the national security, to ensure the effective operation of the Government, or to protect the privacy interests of individuals and (2) classified or controlled information that may be declassified or decontrolled.

  20. Site Transition Plan Guidance | Department of Energy

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

    Plan Guidance Site Transition Plan Guidance Site Transition Plan Guidance PDF icon Site Transition Plan Guidance More Documents & Publications Development of Site Transition Plan, ...

  1. Guidance & Opinions | Department of Energy

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

    DOE Facilities and by DOE Contractors Opinion on Contractor Participation in the Federal Hiring Process Guidance on Inherently Governmental Functions Guidance on Electric Vehicle...

  2. Commissioning Guidance for ESPCs

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

    COMMISSIONING GUIDANCE FOR ESPCs CONTENTS Introduction ................................................................................................................................................... 1 Overview of Commissioning in the ESPC Process ...................................................................................... 2 Summary of Roles And Responsibilities In ESPC Project Commissioning ................................................. 3 Key Elements of Commissioning

  3. Selected Guidance & Requirements

    Broader source: Energy.gov [DOE]

    This page contains the most requested NEPA guidance and requirement documents and those most often recommended by the Office of NEPA Policy and Compliance. Documents are listed by agency, in...

  4. Buy American Program Guidance

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

    PROJECTS FUNDED BY THE AMERICAN RECOVERY AND REINVESTMENT ACT OF 2009 AND ADMINISTERED BY THE OFFICE OF ENERGY EFFICIENCY AND RENEWABLE ENERGY NOTICE EFFECTIVE DATE: December 17, 2009 SUBJECT: GUIDANCE ON THE BUY AMERICAN PROVISIONS AS APPLIED TO ENERGY EFFICIENCY AND RENEWABLE ENERGY PROJECTS FUNDED BY THE AMERICAN RECOVERY AND REINVESTMENT ACT OF 2009 AND ADMINISTERED BY THE OFFICE OF ENERGY EFFICIENCY AND RENEWABLE ENERGY PURPOSE: Provides guidance to financial assistance recipients regarding

  5. Guidance for preparation of safety analysis reports for nonreactor facilities and operations. Revision 2

    SciTech Connect (OSTI)

    Not Available

    1992-11-06

    Department of Energy (DOE) Orders 5480.23, ``Nuclear Safety Analysis Reports,`` and 5481.1B, ``Safety Analysis and Review System`` require the preparation of appropriate safety analyses for each DOE operation and subsequent significant modifications including decommissioning, and independent review of each safety analysis. The purpose of this guide is to assist in the preparation and review of safety documentation for Oak Ridge Field Office (OR) nonreactor facilities and operation. Appendix A lists DOE Orders, NRC Regulatory Guides and other documents applicable to the preparation of safety analysis reports.

  6. Guidance for preparation of safety analysis reports for nonreactor facilities and operations

    SciTech Connect (OSTI)

    Not Available

    1992-11-06

    Department of Energy (DOE) Orders 5480.23, Nuclear Safety Analysis Reports,'' and 5481.1B, Safety Analysis and Review System'' require the preparation of appropriate safety analyses for each DOE operation and subsequent significant modifications including decommissioning, and independent review of each safety analysis. The purpose of this guide is to assist in the preparation and review of safety documentation for Oak Ridge Field Office (OR) nonreactor facilities and operation. Appendix A lists DOE Orders, NRC Regulatory Guides and other documents applicable to the preparation of safety analysis reports.

  7. ARM - Social Media Guidance

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

    CenterSocial Media Guidance Media Contact Hanna Goss hanna-dot-goss-at-pnnl-dot-gov @armnewsteam Field Notes Blog Topics Field Notes117 AGU 3 AMIE 10 ARM Aerial Facility 2 ARM Mobile Facility 1 7 ARM Mobile Facility 2 47 ARM Mobile Facility 3 1 BAECC 1 BBOP 4 CARES 1 Data Quality Office 2 ENA 2 GOAMAZON 7 HI-SCALE 4 LASIC 3 MAGIC 15 MC3E 17 PECAN 3 SGP 8 STORMVEX 29 TCAP 3 Search News Search Blog News Center All Categories What's this? Social Media Guidance News Center All Categories Features

  8. Section 106 Archaeology Guidance

    Broader source: Energy.gov [DOE]

    The Advisory Council on Historic Preservation's Section 106 guidance is designed to assist federal agencies in making effective management decisions about archaeological resources in completing the requirements of Section 106 of the National Historic Preservation Act (16 U.S.C. 470f) and its implementing regulations (36 CFR Part 800). This guidance highlights the decision-making role of the federal agency in the Section 106 process. It is also designed for use by State and Tribal Historic Preservation Officers, Indian tribes, Native Hawaiian organizations, and cultural resource management professionals when assisting federal agencies to meet their responsibilities under Section 106.

  9. NON-NRC FUNDED RELAP5-3D VERSION 4.x.x SOFTWARE REACTOR EXCURSION AND LEAK ANALYSIS PACKAGE - THREE DIMENSIONAL

    SciTech Connect (OSTI)

    2012-03-26

    The RELAP5-3D Version 3.x code has been developed for best-estimate transient simulation of nuclear reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents and operational transients such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems including pressurized water reactors, boiling water reactors, Soviet-designed reactors, heavy water reactors, gas-cooled reactors, liquid metal and molten salt cooled reactors, and even fusion reactors. Numerical models include multi-dimensional hydrodynamics, 1- and 2-D heat transfer in metal walls, 0-, 1-, 2-, and 3-D neutron kinetics, trips, and control systems. Secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems.

  10. 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; Downar, Thomas J.; Ulses, Anthony; Akdeniz, Bedirhan; Ivanov, Kostadin N.

    2004-10-15

    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.

  11. Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations

    SciTech Connect (OSTI)

    Ivanov, Kostadin N.; Todorova, Nadejda K.; Sartori, Enrico

    2003-05-15

    Incorporating full three-dimensional (3-D) models of the reactor core into system transient codes allows for a 'best-estimate' calculation of interactions between the core behavior and plant dynamics. Recent progress in computer technology has made the development of coupled thermal-hydraulic (T-H) and neutron kinetics code systems feasible. Considerable efforts have been made in various countries and organizations in this direction. Appropriate benchmarks need to be developed that will permit testing of two particular aspects. One is to verify the capability of the coupled codes to analyze complex transients with coupled core-plant interactions. The second is to test fully the neutronics/T-H coupling. One such benchmark is the Pressurized Water Reactor Main Steam Line Break (MSLB) Benchmark problem. It was sponsored by the Organization for Economic Cooperation and Development, U.S. Nuclear Regulatory Commission, and The Pennsylvania State University. The benchmark problem uses a 3-D neutronics core model that is based on real plant design and operational data for the Three Mile Island Unit 1 nuclear power plant. The purpose of this benchmark is threefold: to verify the capability of system codes for analyzing complex transients with coupled core-plant interactions; to test fully the 3-D neutronics/T-H coupling; and to evaluate discrepancies among the predictions of coupled codes in best-estimate transient simulations. The purposes of the benchmark are met through the application of three exercises: a point kinetics plant simulation (exercise 1), a coupled 3-D neutronics/core T-H evaluation of core response (exercise 2), and a best-estimate coupled core-plant transient model (exercise 3).In this paper we present the three exercises of the MSLB benchmark, and we summarize the findings of the participants with regard to the current numerical and computational issues of coupled calculations. In addition, this paper reviews in some detail the sensitivity studies on exercises 2 and 3 performed by the benchmark team using the coupled code TRAC-PF1/NEM. The purpose of these supporting studies was to aid participants in developing their models.

  12. 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.

    1982-09-01

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    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.

  15. NON-NRC FUNDED RELAP5-3D VERSION 4.x.x SOFTWARE REACTOR EXCURSION AND LEAK ANALYSIS PACKAGE - THREE DIMENSIONAL

    Energy Science and Technology Software Center (OSTI)

    2012-03-26

    The RELAP5-3D Version 3.x code has been developed for best-estimate transient simulation of nuclear reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents and operational transients such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems including pressurized watermore » reactors, boiling water reactors, Soviet-designed reactors, heavy water reactors, gas-cooled reactors, liquid metal and molten salt cooled reactors, and even fusion reactors. Numerical models include multi-dimensional hydrodynamics, 1- and 2-D heat transfer in metal walls, 0-, 1-, 2-, and 3-D neutron kinetics, trips, and control systems. Secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems.« less

  16. Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive materials packages. Volume 3, Revision 15

    SciTech Connect (OSTI)

    1995-10-01

    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.

  17. Evaluation of select heat and pressure measurement gauges for potential use in the NRC/OECD High Energy Arc Fault (HEAF) test program.

    SciTech Connect (OSTI)

    Lopez, Carlos; Wente, William Baker; Figueroa, Victor G.

    2014-01-01

    In an effort to improve the current state of the art in fire probabilistic risk assessment methodology, the U.S. Nuclear Regulatory Commission, Office of Regulatory Research, contracted Sandia National Laboratories (SNL) to conduct a series of scoping tests to identify thermal and mechanical probes that could be used to characterize the zone of influence (ZOI) during high energy arc fault (HEAF) testing. For the thermal evaluation, passive and active probes were exposed to HEAF-like heat fluxes for a period of 2 seconds at the SNLs National Solar Thermal Test Facility to determine their ability to survive and measure such an extreme environment. Thermal probes tested included temperature lacquers (passive), NANMAC thermocouples, directional flame thermometers, modified plate thermometers, infrared temperature sensors, and a Gardon heat flux gauge. Similarly, passive and active pressure probes were evaluated by exposing them to pressures resulting from various high-explosive detonations at the Sandia Terminal Ballistic Facility. Pressure probes included bikini pressure gauges (passive) and pressure transducers. Results from these tests provided good insight to determine which probes should be considered for use during future HEAF testing.

  18. Guidance and Opinions | Department of Energy

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

    Guidance and Opinions Guidance and Opinions Contractor Relations Guidance on Accessing Contractor and Subcontractor Employment Records Arbitration Guidance for Management and Operating Contractors Guidance on Meetings with Union Officials Political Activity at DOE Facilities and by DOE Contractors Opinion on Contractor Participation in the Federal Hiring Process Guidance on Inherently Governmental Functions Guidance on Electric Vehicle Recharging Stations Safety Regulations Interpretations

  19. High Performance and Sustainable Buildings Guidance | Department...

    Office of Environmental Management (EM)

    High Performance and Sustainable Buildings Guidance High Performance and Sustainable Buildings Guidance High Performance and Sustainable Buildings Guidance (192.76 KB) More ...

