National Library of Energy BETA

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. 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.

  3. NRC Recommendations

    Broader source: Energy.gov [DOE]

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

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

    SciTech Connect (OSTI)

    Whitworth, Julia [Los Alamos National Laboratory; Stewart, Bill [Los Alamos National Laboratory; Cuthbertson, Abigail [DOE

    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. 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.

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

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

    NRC Mission Safety Culture NRC Oversight NRC Inspection Program Technical Qualification Continuous Learning NRC Leadership Expectations and Practices for Sustaining a High...

  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. NRC Construction Light Source Flicker: What We

    E-Print Network [OSTI]

    California at Davis, University of

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

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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).

  14. AVAILABILITY OF REFERENCE MATERIALS NRC Reference Material

    E-Print Network [OSTI]

    Services Section U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 E-mail: DISTRIBUTION, Division of Administrative Services, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001. ised; licensee event reports; and Commission papers and their attachments. NRC publications in the NUREG series

  15. 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 systems approved for use in the nuclear power industry by the NRC. (3) Identify and discuss key design issues, features, benefits, and limitations of these NRC approved digital control systems that can be applied as design guidance and correlated to the Monitored Geologic Repository (MGR) design requirements. (4) Identify codes and standards used in the design of these NRC approved digital control systems and discuss their possible applicability to the design of a subsurface nuclear waste repository. (5) Evaluate the NRC approved digital control system's safety, reliability and maintainability features and issues. Apply these to MGR design methodologies and requirements. (6) Provide recommendations for use in developing design criteria in the System Description Documents for the digital control systems of the subsurface nuclear waste repository at Yucca Mountain. (7) Develop recommendations for applying NRC approval methods for digital control systems for the subsurface nuclear waste repository at Yucca Mountain. This analysis will focus on the development of the issues, criteria and methods used and required for identifying the appropriate requirements for digital based control systems. Attention will be placed on development of recommended design criteria for digital controls including interpretation of codes, standards and regulations. Attention will also focus on the use of digital controls and COTS (Commercial Off-the-shelf) technology and equipment in selected NRC approved digital control systems, and as referenced in applicable codes, standards and regulations. The analysis will address design issues related to COTS technology and how they were dealt with in previous NRC approved digital control systems.

  16. 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)...

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

    Office of Environmental Management (EM)

    for DOE and NRC to exchange information related to safety issues associated with non-reactor nuclear facilities. The NRC-DOE Inter-Agency nuclear safety information sharing...

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

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

    DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON,...

  19. 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.

  20. 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...

  1. NRC Solomons RFQ | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History ViewMayo, Maryland:NPI Ventures Ltd Jump to: navigation, search Name: NPIProgram JumpNRC

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

    National Nuclear Security Administration (NNSA)

    or prepared for" concept in the regulations 6 Appendix A to Part 110-Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note: A nuclear reactor...

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

    Office of Environmental Management (EM)

    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...

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

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

    (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...

  5. 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)''.

  6. NRC policy on future reactor designs

    SciTech Connect (OSTI)

    none,

    1985-07-01

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

  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. 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 NRC's role will change from doing both consultation and monitoring to being focused on monitoring activities within NDAA. DOE has identified other activities at the Hanford Nuclear Reservation that would continue consultation activities but outside of the NDAA in the future. During the past seven years of consultations and monitoring a number of lessons learned about the process, communication issues, and technical guidance have been identified. With the change in focus from reviewing initial performance assessments and draft waste determinations to long-term monitoring (e.g., individual waste tank closure, at F Tank Farm or complete tank farm closure at INTEC expected in the near future), the NRC is going to revise and update its guidance over the next few years to reflect the lessons learned and the change in focus. In addition to the lessons learned, improvements in the guidance will have to account possible rule and guidance changes underway within Part 61. This paper will discuss the initial plans, approaches, and time lines to revise the guidance within NUREG-1854, including opportunities for public involvement. (authors)

  9. 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 Environmental Report is being evaluated at the Savannah River Site as a case study for application across the DOE Complex. This paper will present areas of direct correlation as well as those where the need for site specific data for either DOE operations or NRC compliance warrant additional interaction between the agencies. Areas where further refinement of the SMR technologies may drive collaborative development of revised regulations through such means as industry consensus standards will also be highlighted. Both NRC and DOE have requirements that mandate public involvement in their processes. The importance and value of early engagement with the public as well as collaborating regulatory agencies is of critical importance when deploying new technologies. (authors)

  10. 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.