  20. General Privacy Act Guidance | Department of Energy

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

    Privacy Act Guidance General Privacy Act Guidance This document provides information on Privacy Act Requests and responses to general FAQs PDF icon General Privacy Act Guidance ...

  1. NEPA Contracting Reform Guidance

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

    defining early what contractors should accomplish < establishing contracts ahead of time < minimizing cost while maintaining quality by * maximizing competition and use of incentives * using past performance information in awarding work * managing the NEPA process as a project This guidance provides: < model statements of work < information on contract types and incentives < direction on effective NEPA contract management by the NEPA Document Manager < a system for measuring

  2. Environmental guidance regulatory bulletin

    SciTech Connect (OSTI)

    1997-01-31

    This document describes the background on expanding public participation in the Resource Conservation and Recovery Act and DOE`s response. The bulletin also describes the changes made by the final rule to existing regulations, guidance provided by EPA in the preamble and in the revised RCRA Public Participation Manual, the relationship between public participation and environmental justice, and DOE`s recent public participation and environmental justice initiatives.

  3. Microsoft Word - S06584StSoil.doc

    Office of Legacy Management (LM)

    NRC Technical Evaluation Reports This page intentionally left blank

  4. Microsoft Word - S06584StSoil.doc

    Office of Legacy Management (LM)

    ADAMS is accessible from the NRC Web site at http:www.nrc.govreading-rmadams.html. ... ADAMS is accessible from the NRC Web site at http:www.nrc.govreading-rmadams.html. ...

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

    SciTech Connect (OSTI)

    Savage, J.W.

    1982-03-10

    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.

  6. Lessons Learned Quarterly Report; March 3, 2003; Issue No. 34...

    National Nuclear Security Administration (NNSA)

    ... Further Information: The Commission's rulings can be found on the NRC Web site (Utah ... DOE's guidance on accident analyses can be found on the DOE NEPA Web site: tis.eh.doe.gov...

  7. Energy Sector Cybersecurity Framework Implementation Guidance

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

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

  8. Departmental Personnel Security - Implementation Guidance | Department...

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

    Departmental Personnel Security - Implementation Guidance Implementation Guidance Overview of Security ClearanceAccess Authorization Process for Applicants Drug Testing ...

  9. Project Management Policy & Guidance Documents | Department of...

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

    Policy & Guidance Documents Project Management Policy & Guidance Documents << Return to Directives & Documents | Proceed to Publications & Documents >> Document Type Function

  10. Appliance Standards Guidance and Frequently Asked Questions

    Office of Environmental Management (EM)

    Implementation, Certification, & Enforcement Rulemakings & Notices Further Guidance ENERGY STAR Building Energy Codes Appliance Standards Guidance and Frequently Asked...

  11. Microsoft PowerPoint - 9_ANDY_IMBODEN_NMMSS_2014_Powerpoint_Waste...

    National Nuclear Security Administration (NNSA)

    NRC's Waste Confidence Rulemaking Andy Imboden, NRC, Office of Nuclear Material Safety and Safeguards Outline Schedule Completed Activities Public Participation ...

  12. Guidance Documents | Department of Energy

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

    Guidance Documents Guidance Documents Guidance documents for the financial opportunities process. Recipient's Guide to Negotiation with EERE (281.39 KB) DOE Guide to Financial Assistance (539.53 KB) DOE Merit Review Guide (223.37 KB) Technology Readiness Levels (TRLs) (255.77 KB) Generally Unallowable Costs (256.08 KB) Catalog of Federal Domestic Assistance Numbers (CFDA) (253.83 KB) More Documents & Publications Financial Assistance Guide (2013) Revised Guide for Financial Assistance

  13. Environmental Justice: Guidance Under NEPA

    Broader source: Energy.gov [DOE]

    Guidance from the Council on Environmental Quality to assist Federal agencies with their NEPA procedures so that environmental justice concerns are effectively identified and addressed.

  14. EECBG Guidance | Department of Energy

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

    Efficiency And Conservation Block Grant Grantees On Financing Programs EECBG Program Notice 09-002B - Guidance for Energy Efficiency and Conservation Block Grant Grantees on ...

  15. Communications and Guidance | Department of Energy

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

    and Guidance Communications and Guidance Issued Guidance: Throughout the life of the Recovery Act, it has at times been necessary to issue guidance around certain policies or procedures. DOE Interim Guidance on Recipient Signage (May 2010) Buy American Act Guidance Davis-Bacon Compliance Guidance on Recovery Act Logo Usage (March 2009) Recovery Act Memos: Special reports written on cross-cutting themes of Recovery Act impact. Small Businesses Helping Drive Economy: Clean Energy, Clean Sites

  16. Prototype Programmatic Agreement Guidance

    Broader source: Energy.gov [DOE]

    Prototype programmatic agreements are a type of program alternative that the Advisory Council on Historic Preservation (ACHP) can designate to assist federal agencies in their efforts to comply with the requirements of Section 106 of the National Historic Preservation Act (16 U.S.C. 470f) and its implementing regulations (36 CFR Part 800). Prototype agreements may be used for the same type of program or undertaking in more than one case or area, and typically establish efficiencies and protocols for implementing these undertakings. This ACHP guidance describes the process for developing prototype agreements, the involvement of interested parties, and other important components to be considered when exploring the use of a prototype agreement as a program alternative.

  17. Security Policy, Guidance & Reports

    Broader source: Energy.gov [DOE]

    The Office of Headquarters Security Operations strengthens national security by protecting personnel, facilities, property, classified information, and sensitive unclassified information for DOE Headquarters facilities in the National Capital Area under normal and abnormal (i.e., emergency) conditions; managing access authorization functions for Headquarters; ensuring that executives and dignitaries are fully protected, and supporting efforts to ensure the continuity of government in all circumstances as mandated by Presidential Decision Directive. The Office is responsible for the principal personnel security information processing activities of the Department and personnel security administrative review process. The Office of Headquarters Security Operations provides oversight and direction support to all Headquarters security operations to include physical protection, information security, personnel security, and guidance to the Headquarters Security Officers (HSO).

  18. 2015 ASER Guidance | Department of Energy

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

    ASER Guidance 2015 ASER Guidance Guidance for Preparation of the 2015 Department of Energy Annual Site Environmental Reports (ASER); ASER Formats 2015 ASER Guidance (504.85 KB) More Documents & Publications Guidance for Preparation of the 2014 Department of Energy Annual Site Environmental Reports ERAD 2014 Presentations Portsmouth Annual Site Environmental Reports

  19. Site Transition Guidance | Department of Energy

    Office of Environmental Management (EM)

    Guidance Site Transition Guidance On June 16, 2004, Michael W. Owen, Director, Office of Legacy Management (LM) and Jessie H. Roberson, Assistant Secretary, Office of Environmental ...

  20. Interim Guidance Regarding Limitations on CERCLA Liability |...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - Inner-Office Memorandum: Interim Guidance Regarding Limitations on CERCLA LiabilityPermitting...

  1. Utah Antidegradation Review Implementation Guidance | Open Energy...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Utah Antidegradation Review Implementation GuidancePermittingRegulatory...

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

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

    Environmental Review Process (EPA, 1993) Guidance on Incorporating EPA's Pollution Prevention Strategy into the Environmental Review Process (EPA, 1993) The guidance discusses ...

  3. Amended Environmental Impact Statement Filing System Guidance...

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

    Amended Environmental Impact Statement Filing System Guidance (EPA, 2012) Amended Environmental Impact Statement Filing System Guidance (EPA, 2012) Amended Environmental Impact ...

  4. Additional Guidance Regarding Application of Current Procedures...

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

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

  5. Renewable Energy Financial Instruments Guidance Tool (REFINe...

    Open Energy Info (EERE)

    Guidance Tool (REFINe) Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Renewable Energy Financial Instruments Guidance Tool (REFINe) Focus Area: Renewable Energy...

  6. Security and Cyber Guidance | Department of Energy

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

    Security and Cyber Guidance Security and Cyber Guidance Appraisal Process Guides Security Evaluations Appraisal Process Guide - April 2008 Cyber Security Evaluations Appraisal ...

  7. Request for Proposal Guidance | Department of Energy

    Energy Savers [EERE]

    Request for Proposal Guidance Request for Proposal Guidance When purchasing plug-in electric vehicle charging stations as part of your workplace charging program, your organization ...

  8. Nuclear Safety Policy, Guidance & Reports

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety establishes and maintains nuclear safety policy, requirements, and guidance including policy and requirements relating to hazard and accident analysis, facility design and operation, and Quality Assurance.

  9. DOE Guidance-Category Rating

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

    August 27, 2010 MEMORANDUM FOR HUMAN RESOURCES DIRECTORS FROM: SARA"iJ. Boku1, DIRECToR OF HUMAN CTAL MANAGEMENT SUBJECT: GUIDANCE MEMORANDUM 10 CATEGORY RATING The purpose of ...

  10. Implemenation Guidance | Department of Energy

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

    Services » Earned Value Management » Implemenation Guidance Implemenation Guidance Earned Value Management (EVM) is a systematic approach to the integration and measurement of cost, schedule, and technical (scope) accomplishments on a project or task. Following established implementation guidelines and conducting periodic surveillance of implemented EVM System (EVMS) will ensure that both the government and contractors have the ability to examine detailed schedule information, critical program

  11. QA in Design Guidance | Department of Energy

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

    in Design Guidance QA in Design Guidance This Department of Energy (DOE) Environmental Management (EM) guidance document is approved for use by all DOE EM organizational units and contractors performing work for EM. QA in Design Guidance (103.15 KB) More Documents & Publications Audit Report: IG-0863 Line Management Understanding of QA and Oversight Requirements Flowdown and Graded Approach to QA

  12. CMI Guidance Documents | Critical Materials Institute

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

    CMI Guidance Documents This page has links to pdf versions of CMI Guidance Documents for CMI staff: Publication process flow chart Acknowledgement text Foreign travel Press releases IP protection The Microsoft Word versions of these, and additional guidance documents, are available in the data storage server. Tags: guidance document

  13. Buy American Program Guidance | Department of Energy

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

    Buy American Program Guidance Buy American Program Guidance Provides information on the December 17, 2009, Buy American Guidance eere_program_guidance_buy_american_121709.pdf (122 KB) More Documents & Publications Projects Funded by the American Recovery and Reinvestment Act of 2009 and Administered by the Office of Energy Efficiency and Renewable Energy (EERE) Notice Buy American Guidance Documents FAQs Docs for the Buy American Provision

  14. Information architecture. Volume 3: Guidance

    SciTech Connect (OSTI)

    1997-04-01

    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.

  15. Microsoft Word - Interpretive Guidance FINAL

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

    June 2, 2011 INTERPRETIVE GUIDANCE ON THE REQUIREMENTS OF 10 C.F.R. § 205.322 This guidance is intended to clarify the Department of Energy (DOE)'s interpretation of 10 C.F.R. § 205.322, which sets forth the contents of an application for a Presidential permit issued by DOE under Executive Order (E.O.) 10485, as amended by E.O. 12038. Anyone seeking to construct, operate, maintain, or connect an electric transmission facility crossing the borders of the United States must first obtain a

  16. Policy Standards, Guidance and Statutes

    Broader source: Energy.gov [DOE]

    Policy Guidance and Statutes, DOE Standards, STD, Atomic Energy Act, Table, Draft DOE P, American Indian Religiuos Freedom, CERCLA, RCRA, Clean Air ACt, Clean Water Act, Emergency Planing and Community, Federal Environmental Laws, Surface Contamination Guidelines, DOE STD-1196-2011, Derived Concentration Technical Standard, ALARA, 0173T

  17. Privacy Impact Assessment Template and Guidance

    Broader source: Energy.gov [DOE]

    Guidance is provided in the template. See DOE Order 206.1, Department of Energy Privacy Program, Appendix A, Privacy Impact Assessments, for requirements and additional guidance for conducting an...

  18. NEPA Guidance and Requirements- Search Index

    Office of Energy Efficiency and Renewable Energy (EERE)

    The NEPA Guidance and Requirements - Search Index is a one-stop solution providing you with DOE's Guidance and Requirements documents combined into one file for easy download and use.

  19. Wetlands, Floodplains, and Other Water Resources Guidance and...

    Office of Environmental Management (EM)

    Wetlands, Floodplains, and Other Water Resources Guidance and Requirements Wetlands, Floodplains, and Other Water Resources Guidance and Requirements Guidance Revised Guidelines ...

  20. 2012 Federal Real Property Council Reporting Guidance | Department...

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

    2012 Data Dictionary FINAL.pdf More Documents & Publications 2015 Federal Real Property Council Reporting Guidance FRPC User Guidance -for FY2006 FRPC User Guidance -for FY2006...

  1. Idaho Section 401 Certification Guidance | Open Energy Information

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Idaho Section 401 Certification GuidancePermittingRegulatory GuidanceGuide...

  2. Federal Building Energy Use Benchmarking Guidance, August 2014...

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

    Energy Use Benchmarking Guidance, August 2014 Update Federal Building Energy Use Benchmarking Guidance, August 2014 Update Guidance describes the Energy Independence and Security ...

  3. Council on Environmental Quality (CEQ) NEPA Guidance and Requirements...

    Office of Environmental Management (EM)

    Council on Environmental Quality (CEQ) NEPA Guidance and Requirements Council on Environmental Quality (CEQ) NEPA Guidance and Requirements Also see CEQ's NEPA guidance page: ...

  4. February2GuidanceMemorandum.pdf | Department of Energy

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

    February2GuidanceMemorandum.pdf February2GuidanceMemorandum.pdf PDF icon February2GuidanceMemorandum.pdf More Documents & Publications Memorandum of Understanding (MOU) POLICY...

  5. Multiyear Program Plan Template - Phase II Guidance | Department...

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

    Multiyear Program Plan Template - Phase II Guidance Multiyear Program Plan Template - Phase II Guidance EERE template and guidance for program managers to develop multiyear plans, ...

  6. Guidance for Procurement Officials | Department of Energy

    Office of Environmental Management (EM)

    Guidance for Procurement Officials Acquisition Regulations Federal Acquisition Regulation (FAR) Department of Energy Acquisition Regulation (DEAR) Acquisition Policy Acquisition ...

  7. WPN 06-1: 2006 Grant Guidance

    Broader source: Energy.gov [DOE]

    To issue grant guidance and management information for the Low-Income Weatherization Assistance Program (Weatherization) for Program Year 2006.

  8. Internal Controls Guidance | Department of Energy

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

    Internal Controls Guidance Internal Controls Guidance Guidance required to be implemented by Departmental elements to meet the requirements of the Federal Managers' Financial Integrity Act (FMFIA), as described in Office of Management and Budget (OMB) Circular A-123, Management's Responsibility for Internal Control. This guidance provides instructions for conducting internal controls evaluations and help ensure the Secretary's annual Statement of Assurance is accurate and adequately supported.

  9. Guidance Regarding NEPA Regulations | Department of Energy

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

    This document provides Council on Environmental Quality guidance on several topics: scoping, categorical exclusions, adoption procedures, contracting provisions, selection of ...

  10. DOE Releases Federal Building Metering Guidance

    Broader source: Energy.gov [DOE]

    The guidance requires federal agencies to review, revise, and submit to FEMP its metering implementation plan within one year.

  11. FTCP Assessment Guidance and Criteria

    Broader source: Energy.gov [DOE]

    This document establishes the guidance and criteria for conducting internal and independent Federal Technical Capability Assessments within the Department. The requirements of this document are applicable to those organizations having safety responsibilities for defense nuclear facilities. This includes both headquarters and field organizations. Regardless of the type of assessment conducted, the objectives and criteria within this document are used as a basis for the assessment. Use of consistent objectives and criteria is necessary to establish baselines and to track and trend performance.

  12. Review of the IEEE Standard for Computerized Operating Procedure Systems

    SciTech Connect (OSTI)

    O'Hara, J.; Higgins, J.

    2010-02-26

    Increasingly nuclear power plant procedures, such as emergency operating procedures, are being presented in computer form with functionality to support operator use and management of the procedures. The U.S. Nuclear Regulatory Commission (NRC) currently has guidance for the review of computer-based procedures (CBPs); however, there remain CBP functions and human performance issues for which up-to-date guidance is lacking. The Institute of Electrical and Electronics Engineers (IEEE) has initiated a standard development effort to address the human factors engineering (HFE) aspects of CBP systems. When completed, it may provide guidance to supplement the NRC staff's review criteria. The purpose of our study was to evaluate the suitability of the IEEE Standard for use in the NRC's HFE safety reviews of CBP systems and to ensure that the guidance meets the NRC's standard for scientific and engineering rigor used in its own guidance development efforts. We established the following criteria with which to evaluate the Standard: (1) it should meet an existing need of NRC reviewers, (2) it should be based in sound HFE principles, (3) it should be thoroughly peer-reviewed, and (4) it should address CBP-related human performance issues identified in the literature. This report describes the methodology we used to evaluate each criterion. Our evaluation concluded that the Standard generally does meet these criteria, however several areas were identified for which additional clarifications are needed. Thus consideration of the Standard's use by the NRC is supported. The standard evaluation methodology developed in this study can be generally applied to the review of other HFE standards being considered for possible use or endorsement by the NRC.

  13. POLICY GUIDANCE MEMORANDUM #01 Documenting Hires Funded by ARRA (Expired)

    Broader source: Energy.gov [DOE]

    THIS GUIDANCE HAS EXPIRED Guidance on Documenting Hires funded by American Recovery and Reinvestment Act of 2009

  14. DOE Indian Energy Purchase Preference Policy Guidance | Department of

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

    Energy Indian Energy Purchase Preference Policy Guidance DOE Indian Energy Purchase Preference Policy Guidance PDF_FINAL DOE Indian Energy purchase preference policy guidance.pdf (266.84 KB) More Documents & Publications State Energy Program Notice 14-2, Implementation Model Guidance FY 2014-2024 Ten Year Site Plan Preparation Guidance Revised Guidance for Recruitment, Retention and Relocation Incentives

  15. Commercial Grade Dedication Guidance | Department of Energy

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

    Guidance Commercial Grade Dedication Guidance This Guide provides an acceptable process (Commercial Grade Dedication [CGD]) for EM facilities and projects to dedicate an item or service that performs a nuclear safety function that was not manufactured, developed, or performed under a qualified American Society of Mechanical Engineers (ASME) NQA-1 Quality Assurance program. This Guide also provides guidance for the development of the associated documentation supporting the dedication activity.

  16. Energy Sector Cybersecurity Framework Implementation Guidance | Department

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

    of Energy Cybersecurity Framework Implementation Guidance Energy Sector Cybersecurity Framework Implementation Guidance On January 8, 2015, the Energy Department released guidance to help the energy sector establish or align existing cybersecurity risk management programs to meet the objectives of the Cybersecurity Framework released by the National Institutes of Standards and Technology (NIST) in February 2014. The voluntary Cybersecurity Framework consists of standards, guidelines, and

  17. Adverse Diversity Analysis Guidance | Department of Energy

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

    Adverse Diversity Analysis Guidance Adverse Diversity Analysis Guidance Attachment 8 - Adverse Diversity Analysis Guidance (124.04 KB) Attachment 8(a) - WFR disparate impact chart example completed (96.18 KB) Attachment 8(b) - WFR disparate impact chart clean (88.56 KB) More Documents & Publications Fact #922: April 25, 2016 Share of Older Population Holding Driver's Licenses is Up and Share of Younger Population Holding Driver's Licenses is Down - Dataset FAIR Act Inventory - FY13 Fayette

  18. CAP Program Guidance | Department of Energy

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

    CAP Program Guidance CAP Program Guidance In 2002, the Department of Energy signed an interagency agreement with the Department of Defense's Computer/Electronic Accommodations Program (CAP) program to provide assistive/adaptive technology free of charge to DOE employees with disabilities. The following information regarding CAP is being provided to assist federal employees, managers and on- site disability coordinators with the CAP application process. CAP Program Guidance (40.26 KB) Responsible

  19. Multiyear Program Plan Template - Phase II Guidance

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

    Multi-Year Program Plan Guidance and Template Page For questions or help, contact the PM Help Desk at PMHelpDesk @ee.doe.gov EERE Multi- Year Program Plan Guidance and Template July 2016 Prepared by the Project Management Coordination Office (PMCO) EERE Multi-Year Program Plan Guidance and Template Page i For questions or help, contact the PM Help Desk at PMHelpDesk @ee.doe.gov Table of Contents Part I - Multi-Year Program Plan (MYPP)

  20. Policy, Guidance & Reports | Department of Energy

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

    Reports Policy, Guidance & Reports The Department of Energy's (DOE) Office of Environment, Health, Safety and Security (EHSS) administers DOE-wide health, safety, security and environmental policy, programs and guidance, and related federal requirements that support DOE's mission accomplishment in a safe, secure and environmentally responsible manner. Guidance documents are developed to support effective implementation of directives and standards and provide technical positions on

  1. Commissioning Guidance for ESPCs | Department of Energy

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

    Guidance for ESPCs Commissioning Guidance for ESPCs Document provides a description of how commissioning in energy savings performance contract (ESPC) projects can achieve the objective of meeting or exceeding facility performance requirements by optimizing the operation and efficiency of building systems and equipment. Download the Commissioning Guidance. (316.39 KB) More Documents & Publications FEMP Comprehensive ESPC Workshop Presentations Investment-Grade Audit Kickoff Meeting Sample

  2. Enforcement Guidance Supplements | Department of Energy

    Office of Environmental Management (EM)

    To better support and describe implementation of the Department of Energy's nuclear safety enforcement program, over the years the Office of Enforcement has developed guidance (in ...