  11. 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 a fire HRA. This process includes identification and definition of post-fire human failure events, qualitative analysis, quantification, recovery, dependency, and uncertainty. This document provides three approaches to quantification: screening, scoping, and detailed HRA. Screening is based on the guidance in NUREG/CR-6850, with some additional guidance for scenarios with long time windows. Scoping is a new approach to quantification developed specifically to support the iterative nature of fire PRA quantification. Scoping is intended to provide less conservative HEPs than screening, but requires fewer resources than a detailed HRA analysis. For detailed HRA quantification, guidance has been developed on how to apply existing methods to assess post-fire fire HEPs.

  12. Introduction To GIS Course Syllabus Introduction to GIS NRC585

    E-Print Network [OSTI]

    Bradley, Bethany

    - 1 ­ Introduction To GIS Course Syllabus Introduction to GIS ­ NRC585 Lecture: Thurs. 1:00 - 2: by appointment Email: bbradley@eco.umass.edu Email: tcross@eco.umass.edu Website: http://people.umass.edu/bethanyb/gis.html Course Objective: To provide an understanding of the basic concepts and uses of GIS technology

  13. 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 enhance core and spent fuel pool cooling, reactor coolant system integrity, and containment integrity. (authors)

  14. 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...

  15. 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.

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

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

  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 that NRC should consider that address the site-specific matter that triggered consultation. Over the course of consultations on the eight sites, there have been some reoccurring themes to EPA's views. Primarily, these are EPA: 1. Recommending that NRC consider selecting institutional controls to ensure that NRC's assumptions about future human exposure at the site are not exceeded. 2. Recommending that NRC consider using more site-specific information when conducting dose assessment modeling. 3. Recommending that NRC consider a flexible approach to groundwater protection that still ensures the public is not exposed to contamination levels over drinking water limits. 4. Recommending that NRC consider an approach similar to how EPA implements supplemental standards under 40 CFR 192 as an ARAR when the UMTRCA soil standard of 5 pCi/g is not being met.

  18. NAS/NRC Report:NAS/NRC Report: Health Risks from Dioxin and RelatedHealth Risks from Dioxin and Related

    E-Print Network [OSTI]

    Doty, Sharon Lafferty

    NAS/NRC Report:NAS/NRC Report: Health Risks from Dioxin and RelatedHealth Risks from Dioxin Provost for Research University of WashingtonUniversity of Washington #12;Dioxins, Dibenzofurans and PCBs · Chlorinated Dioxins represent a class of compounds, of which 7 are included in EPA regulations (Contaminants

  19. 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.

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

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History ViewMayo, Maryland:NPI Ventures Ltd Jump to: navigation, search Name: NPIProgram JumpNRC Institute

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (JournalvivoHighHussein KhalilResearch88 Sign In About | Workshop for- NRC

  2. 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).

  3. 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)

  4. 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.

  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. 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.

  7. Can. J. Zool. 76: 10631079 (1998) 1998 NRC Canada The turning-and linear-maneuvering

    E-Print Network [OSTI]

    Warrick, Douglas R.

    1998-01-01

    Can. J. Zool. 76: 1063­1079 (1998) © 1998 NRC Canada 1063 The turning- and linear; Norberg and Rayner 1987). But because most bird flight is flapping flight (thus violating the assumption

  8. 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 -...

  9. 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 Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

  10. 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).

  11. 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.

  12. 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.

  13. 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.

  14. 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.

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

    E-Print Network [OSTI]

    Christian, Eric

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

  16. Types of Cost in Inductive Concept Learning Peter Turney PETER.TURNEY@NRC.CA

    E-Print Network [OSTI]

    Weiss, Gary

    Types of Cost in Inductive Concept Learning Peter Turney PETER.TURNEY@NRC.CA Institute of classes. In real-world applications of concept learning, there are many different types of cost involved. The majority of the machine learning literature ignores all types of cost (unless accuracy is interpreted

  17. 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 related to training, developing, and transferring knowledge to NRC staff on how to review dose-modeling portions of licensee-submitted DPs and LTPs. This project identified specific cases and examples, created easily updateable educational modules, represented material in an engaging format through animations, video, and graphics, and distributed information on how to perform these reviews in an accessible, web-based format. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT will provide reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling will promote staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities. One of the key advantages of this type of web-based training is that it can be loaded on-demand and can be reused indefinitely. In addition to the benefits of on-demand training, the modules can also be used for reference. The presentations are hosted on a web server that can be accessed by registered users at any time. Staff can return to a particular module to review the material long after they have completed the course.