  3. NEPA Contracting Reform Guidance (December 1996)

    Broader source: Energy.gov [DOE]

    This guidance provides: model statements of work, information on contract types and incentives, direction on effective NEPA contract management by the NEPA Document Manager, a system for measuring...

  4. Standardized Permit Guidance | Open Energy Information

    Open Energy Info (EERE)

    current through August 7, 2014. Published NA Year Signed or Took Effect 2006 Legal Citation Standardized Permit Guidance (2006) DOI Not Provided Check for DOI availability:...

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

    Open Energy Info (EERE)

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

  6. Guidance Regarding Refinancing, Restructuring, or Modifying Loan...

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

    Regarding Refinancing, Restructuring, or Modifying Loan Agreements Entered into by an Energy Services Company Under a Federal Energy Savings Performance Contract Guidance Regarding...

  7. 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...

  8. EERE 810 - Peer Review Guidance - June 2016

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

    EERE 810 Peer Review Guidance June 2016 Template Version: 6/24/2016 June 2016 Table of Contents What Has Changed?................................................................................................................................................ 3 Executive Summary................................................................................................................................................. 3 1 Introduction

  9. GC GUIDANCE ON MINOR CONSTRUCTION THRESHOLDS

    Energy Savers [EERE]

    GUIDANCE ON MINOR CONSTRUCTION THRESHOLDS We have been asked about how the Department implements what is known as the "minor construction threshold," which limits the amount of ...

  10. All NEPA Guidance | Department of Energy

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

    ... Final Guidance for Consideration of Environmental Justice in Clean Air Act 309 Reviews (1999) Pollution Prevention & Environmental Impact Reduction Checklists for NEPA309 ...

  11. Guidance Regarding NEPA Regulations (CEQ, 1983)

    Broader source: Energy.gov [DOE]

    This document provides Council on Environmental Quality guidance on several topics: scoping, categorical exclusions, adoption procedures, contracting provisions, selection of alternatives in licensing and permitting situations, and tiering.

  12. NEPA Contracting Reform Guidance | Department of Energy

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

    Guidance also provides: model statements of work, direction on NEPA contract management by NEPA Document Manager; a system for measuring NEPA costs and for evaluating contractor ...

  13. 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...

  14. Energy Sector Cybersecurity Framework Implementation Guidance

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

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

  15. Guidance on Inherently Governmental Functions | Department of...

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

    Federal law prohibits contractors from performing "inherently governmental functions." This guidance is designed to provide the basic rules applicable to the Department....

  16. New Guidance Helps LM Manage Institutional Controls

    Broader source: Energy.gov [DOE]

    The official Guidance for Developing and Implementing Institutional Controls for Long-Term Surveillance and Maintenance at DOE Legacy Management Sites, was issued in January as a supplemental...

  17. Environmental Justice: Guidance Under NEPA (CEQ, 1997)

    Broader source: Energy.gov [DOE]

    Guidance from the Council on Environmental Quality to assist Federal agencies with their NEPA procedures so that environmental justice concerns are effectively identified and addressed.

  18. Energy Sector Cybersecurity Framework Implementation Guidance...

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

    Department released guidance to help the energy sector establish or align existing cybersecurity risk management programs to meet the objectives of the Cybersecurity Framework...

  19. Draft Energy Sector Cybersecurity Framework Implementation Guidance...

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

    in the Federal Register, inviting the public to comment on DOE's Energy Sector Cybersecurity Framework Implementation Guidance. Comments must be received on or before October...

  20. Energy Sector Cybersecurity Framework Implementation Guidance...

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

    invites public comment on a draft of the Energy Sector Cybersecurity Framework Implementation Guidance. Comments must be received on or before October 14, 2014. The draft document...

  1. Hanford Site C Tank Farm Meeting Summary

    Office of Environmental Management (EM)

    danl@nezperce.org Sobczyk, Stan NPT (208) 621-3751 stans@nezperce.org Lowman, Don NRC (301) 415-5452 Donald.lowman@nrc.gov Schwartzman, Adam NRC (301) 415-8172...

  2. Hanford Site C Tank Farm Meeting Summary

    Office of Environmental Management (EM)

    davidb@nezperce.org Sobczyk, Stan NPT-ERWM 208-621-3751 stans@nezperce.org Lowman, Don NRC 301-415-5452 donald.lowman@nrc.com McKenney, Chris NRC 301-415-6663...

  3. State Energy Program 2015 Formula Grant Guidance | Department of Energy

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

    Formula Grant Guidance State Energy Program 2015 Formula Grant Guidance The document below is effective February 27, 2015 and offers State Energy Program Formula Grant Guidance for Program Year 2015. SEP 2015 Formula Grant Guidance (1.48 MB) More Documents & Publications State Energy Program 2016 Formula Grant Guidance State Energy Program 2014 Formula Grant Guidance Program Year 2013 State Energy Program Formula Grant Guidance

  4. State Energy Program 2016 Formula Grant Guidance | Department of Energy

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

    Formula Grant Guidance State Energy Program 2016 Formula Grant Guidance The document below is effective Feb. 26, 2016, and offers State Energy Program Formula Grant Guidance for Program Year 2016. SEP 2016 Formula Grant Guidance (6.45 MB) More Documents & Publications State Energy Program 2015 Formula Grant Guidance State Energy Program 2014 Formula Grant Guidance Program Year 2013 State Energy Program Formula Grant Guidance

  5. 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 Cybersecurity Framework Implementation Guidance │ Table of Contents TABLE OF CONTENTS 1. Introduction .............................................................................................................................................. 1 2. Preparing for Framework Implementation

  6. Guidance for Procurement Officials | Department of Energy

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

    for Procurement Officials Guidance for Procurement Officials Acquisition Regulations Federal Acquisition Regulation (FAR) Department of Energy Acquisition Regulation (DEAR) Acquisition Policy Acquisition Letters Acquisition Guidance Acquisition Guide Contracting for Support Services Department of Energy Acquisition System - A Guide for Executives Ethics in Procurement Lobbying Brochure Procurement Integrity Brochure Unsolicited Proposals Balanced scorecard Balanced Scorecard performance

  7. Guidance for performing preliminary assessments under CERCLA

    SciTech Connect (OSTI)

    1991-09-01

    EPA headquarters and a national site assessment workgroup produced this guidance for Regional, State, and contractor staff who manage or perform preliminary assessments (PAs). EPA has focused this guidance on the types of sites and site conditions most commonly encountered. The PA approach described in this guidance is generally applicable to a wide variety of sites. However, because of the variability among sites, the amount of information available, and the level of investigative effort required, it is not possible to provide guidance that is equally applicable to all sites. PA investigators should recognize this and be aware that variation from this guidance may be necessary for some sites, particularly for PAs performed at Federal facilities, PAs conducted under EPA`s Environmental Priorities Initiative (EPI), and PAs at sites that have previously been extensively investigated by EPA or others. The purpose of this guidance is to provide instructions for conducting a PA and reporting results. This guidance discusses the information required to evaluate a site and how to obtain it, how to score a site, and reporting requirements. This document also provides guidelines and instruction on PA evaluation, scoring, and the use of standard PA scoresheets. The overall goal of this guidance is to assist PA investigators in conducting high-quality assessments that result in correct site screening or further action recommendations on a nationally consistent basis.

  8. Information and Records Management Transition Guidance | Department of

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

    Energy Information and Records Management Transition Guidance Information and Records Management Transition Guidance Information and Records Management Transition Guidance (March 2004) Information and Records Management Transition Guidance (869.4 KB) More Documents & Publications LM Records and Information Management Transition Guidance (May 2016) ADMINISTRATIVE RECORDS SCHEDULE 20: ELECTRONIC RECORDS ADMINISTRATIVE RECORDS SCHEDULE 20: ELECTRONIC RECORDS

  9. PWR FLECHT SEASET 21-rod-bundle flow-blockage task: data and analysis report. NRC/EPRI/Westinghouse report No. 11, main report and appendices A-J

    SciTech Connect (OSTI)

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

    1982-09-01

    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.

  10. Appendix D References | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    ... NRC (US Nuclear Regulatory Commission) 1975. Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. WASH-1400, NUREG-75014. October. NRC ...

  11. SPD SEIS References for Appendix J | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    17. 462 NRC (U.S. Nuclear Regulatory Commission), 2012c, "Actions in Response to the Japan Nuclear Accident" (accessed May 9, 2012, http:www.nrc.govreactorsoperating...

  12. DOE Announces New Manager for the Carlsbad Field Office

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

    (NRC) licensing process for the Yucca Mountain Project, including work on the safety basis, programmatic impacts, and long-term performance of a repository during NRC review. ...

  13. Microsoft PowerPoint - 8_Morello NMMSS_2013_Presentation_Morello...

    National Nuclear Security Administration (NNSA)

    on NMMSS Licensee Issues First Step... - Meeting held with Paul Peduzzi (NRC), Ron Albert (NRC), Andrew Mauer (NEI) and Tom Morello (CENG) October 2012. - The issues from the...

  14. Nuclear Safety Information Agreement Between the U.S. Nuclear...

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

    DOE), Cathy Haney (Director, Office of Nuclear Materials Safety and Safeguards (NRC)), ... (NRC)) Back Row: Tom Hiltz, Office of Nuclear Safety (EHSS DOE), Roy Zimmerman (Deputy ...

  15. TRIBAL ISSUES TOPIC GROUP CONFERENCE CALL SUMMARY (April 26,

    Office of Environmental Management (EM)

    Alcorn (DOEEM), Kevin Blackwell (DOT), Judith Bradbury (PNL), Stephanie Bush-Goddard (NRC), Kevin Clarke (DOERL), Martha Crosland (DOEEM), Tony Dipalo (NRC), Spiros Droggitis...

  16. DOE - Office of Legacy Management -- El_Verde

    Office of Legacy Management (LM)

    16, 2015 Other Documents Regulatory Status of Study Area 4 July 10, 2008 Amendment of NRC Materials License November 16, 2005 Amendment of NRC Materials License September 12,...

  17. Federal Register Notice | Department of Energy

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

    The purpose of this workshop is to gather information from a broad spectrum of stakeholders concerning the NRC's proposed options for a comprehensive revision to NRC's and DOE's ...

  18. Regulatory Guide 5.29, Revision 2, "Special Nuclear Material...

    National Nuclear Security Administration (NNSA)

    may be submitted through the NRC's public Web site under the Regulatory Guides document ... are available through the NRC's public Web site under the Regulatory Guides document ...

  19. LLWnotes - Volume 11, Number 6 August/September 1996

    SciTech Connect (OSTI)

    1996-09-01

    This document is the August/September 1996 issue of LLWnotes. It contains articles and news items on the following topics: California Department of Health Services questions accuracy of waste data; NRC authority over land transfers; Southeast Commission funding of North Carolina project; study of federal siting criteria; court rulings and calendar; wetland classifications; DOE tritium purchase options; control over licensed devices; revised EPA risk assessment model; EPA environmental justice guidance; possible effects of EPA guidance on LLRW disposal; elements of an adequate LLRW program; NRC Information Notice on on-site land burials; and a decommissioning schedule petition.

  20. Guidance on the Consideration of Past Actions in Cumulative Effects...

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

    Information, Final Rule DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and Greenhouse Gas Emissions CEQ Guidance on the Application of NEPA to ...

  1. Guidance for Requesting Emergency Oil from the SPR | Department...

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

    Services Petroleum Reserves Strategic Petroleum Reserve Guidance for Requesting Emergency Oil from the SPR Guidance for Requesting Emergency Oil from the SPR If hurricanes ...

  2. 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

  3. Guidance for Fiscal Year 2015 Facilities Information Management...

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

    Guidance for Fiscal Year 2015 Facilities Information Management System Data Validations Guidance for Fiscal Year 2015 Facilities Information Management System Data Validations PDF...

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

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

    Recipients on Program Evaluation Guidelines Guidance for Energy Efficiency and Conservation Block Grant Recipients on Program Evaluation Guidelines Guidance for Energy Efficiency ...

  5. SEP Program Notice 10-008E, Financing Programs Guidance

    Broader source: Energy.gov [DOE]

    This guidance provides information to State Energy Program grantees on financing programs. This guidance supersedes SEP Program notice 10-008D, which was issued Oct. 26, 2012.

  6. EECBG Appliance Rebate Guidance (Program Notice 10-015) | Department...

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

    EECBG Appliance Rebate Guidance (Program Notice 10-015) Guidance for Efficiency and Conservation Block Grant Program grantees on consumer rebate programs for Energy Star and other ...

  7. Building America Technology Solutions Case Study: Design Guidance...

    Energy Savers [EERE]

    Design Guidance for Passive Vents in New Construction, Multifamily Buildings Building America Technology Solutions Case Study: Design Guidance for Passive Vents in New Construction...

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

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

    Office of Personnel Management (OPM) Guidance on Diversity and Inclusion Office of Personnel Management (OPM) Guidance on Diversity and Inclusion The following documents are from ...

  9. OfficeGovernmentEthicsGuidanceEthicsandProcurementIntegrity.pdf...

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

    OfficeGovernmentEthicsGuidanceEthicsandProcurementIntegrity.pdf OfficeGovernmentEthicsGuidanceEthicsandProcurementIntegrity.pdf (2.33 MB) More Documents & Publications POLICY FLASH ...

  10. Guidance for FY2014 Facilities Information Management System...

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

    FY2014 Facilities Information Management System Data Validations Guidance for FY2014 Facilities Information Management System Data Validations FY 2014 FIMS Data Validation Guidance ...

  11. DOE Issues Enforcement Guidance on Large-Capacity Clothes Washer...

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

    Enforcement Guidance on Large-Capacity Clothes Washer Waivers and the Waiver Process DOE Issues Enforcement Guidance on Large-Capacity Clothes Washer Waivers and the Waiver Process...

  12. Guidance on Ex Parte Communications | Department of Energy

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

    Ex Parte Communications Guidance on Ex Parte Communications The Department of Energy sets forth guidance on ex parte communications during informal rulemaking proceedings. The ...

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

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

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

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

    Energy Savers [EERE]

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

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

    Energy Savers [EERE]

    Guidance for the Preparation of Department of Energy (DOE) Annual Site Environmental reports (ASERs) for Calendar Year 2014 Memorandum Guidance for the Preparation of Department of ...

  16. Guidance for Preparation of the 2014 Department of Energy Annual...

    Office of Environmental Management (EM)

    Guidance for Preparation of the 2014 Department of Energy Annual Site Environmental Reports Guidance for Preparation of the 2014 Department of Energy Annual Site Environmental ...

  17. Utah Air Guidance Documents Webpage | Open Energy Information

    Open Energy Info (EERE)

    link for Utah Air Guidance Documents Webpage Citation Utah Department of Environmental Quality. Utah Air Guidance Documents Webpage Internet. State of Utah. cited 201411...

  18. DRAFT NEPA Guidance on Consideration of the Effects of Climate...

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

    DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and Greenhouse Gas Emissions DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and ...

  19. Policy Guidance Memorandum #36 SES Competitive Staffing Procedures

    Broader source: Energy.gov [DOE]

    Policy Guidance Memorandum #36 provides overarching policy guidance and implementing procedures for the Senior Executive Service (SES) competitive recruitment process to ensure consistency,...

  20. Application Submittal Guidance for Stormwater Permits andPost...

    Open Energy Info (EERE)

    Post-Authorization Stormwater Permit CorrespondencePermittingRegulatory GuidanceGuideHandbook Abstract Application Submittal Guidance for Stormwater Permits and...

  1. Renewable Energy Requirement Guidance for EPAct 2005 | Department...

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

    Guidance originally specified conditions for agencies to meet the renewable energy ... and is still applicable. Download the Renewable Energy Requirement Guidance for EPAct ...

  2. Transmittal Letter for Final Federal Renewable Energy Guidance...

    Office of Environmental Management (EM)

    Transmittal Letter for Final Federal Renewable Energy Guidance Transmittal Letter for Final Federal Renewable Energy Guidance Letter to federal energy officials summarizing the new ...

  3. 2015 Federal Real Property Council Reporting Guidance | Department...

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

    2015 Federal Real Property Council Reporting Guidance 2015 Federal Real Property Council Reporting Guidance Real Property Reporting: EO 13327 requires agencies to report annually ...

  4. Army Corps of Engineers - Regulatory Guidance Letters | Open...

    Open Energy Info (EERE)

    Guidance Letters Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Army Corps of Engineers - Regulatory Guidance Letters Abstract This webpage...

  5. Guidance for Site-wide Environmental Impact Statements | Department...

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

    guidance for Site-wide Environmental Impact Statements PDF icon Guidance for Site-wide Environmental Impact Statements More Documents & Publications Recommendations on...

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

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

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

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

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

    Guidance on Consideration of Greenhouse Gas Emissions and the Effects of Climate Change in NEPA Reviews CEQ Issues Revised Draft Guidance on Consideration of Greenhouse Gas ...

  8. Revised Draft Guidance on Consideration of Greenhouse Gas Emissions...

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

    Draft Guidance on Consideration of Greenhouse Gas Emissions and Climate Change in NEPA Reviews Revised Draft Guidance on Consideration of Greenhouse Gas Emissions and Climate ...

  9. POLICY GUIDANCE MEMORANDUM #21 Family Members | Department of...

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

    More Documents & Publications Office of Personnel Management (OPM) Guidance on Diversity and Inclusion POLICY GUIDANCE MEMORANDUM 14 Establishing a Residence for a Relocation ...

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

    Office of Environmental Management (EM)

    Actions That May Proceed During the NEPA Process: Interim Actions Guidance Regarding Actions That May Proceed During the NEPA Process: Interim Actions DOE guidance to provide...

  11. General Counsel's Office Issues Guidance on Inherently Governmental...

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

    General Counsel's Office Issues Guidance on Inherently Governmental Functions General Counsel's Office Issues Guidance on Inherently Governmental Functions February 4, 2011 -...

  12. Guidance for Meeting Executive Order 13514 Water Goals | Department...

    Energy Savers [EERE]

    Water Efficiency Guidance for Meeting Executive Order 13514 Water Goals Guidance for Meeting Executive Order 13514 Water Goals The Federal Energy Management Program offers...

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

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

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

  14. POLICY GUIDANCE MEMORANDUM #34B Direct Hire Authority for Contract...

    Office of Environmental Management (EM)

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

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

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

    2 Payment of Expenses for Professional Credentials POLICY GUIDANCE MEMORANDUM 12 Payment of Expenses for Professional Credentials Departmental guidance to authorize payments to ...

  16. 2013 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

    Plan Report Memo, Guidance and Template 2013 Workforce Analysis and Staffing Plan Report Memo, Guidance and Template The Department of Energy Federal Technical Capability ...

  17. 2014 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

    Plan Report Memo, Guidance and Template 2014 Workforce Analysis and Staffing Plan Report Memo, Guidance and Template The Department of Energy Federal Technical Capability ...

  18. 2015 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

    Plan Report Memo, Guidance and Template 2015 Workforce Analysis and Staffing Plan Report Memo, Guidance and Template The Department of Energy Federal Technical Capability ...

  19. 2011 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

    Plan Report Memo, Guidance and Template 2011 Workforce Analysis and Staffing Plan Report Memo, Guidance and Template The Department of Energy Federal Technical Capability ...

  20. Smart Grid Grant Program Recipient Reporting Guidance, Updated...

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

    Smart Grid Grant Program Recipient Reporting Guidance, Updated Reporting guidance for the Smart Grid Investment Grant project under the American Recovery and Reinvestment Act. ...

  1. 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 ...

  2. Additional Guidance for EERE Digital Data Management Plans |...

    Office of Environmental Management (EM)

    Services Funding Digital Data Management Additional Guidance for EERE Digital Data Management Plans Additional Guidance for EERE Digital Data Management Plans Beyond the ...