  18. DOE/NRC Forms | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1 PAGE 1 OF2Guidance to [SubmitO3Template

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

    E-Print Network [OSTI]

    Standards (ISCORS), the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental Protection

  20. 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.

  1. 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.

  2. 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.

  3. 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.

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

    SciTech Connect (OSTI)

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

    1980-05-01

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

  5. Initial demonstration of the NRC`s capability to conduct a performance assessment for a High-Level Waste Repository

    SciTech Connect (OSTI)

    Codell, R.; Eisenberg, N.; Fehringer, D.; Ford, W.; Margulies, T.; McCartin, T.; Park, J.; Randall, J.

    1992-05-01

    In order to better review licensing submittals for a High-Level Waste Repository, the US Nuclear Regulatory Commission staff has expanded and improved its capability to conduct performance assessments. This report documents an initial demonstration of this capability. The demonstration made use of the limited data from Yucca Mountain, Nevada to investigate a small set of scenario classes. Models of release and transport of radionuclides from a repository via the groundwater and direct release pathways provided preliminary estimates of releases to the accessible environment for a 10,000 year simulation time. Latin hypercube sampling of input parameters was used to express results as distributions and to investigate model sensitivities. This methodology demonstration should not be interpreted as an estimate of performance of the proposed repository at Yucca Mountain, Nevada. By expanding and developing the NRC staff capability to conduct such analyses, NRC would be better able to conduct an independent technical review of the US Department of Energy (DOE) licensing submittals for a high-level waste (HLW) repository. These activities were divided initially into Phase 1 and Phase 2 activities. Additional phases may follow as part of a program of iterative performance assessment at the NRC. The NRC staff conducted Phase 1 activities primarily in CY 1989 with minimal participation from NRC contractors. The Phase 2 activities were to involve NRC contractors actively and to provide for the transfer of technology. The Phase 2 activities are scheduled to start in CY 1990, to allow Sandia National Laboratories to complete development and transfer of computer codes and the Center for Nuclear Waste Regulatory Analyses (CNWRA) to be in a position to assist in the acquisition of the codes.

  6. 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)

  7. 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.

  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. 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.

  10. 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 [U.S. NRC, Rockville, MD (United States)] [U.S. NRC, Rockville, MD (United States); Pabalan, Roberto; Pickett, David [Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX (United States)] [Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX (United States); Dinwiddie, Cynthia [Southwest Research Institute, San Antonio, TX (United States)] [Southwest Research Institute, San Antonio, TX (United States)

    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)

  11. 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.

  12. 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 [Nuclear Regulatory Commission (United States)

    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)

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

    SciTech Connect (OSTI)

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

    1991-02-01

    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)

  14. 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 final status surveys are addressed in the WBT. Realistic case examples are presented and analyzed including the abstraction of a realistic site into a conceptual model and computer model. A case history is also used to demonstrate development of NRC review documents such as requests for additional information (RAIs). To enhance the web-based training experience, audio, animations, linked documents, quizzes, and scripts are being integrated with a commercial web-based training package that supports simple navigation. The course is also being integrated into both existing and state-of-the-art learning management systems. A testing group is being utilized to identify and help resolve training issues prior to deployment of the course. When completed, the course can be accessed for credited training with required modules dependent on the job category of the training participant. The modules will also be accessible to NRC staff for review or refresher following initial course completion. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT will provide reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling will promote staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities. (authors)

  15. 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 final status surveys are addressed in the WBT. Realistic case examples are presented and analyzed including the abstraction of a realistic site into a conceptual model and computer model. A case history is also used to demonstrate development of NRC review documents such as requests for additional information (RAIs). To enhance the web-based training experience, audio, animations, linked documents, quizzes, and scripts are being integrated with a commercial web-based training package that supports simple navigation. The course is also being integrated into both existing and state-of-the-art learning management systems. A testing group is being utilized to identify and help resolve training issues prior to deployment of the course. When completed, the course can be accessed for credited training with required modules dependent on the job category of the training participant. The modules will also be accessible to NRC staff for review or refresher following initial course completion. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT provides reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling promotes staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities.

  16. 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 [Nuclear Regulatory Commission (United States)

    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 consistently apply the lessons learned and continue to create an open and collaborative work environment to maintain the process of continuous improvement. (authors)

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

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700, 1. .&. ' , c 1 1; -.ll 1q 3 THE/NRC HAS

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3 Recognitions Brian Horn, NRC Pete

  19. 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 to date indicate that the deliquescence RH for sea salt is close to that of MgCl{sub 2} pure salt. SCC is observed between 35 and 80 deg. C when the ambient (RH) is close to or higher than this level, even for a low surface salt concentration. (authors)

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

    SciTech Connect (OSTI)

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

    2012-07-01

    '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. That was due in large measure to the fact that the NRC has a well-tested system of responding to nuclear emergencies, and we followed our plan. (authors)

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) August 2012 Guidance for High Temperature news October

  2. 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.