  3. Digital Data Management Additional Guidance | Department of Energy

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

    Additional Guidance Digital Data Management Additional Guidance Beyond the Office of Energy Efficiency and Renewable Energy (EERE) digital data management requirements, the ...

  4. DOE Showerhead Enforcement Guidance, March 4, 2011 | Department...

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

    Showerhead Enforcement Guidance, March 4, 2011 DOE Showerhead Enforcement Guidance, March 4, 2011 A showerhead with multiple nozzles constitutes a single showerhead for purposes of ...

  5. DOE Launches Public Test Procedure Guidance Website

    Broader source: Energy.gov [DOE]

    The Department of Energy this week launched a new online database offering guidance on the Department’s test procedures for appliances and commercial equipment.  The new database will provide a...

  6. POLICY GUIDANCE MEMORANDUM #03 Addressing Missclassified Positions

    Broader source: Energy.gov [DOE]

    This memorandum provides policy guidance on how to consistently address misclassified positions within the Department and is effective immediately. There are several different circumstances that affect how a misclassified position will be addressed.

  7. Guidance for EPAct 2005 Section 242 Program

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

    Guidance for EPAct 2005 Section 242 Program I. Purpose In the Energy Policy Act of 2005 (EPAct 2005; Public Law 109-58) Congress established a new program to support the expansion ...

  8. Guidance for Developing and Implementing Institutional Controls

    Office of Energy Efficiency and Renewable Energy (EERE)

    This guidance document is to help U.S. Department of Energy (DOE) Office of Legacy Management (LM) personnel understand what is necessary and acceptable for implementing the provisions of DOE...

  9. SORN Template and Guidance | Department of Energy

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

    Privacy Act System of Records Notice (PDF) System of Record Notice template with guidance in a Microsoft Word format. SORN-TemplateJune2009(1).doc (40 KB) More Documents & ...

  10. Ingestion of phosphorus-32 at Massachusetts Institute of Technology, Cambridge, Massachusetts, identified on August 19, 1995

    SciTech Connect (OSTI)

    1995-12-01

    On Monday, October 16, 1995, the Massachussetts Institue of Technology (MIT, the licensee) notified the US Nuclear Regulatory Commission (NRC) of an incident involving ingestion of phosphorus-32 by a researcher at the MIT Center for Cancer Research. The licensee informed the NRC that a researcher had reported the incident on August 19. The licensee initially estimated the intake as 500 microcuries (19 MBq) and the dose as 4000 millirem (40 mSv) to the individual. On October 12, the licensee informed the researcher that its final intake estimate was 579 microcuries (21 MBq), just under the 600 microcuries (22 MBq) which would represent an overexposure. On October 17, the NRC established an Incident Investigation Team to investigate the case. NRC also contracted with Lawrence Livermore National Laboratory and Oak Ridge Institute for Science and Education to do independent dose assessments of the urine sample data and the whole-body data. The Team concluded that the licensee`s final intake and dose estimates were in accordance with accepted scientific references and NRC guidance. However, recognizing the uncertainties involved in the use of models to simulate human characteristics, the Team determined the intake would be better characterized as likely falling within a range of 500 to 750 microcuries (19--28 NMq). An NRC medical consultant concluded that no symptoms or acute effects should be observed from an intake of this level.

  11. SGIG Reporting Guidance Archive | Department of Energy

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

    SGIG Reporting Guidance Archive SGIG Reporting Guidance Archive July 22, 2010-- Federal Register Notice on the DOE's invitation for public comment on request to the Office of Management and Budget (OMB) to extend for three years the emergency Information Collection Request Title: OE Recovery Act Financial Assistance Grants, OMB Control No. 1910-5149 that DOE has submitted to OMB pursuant to the Paperwork Reduction Act of 1995. Comments due on or before August 21, 2010. More> Public comments

  12. Weatherization Program Guidance | Department of Energy

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

    Program Guidance Weatherization Program Guidance The U.S. Department of Energy's (DOE's) Weatherization Assistance Program (WAP) is governed by various federal regulations designed to help manage and account for the resources provided by DOE. Each year, Congress passes a Weatherization Assistance Program Appropriation. Find active and archived weatherization program notices and memorandums in the table below, which establish the framework for administering WAP funds. Type Topic Weatherization

  13. Laser-guidance systems, security classification. Instruction

    SciTech Connect (OSTI)

    Flickinger, A.

    1982-12-03

    The Instruction reissues Department of Defense (DoD) Instruction 5210.62, April 25, 1980, and prescribes policies, standards, and criteria governing the security classification of information pertaining to any laser-guidance system that is developed in whole or in part with information or knowledge obtained from or developed for the Department of Defense; and provides guidance to DoD Components responsible for issuing security classification guides for individual systems and equipment under their control.

  14. Policy and Guidance | Department of Energy

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

    Guidance Policy and Guidance Strategic directions are influenced by an analysis of budget and workforce projections and plans, congressional mandates, administration goals, Departmental priorities and mission needs. Human capital management strategies, policy, programs and plans are developed and assessed for overall success and compliance with merit system principals, civil service laws and regulations, and Departmental HCM directives. OCHCO is the primary representative body for the Department

  15. SEP/EECBG Reporting Guidance FAQs | Department of Energy

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

    EECBG Reporting Guidance FAQs SEP/EECBG Reporting Guidance FAQs sep_eecbg_reporting_guidance_faqs_06242011.pdf (29.52 KB) More Documents & Publications Letter to EECBG Recipients on Changes to Reporting Requirements Letter to SEP Recipients on Changes to Reporting Requirements Reporting Pre-guidance Announcement 06-02-2011

  16. Draft Policy and Planning Guidance for Community Transition Activities

    Broader source: Energy.gov [DOE]

    Planning Guidance for Contractor Work Force RestructuringOffice of Worker and Community Transition 

  17. FY18 Major IT Business Case Guidance | Department of Energy

    Energy Savers [EERE]

    Major IT Business Case Guidance FY18 Major IT Business Case Guidance FY18 MITBC Technical Guidance (FINAL).pdf (1.95 MB) More Documents & Publications FY18 Agency IT Portfolio Summary Guidance IT Reporting Format and Requirements for the BY 2017 Budget Submission eCPIC User Request Form

  18. 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.

  19. POLICY GUIDANCE MEMORANDUM #23 Permanent and Nonpermanent Positions, Appointments, & CHRIS Codes

    Broader source: Energy.gov [DOE]

    Policy Guidance Memorandum #23 - DOE Guidance – Permanent and Nonpermanent Positions, Appointments, & CHRIS Codes

  20. Section 106 Archaeology Guidance (ACHP, 2009)

    Broader source: Energy.gov [DOE]

    The Advisory Council on Historic Preservation's Section 106 guidance is designed to assist federal agencies in making effective management decisions about archaeological resources in completing the requirements of Section 106 of the National Historic Preservation Act (16 U.S.C. 470f) and its implementing regulations (36 CFR Part 800). This guidance highlights the decision-making role of the federal agency in the Section 106 process. It is also designed for use by State and Tribal Historic Preservation Officers, Indian tribes, Native Hawaiian organizations, and cultural resource management professionals when assisting federal agencies to meet their responsibilities under Section 106.

  1. SECTION J, APPENDIX L - DIVERSITY PLAN GUIDANCE

    National Nuclear Security Administration (NNSA)

    L, Page 1 SECTION J APPENDIX L [Note: The Diversity Plan shall be submitted to the Contracting Officer in accordance with DEAR 970.5226-1] DIVERSITY PLAN GUIDANCE 12/1/10 In accordance with the Contract's Section I Clause entitled "DEAR 970.5226-1, Diversity Plan," this Appendix provides guidance to assist the Contractor in understanding the information being sought by the Department of Energy, National Nuclear Security Administration (DOE/NNSA) for each of the clause's Diversity

  2. Guidance for Potential ATVM Applicants (June 2016)

    Broader source: Energy.gov [DOE]

    The Advanced Technology Vehicles Manufacturing Loan Program (ATVM Program) is administered by the U.S. Department of Energy’s (DOE) Loan Programs Office (LPO). This guidance for the ATVM Program applicants covers the following areas: General Eligibility Requirements, General Application Requirements, Pre-Application Consultation, and Application Process.

  3. Recovery Act Program Guidance by Topic

    Broader source: Energy.gov [DOE]

    Guidance documents under the 2009 American Recovery and Reinvestment Act for the U.S. Department of Energy and the State Energy Program and Energy Efficiency and Conservation Block Grant program for state, local governments, U.S. overseas territories, and Indian Tribal governments.

  4. Hanford Site C Tank Farm Meeting Summary

    Office of Environmental Management (EM)

    378-3187 Dirk.a.dunning@state.or.us Arlt, Hans NRC (301) 415-5845 hda@urc.gov Lowman, Don NRC (301) 415-2026 Donald.Lowman@nrc.gov McKenney, Chris NRC (301) 415-6663...

  5. Identification and Prioritization of Technical Issues

    Broader source: Energy.gov [DOE]

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

  6. US Nuclear Regulatory Commission functional organization charts

    SciTech Connect (OSTI)

    Not Available

    1988-01-01

    This document provides functional organization charts for all NRC Offices and Regions, and their components.

  7. US Nuclear Regulatory Commission functional organization charts

    SciTech Connect (OSTI)

    Not Available

    1986-11-30

    Functional organization charts for the NRC Commission Offices, Divisions, and Branches are presented.

  8. U. S. Nuclear Regulatory Commission functional organization charts

    SciTech Connect (OSTI)

    Not Available

    1982-02-01

    Functional organization charts for the NRC Commission Offices, Divisions, Staffs and Branches are presented.

  9. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    SciTech Connect (OSTI)

    1996-02-01

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  10. Safety Planning Guidance for Hydrogen and Fuel Cell Projects...

    Energy Savers [EERE]

    Safety Planning Guidance for Hydrogen and Fuel Cell Projects Safety Planning Guidance for Hydrogen and Fuel Cell Projects Hydrogen and fuel cell project safety by U.S. Department ...

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

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

    Building America Climate-Specific Guidance Building America Climate-Specific Guidance Marine Hot-Humid Hot-DryMixed-Dry Mixed-Humid ColdVery Cold Click on the map to access case...

  12. Mini-Guidance Articles from Lessons Learned Quarterly Reports...

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

    Mini-Guidance Articles from Lessons Learned Quarterly Reports, Dec. 1994 to Sept. 2005 Mini-Guidance Articles from Lessons Learned Quarterly Reports, Dec. 1994 to Sept. 2005 The ...

  13. Nevada Solid Waste Forms and Guidance Documents Webpage | Open...

    Open Energy Info (EERE)

    Solid Waste Forms and Guidance Documents Webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Nevada Solid Waste Forms and Guidance Documents...

  14. WPN 08-6: Interim Lead-Safe Weatherization Guidance

    Broader source: Energy.gov [DOE]

    To provide additional guidance for an LSW component of a health and safety plan. This guidance builds on the foundation provided in WPN 02-6, Weatherization Activities and Federal Lead Based Paint Regulations.

  15. Policy Flash 2013-26 Guidance for tracking inquiries related...

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

    6 Guidance for tracking inquiries related to the licensing of inventions developed at DOE facilities Policy Flash 2013-26 Guidance for tracking inquiries related to the licensing of ...

  16. GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM...

    Energy Savers [EERE]

    GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM The Department of Energy has on a variety of occasions ...

  17. DOE, Treasury Provide Guidance on Direct Payments for Renewable...

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

    DOE, Treasury Provide Guidance on Direct Payments for Renewable Projects DOE, Treasury Provide Guidance on Direct Payments for Renewable Projects July 15, 2009 - 2:33pm Addthis DOE...

  18. Safety Planning Guidance for Hydrogen and Fuel Cell Projects...

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

    Safety Planning Guidance for Hydrogen and Fuel Cell Projects Safety Planning Guidance for Hydrogen and Fuel Cell Projects Hydrogen and fuel cell project safety by U.S. Department...

  19. NNSA Supplemental Guidance: NA-1 SD G 1027 | Department of Energy

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

    Supplemental Guidance: NA-1 SD G 1027 NNSA Supplemental Guidance: NA-1 SD G 1027 Guidance on using Release Fraction and Modern Dosimetric information consistently with DOE STD ...

  20. Final Guidance for Effective Use of Programmatic NEPA Review...

    Energy Savers [EERE]

    for proposals that affect the resources they manage. http:www.whitehouse.govadministrationeopceqinitiativesnepaprogrammatic-reviews Final Guidance for Effective Use of ...

  1. WPN 03-1: Program Year 2003 Weatherization Grant Guidance

    Office of Energy Efficiency and Renewable Energy (EERE)

    To issue grant guidance and management information for the low-income Weatherization Assistance Program for Program Year 2003.

  2. Treasury, Energy Announce Guidance for Tax Treatment of Smart Grid

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

    Investment Grants | Department of Energy Guidance for Tax Treatment of Smart Grid Investment Grants Treasury, Energy Announce Guidance for Tax Treatment of Smart Grid Investment Grants March 10, 2010 - 12:00am Addthis Washington, DC - The Department of Treasury and the Department of Energy announced today new guidance on the tax treatment for grantees receiving Recovery Act funding under the $3.4 billion Smart Grid Investment Grant program. Under the guidance released today, the Internal

  3. WPN 04-1: Program Year 2004 Weatherization Grant Guidance

    Broader source: Energy.gov [DOE]

    To issue grant guidance and management information for the low-income Weatherization Assistance Program for Program Year 2004.

  4. Environmental Justice: Guidance Under the National Environmental Policy Act

    Broader source: Energy.gov [DOE]

    Environmental JusticeGuidance Under the National Environmental Policy ActCouncil on Environmental Quality (December 1997) 

  5. WPN 02-1: Program Year 2002 Weatherization Grant Guidance

    Office of Energy Efficiency and Renewable Energy (EERE)

    To issue grant guidance and management information for the low-income Weatherization Assistance Program for Program Year 2002.

  6. WPN 05-1: Program Year 2005 Weatherization Grant Guidance

    Broader source: Energy.gov [DOE]

    To issue grant guidance and management information for the low-income Weatherization Assistance Program (Weatherization) for Program Year 2005.

  7. Updated Guidance on Conference-Related Activities and Spending

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-12-06

    Updated guidance and requirements in this memorandum are the result of improved processes that have been developed.

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

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

    Positions (Expired) | Department of Energy 9A Direct Hire Authority for Acquisition Positions (Expired) POLICY GUIDANCE MEMORANDUM #09A Direct Hire Authority for Acquisition Positions (Expired) THIS GUIDANCE HAS EXPIRED This Policy on Direct Hire Authority for Acquisition Positions has been replaced by POLICY GUIDANCE MEMORANDUM #34B Direct Hire Authority for Contract Specialist Positions POLICY GUIDANCE MEMORANDUM #09A Direct Hire Authority for Acquisition Positions (Expired) (49.21 KB)

  9. WPN 13-1: Program Year 2013 Weatherization Grant Guidance

    Broader source: Energy.gov [DOE]

    To issue grant guidance and management information for the Weatherization Assistance Program (WAP) for Program Year (PY) 2013.

  10. GC Guidance on Conducting and Participating in Conferences | Department of

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

    Energy Guidance on Conducting and Participating in Conferences GC Guidance on Conducting and Participating in Conferences Guidance and FAQs on DOE Employees Participating in and/or Hosting Conferences GC Conference Guidance.pdf (83.86 KB) Conference Co-sponsorship Template.pdf (26.97 KB) More Documents & Publications Acquisition Letter No. AL 2015-09 POLICY FLASH 2015-36 - AL 2015-09 Inspection Report: IG-0433

  11. Guidance for Energy Efficiency and Conservation Block Grant Grantees on

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

    Financing Programs | Department of Energy Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing Programs Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing Programs Provides general guidance to the U.S. Department of Energy's Energy Efficiency and Conservation Block Grant grantees on financing programs. Author: U.S. Department of Energy Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing Programs (447.91

  12. Guidance on Ex Parte Communications | Department of Energy

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

    on Ex Parte Communications Guidance on Ex Parte Communications Notice of guidance on ex parte communications. The Department of Energy sets forth guidance on ex parte communications during informal rulemaking proceedings. The guidance is intended to encourage the public to provide DOE with all information necessary to develop rules that advance the public interest, while ensuring that rulemaking proceedings are not subject to improper influence from off-the-record communications. As President

  13. Energy Efficiency and Conservation Block Grant Financing Program Guidance |

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

    Department of Energy Guidance Energy Efficiency and Conservation Block Grant Financing Program Guidance Relevant guidance for Energy Efficiency and Conservation Block Grant financing programs is provided below in the Grantee Letter and supporting appendices listed here. Appendix 1: EECBG Financing Program Annual Report (372.67 KB) Appendix 2: EECBG Program Notice 09-002D Guidance for Energy Efficiency and Conservation Block Grant Grantees on Financing Programs, revised October 17, 2012

  14. Federal Building Energy Use Benchmarking Guidance, August 2014 Update

    Broader source: Energy.gov [DOE]

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

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

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

    Program Employment Opps (Expired) | Department of Energy 8 Advertisement of Federal Career Intern Program Employment Opps (Expired) POLICY GUIDANCE MEMORANDUM #18 Advertisement of Federal Career Intern Program Employment Opps (Expired) THIS GUIDANCE HAS EXPIRED Guidance on advertising positions under the Federal Career Intern Program (FCIP) POLICY GUIDANCE MEMORANDUM #18 Advertisement of Federal Career Intern Program Employment Opps (Expired) (61.64 KB) Responsible Contacts Ahtora Brooks

  16. Energy Efficiency and Conservation Block Grant Program Guidance |

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

    Department of Energy Energy Efficiency & Conservation Block Grant Program » Energy Efficiency and Conservation Block Grant Program Guidance Energy Efficiency and Conservation Block Grant Program Guidance The Energy Efficiency and Conservation Block Grant (EECBG) Program released guidance documents that explain how the recipients of EECBG funds need to report and manage those funds. These documents are listed below by the year they were released. More program guidance documents are

  17. State Energy Program 2014 Formula Grant Guidance | Department of Energy

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

    Formula Grant Guidance State Energy Program 2014 Formula Grant Guidance The document below is effective March 19, 2014 and offers State Energy Program Formula Grant Guidance for Program Year 2014. SEP-Notice14-01.pdf (4.32 MB) More Documents & Publications State Energy Program 2014 Administrative and Legal Requirements Document Financing Energy Upgrades for K-12 School Districts Guidance for State Energy Program Grantees on Sub-Recipient Monitoring

  18. State Energy Program Formula Grant Guidance Program Year 2007 | Department

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

    of Energy Guidance Program Year 2007 State Energy Program Formula Grant Guidance Program Year 2007 This document provides instructions to the states for program year 2007 about how they should administer their DOE grants provided through the State Energy Program. fy07_grant_guidance.pdf (142.21 KB) More Documents & Publications State Energy Program Fiscal Year 2006 Formula Grant Guidance Program Year 2008 State Energy Program Formula Audit Report: OAS-M-06-05

  19. State Energy Program Notice 14-2, Implementation Model Guidance |

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

    Department of Energy 4-2, Implementation Model Guidance State Energy Program Notice 14-2, Implementation Model Guidance This State Energy Program (SEP) Notice 14-2 provides Implementation Model guidance for SEP competitive award recipients. SEP Program Notice 14-2 Implementation Model Guidance.pdf (3.89 MB) More Documents & Publications Clean Energy Finance Guide (Chapter 5: Basic Concepts for Clean Energy Unsecured Lending and Loan Loss Reserve Funds) Financing Energy Upgrades for K-12

  20. WPN 14-1: Program Year 2014 Weatherization Grant Guidance

    Office of Energy Efficiency and Renewable Energy (EERE)

    To issue grant guidance and management information for the Weatherization Assistance Program (WAP) for Program Year (PY) 2014.

  1. WPN 16-1: Program Year 2016 Weatherization Grant Guidance

    Office of Energy Efficiency and Renewable Energy (EERE)

    To issue grant guidance and management information for the Weatherization Assistance Program (WAP) for Program Year (PY) 2016.

  2. Guidance on Alternative Contract Language Regarding Energy Savings...

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

    on Alternative Contract Language Regarding Energy Savings Performance Contract Terminations and Cancellations Guidance on Alternative Contract Language Regarding Energy Savings ...

  3. DOE Advisory Committee Members' Ethics and Conflict of Interest Guidance |

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

    Department of Energy DOE Advisory Committee Members' Ethics and Conflict of Interest Guidance DOE Advisory Committee Members' Ethics and Conflict of Interest Guidance DOE Advisory Committee Members' Ethics and Conflict of Interest Guidance, as posted on the U.S. Department of Energy website. Ethics and Conflict of Interest Guidance (18.43 KB) More Documents & Publications GSA Federal Advisory Committee Management; Final Rule -- 41CFR Parts 101-6 and 102-3 DOE Manual - ADVISORY COMMITTEE

  4. Updated Guidance For Applicants To Advanced Technology Vehicles

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

    Manufacturing Loan Program | Department of Energy Updated Guidance For Applicants To Advanced Technology Vehicles Manufacturing Loan Program Updated Guidance For Applicants To Advanced Technology Vehicles Manufacturing Loan Program Updated Guidance For Applicants To Advanced Technology Vehicles Manufacturing Loan Program (150.99 KB) More Documents & Publications ATVM Guidance for Applicants 11.4.14 Advanced Technology Vehicles Manufacturing Loan Program ATVM Loan Program Interim Final

  5. LM Records and Information Management Transition Guidance (May 2016) |

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

    Department of Energy Records and Information Management Transition Guidance (May 2016) LM Records and Information Management Transition Guidance (May 2016) This guidance document establishes a framework for developing a Records and Information Management Transition Plan as part of the overall transition effort for a legacy site. LM Records and Information Management Transition Guidance (May 2016) (1.47 MB) More Documents & Publications Information and Records Management Transition

  6. WPN 00-1- Program Year 2000 Weatherization Grant Guidance

    Broader source: Energy.gov [DOE]

    To issue grant guidance and management information for the low-income Weatherization Assistance Program for Program Year 2000.

  7. Department of Energy Issues Federal Fleet Management Guidance | Department

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

    of Energy Federal Fleet Management Guidance Department of Energy Issues Federal Fleet Management Guidance April 14, 2010 - 12:00am Addthis Washington, D.C. - The U.S. Department of Energy's (DOE) Federal Energy Management Program today released its Federal Fleet Management Guidance, meeting a requirement of President Obama's Executive Order (E.O. 13514) on Federal Leadership in Environmental, Energy and Economic Performance. This is the first comprehensive guidance to address the

  8. Asset Utilization Index (AUI) Guidance | Department of Energy

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

    Asset Utilization Index (AUI) Guidance Asset Utilization Index (AUI) Guidance AUI Guidance_090227.pdf (40.37 KB) More Documents & Publications Three Year Rolling Timeline The Department&#8217;s real property assets are vital to the accomplishment of its mission Three-year Rolling Timeline

  9. Privacy Impact Assessment (PIA) Template and Guidance | Department of

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

    Energy Privacy Impact Assessment (PIA) Template and Guidance Privacy Impact Assessment (PIA) Template and Guidance Privacy_Impact_Assessment_Template_May_2009_w_Guidance.docx (1.74 MB) More Documents & Publications Manchester Software 1099 Reporting PIA, Idaho National Laboratory Occupational Medicine - Assistant PIA, Idaho National Laboratory Integrated Safety Management Workshop Registration, PIA, Idaho National Laboratory

  10. Guidance of the Department of Energy Subcontracting Program | Department of

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

    Energy Guidance of the Department of Energy Subcontracting Program Guidance of the Department of Energy Subcontracting Program information about small businesses Guidance of the Department of Energy Subcontracting Program (134.55 KB) More Documents & Publications SubcontractingGuidelines.doc&#0; Acquisition Guide Chapter 19 Update Chapter 19 - Small Business Programs

  11. 2013 guidance fo real Property Inventory Reporting | Department of Energy

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

    guidance fo real Property Inventory Reporting 2013 guidance fo real Property Inventory Reporting SIGNED_FY13_Rpt_Instructions REV - 2013.08.15.pdf (586.39 KB) More Documents & Publications FY 2012 Federal Real Property Reporting Requirement FY09_Federal_Real_Property_Reporting_Requirements.pdf Guidance for Fiscal Year 2015 Facilities Information Management System Data Validations

  12. GUIDANCE ON CONDUCTING ADVERSE DIVERSITY ANALYSIS

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

    GUIDANCE ON CONDUCTING ADVERSE DIVERSITY ANALYSIS The Uniform Guidelines for Employee Selection Procedures adopted by the Equal Employment Opportunity Commission (EEOC), Department of Labor's Office of Federal Contract Compliance Programs (OFCCP), and U.S. Department of Justice in 1978 set out accepted statistical tests for assessing possible discriminatory impact of employment actions on protected classifications of employees. See 29 CFR Part 1607. Agencies and litigants commonly use

  13. Guidance for EPAct 2005 Section 242 Program

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

    Guidance for EPAct 2005 Section 242 Program I. Purpose In the Energy Policy Act of 2005 (EPAct 2005; Public Law 109-58) Congress established a new program to support the expansion of hydropower energy development at existing dams and impoundments through an incentive payment procedure. Under section 242 of EPAct 2005, the Secretary of Energy is directed to provide incentive payments to the owner or authorized operator of qualified hydroelectric facilities for electric energy generated and sold

  14. Guidance for evaluation of operational emergency plans

    SciTech Connect (OSTI)

    1995-03-01

    The purpose of this document is to provide guidance for development of emergency plans for the USDOE Office of Defense Programs, Office of Energy Research, and Office of Environmental Management facilities. It gathers emergency planning policy and guidance from applicable federal regulations, DOE Orders and related guidance documents. This material, along with recommended good practices, is presented as a checklist against which emergency plans can be reviewed by DOE Headquarters. The Office of Emergency Response (DP-23), Office of Environment, Safety and Health Technical Support (ER-8), and Office of Transportation, Emergency Management and Analytical Services (EM-26) will use this checklist to evaluate plans submitted by DP, ER, and EM field elements. The scope of this document encompasses plans for operational emergencies at DOE facilities, both nuclear and non-nuclear. Operational emergencies, as defined in Attachment 2 to DOE Order 5500.1B (April 30, 1991) are ``significant accidents, incidents, events, or natural phenomena which seriously degrade the safety or security of DOE facilities. Operational Emergencies apply to DOE reactors and other DOE facilities (nuclear and non-nuclear) involved with hazardous materials; DOE-controlled nuclear weapons, components, or test devices; DOE safeguards and security events; and transportation accidents involving hazardous materials under DOE control.``

  15. Proposed Rules

    National Nuclear Security Administration (NNSA)

    4414 Federal Register / Vol. 78, No. 209 / Tuesday, October 29, 2013 / Proposed Rules NRC about the availability of information for the proposed Waste Confidence rule and DGEIS. You may access publicly available information related to these documents by any of the following methods: * Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0246. * NRC's Waste Confidence Web site: Go to http://www.nrc.gov/waste/spent- fuel-storage/wcd.html. * NRC's

  16. State Energy Program Fiscal Year 2006 Formula Grant Guidance | Department

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

    of Energy Fiscal Year 2006 Formula Grant Guidance State Energy Program Fiscal Year 2006 Formula Grant Guidance State Energy Program (SEP) Program Notice 06-1 Fiscal Year 2006 Formula Grant Guidance fy06_grant_guidance.pdf (256.49 KB) More Documents & Publications WPN 06-8: Dun and Bradstreet Universal Numbering System (DUNS) and Central Contractor Registration (CCR) and Grants.Gov Reminder Audit Report: OAS-RA-10-05 State Energy Program Formula Grant Guidance Program Year 2007

  17. FY 2014-2024 Ten Year Site Plan Preparation Guidance | Department of Energy

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

    -2024 Ten Year Site Plan Preparation Guidance FY 2014-2024 Ten Year Site Plan Preparation Guidance 2014.03.13 FY14 TYSP Guidance.pdf (240.24 KB) More Documents & Publications DOE Indian Energy Purchase Preference Policy Guidance State Energy Program Notice 14-2, Implementation Model Guidance 2010.01.15_FY10_TYSP_Guidance_memo.pdf

  18. Site-Specific Analyses for Demonstrating Compliance with 10 CFR 61 Performance Objectives - 12179

    SciTech Connect (OSTI)

    Grossman, C.J.; Esh, D.W.; Yadav, P.; Carrera, A.G.

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations at 10 CFR Part 61 to require low-level radioactive waste disposal facilities to conduct site-specific analyses to demonstrate compliance with the performance objectives in Subpart C. The amendments would require licensees to conduct site-specific analyses for protection of the public and inadvertent intruders as well as analyses for long-lived waste. The amendments would ensure protection of public health and safety, while providing flexibility to demonstrate compliance with the performance objectives, for current and potential future waste streams. NRC staff intends to submit proposed rule language and associated regulatory basis to the Commission for its approval in early 2012. The NRC staff also intends to develop associated guidance to accompany any proposed amendments. The guidance is intended to supplement existing low-level radioactive waste guidance on issues pertinent to conducting site-specific analyses to demonstrate compliance with the performance objectives. The guidance will facilitate implementation of the proposed amendments by licensees and assist competent regulatory authorities in reviewing the site-specific analyses. Specifically, the guidance provides staff recommendations on general considerations for the site-specific analyses, modeling issues for assessments to demonstrate compliance with the performance objectives including the performance assessment, intruder assessment, stability assessment, and analyses for long-lived waste. This paper describes the technical basis for changes to the rule language and the proposed guidance associated with implementation of the rule language. The NRC staff, per Commission direction, intends to propose amendments to 10 CFR Part 61 to require licensees to conduct site-specific analyses to demonstrate compliance with performance objectives for the protection of public health and the environment. The amendments would require a

  19. Notice of 2009 Guidance on Energy Efficiency Enforcement Regulations |

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

    Department of Energy 2009 Guidance on Energy Efficiency Enforcement Regulations Notice of 2009 Guidance on Energy Efficiency Enforcement Regulations Notice - DOE Guidance on Energy Efficiency Enforcement Regulations, Federal Register Vol. 74, No. 197 October 14, 2009. This notice sets forth the Department of Energy's (DOE's) interpretation of its energy efficiency enforcement regulations. These regulations provide for manufacturer submission of compliance statements and certification reports

  20. Energy.gov Content Management System Requirements and Guidance | Department

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

    of Energy Energy.gov Content Management System Requirements and Guidance Energy.gov Content Management System Requirements and Guidance The Office of Energy Efficiency and Renewable Energy's (EERE's) websites are hosted in Energy.gov's Drupal content management system (CMS), which is maintained by the U.S. Department of Energy's Public Affairs Office. Learn more about Energy.gov's Drupal CMS requirements and guidance for: Page types Block types Linking File naming conventions Optimizing