  3. NRC Form 741

    National Nuclear Security Administration (NNSA)

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  4. 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.

  5. 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.

  6. 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.

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3Overview of DOE and NRC Reporting to

  8. 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)

  9. 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.

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

    SciTech Connect (OSTI)

    Collins, M.; Shelton, B.

    1994-07-01

    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.

  11. 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.

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

    SciTech Connect (OSTI)

    Not Available

    1994-08-01

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

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

    SciTech Connect (OSTI)

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

    1997-05-01

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

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

    SciTech Connect (OSTI)

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

    1994-08-01

    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).

  15. 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 regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

  16. 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 conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

  17. ARM - Campaign Instrument - nrc-convair580

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.TheoryTuesday,airgovInstrumentsnfov Comments? We would love to

  18. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No.Administration1

  19. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No.Administration12

  20. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76,

  1. Physical Inventory Listing NRC 742cu

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76,EXAMPLE 4 *** Company Name

  2. Sample Form DOE NRC 740M

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal RegisterStorm Water Pollution

  3. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71- Particulate: ColumnsLake4/%2AMain1 |2

  4. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71- Particulate: ColumnsLake4/%2AMain1 |2.a

  5. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71- Particulate: ColumnsLake4/%2AMain1

  6. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71- Particulate: ColumnsLake4/%2AMain1 ***

  7. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71- Particulate: ColumnsLake4/%2AMain1 ***.A

  8. Material Balance Report NRC 742u

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71- Particulate: ColumnsLake4/%2AMain1

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

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About1996HowFOAShowingFuelWeatherizeeEnergyMonumentWest From:FORM 741 (5-2002)

  10. 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).

  11. Guidance Systems Division ,

    Office of Legacy Management (LM)

    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...

  12. 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.

  13. Radiocolloids in leachate from the NRC field lysimeter investigations

    SciTech Connect (OSTI)

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

    1998-12-31

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

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

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About Us Shirley AnnResourcesEnergyEnergy Update onUranium Leasing

  15. 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.

  16. NRC BP (Mauel) 1 Why the Restructured Program

    E-Print Network [OSTI]

    concepts and fusion technologies Optimization of the Fusion System ß Pursue fusion energy and fusion to reach Our Goal of Economically and Environmentally Attractive Fusion Energy Source Our "science focus leading to the 1995 Restructured Fusion Energy Science Program o Parallels (and differences!) exist

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

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

    for sustaining growth in computing performance. Yelick, who is a recognized leader in programming languages, was a member of the panel discussing "Parallelism and Innovative...

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

    E-Print Network [OSTI]

    " DECADES, U. S. UTILITIES ARE DEPENDING ON ! NATURAL GAS TURBINES ! COAL ! MODEST ADDITIONS OF RENEWABLES of this type" ! "Compact Concepts" ! ". . . have higher power density in the plasma core, which may lead configurations, easing maintenance ... tend to be smaller and/or lower field strength. ! "Within this type

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

    National Nuclear Security Administration (NNSA)

    Agreement AwardsRecognitions Update on Blue Ribbon Commission Report (Tentative) Cyber security Issues and Implications GAO report on Tracking Overseas Material Ownership...

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

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

    Center (INTEC) in Idaho; and management of the Idaho Spent Fuel Facility (ISFF) license. This is a hybrid type contract with Firm-Fixed-Price (FFP), Indefinite Delivery...

  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)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10B 1

  3. Nuclear Material Transaction Report NRC 741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10B

  4. Nuclear Material Transaction Report NRC741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  5. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  6. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  7. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  8. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  9. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  10. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09 |10BC

  11. Nuclear Material Transaction Report nrc741_1

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76, No. 2 / Tuesday,09

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. Geographic TermsOVERVIEWO594-ADD1Visit

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia NationalSecurityNuclearH-canyon |I6 Page 2Public6

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department ofRefrigeratorsDepartmentEP9425 701Energy DOE

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 20153 METHODSDOE/Labor Leadership RoundtableViolations0M

  16. DOE/NRC F 742 | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 20153 METHODSDOE/Labor Leadership RoundtableViolations0M

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 20153 METHODSDOE/Labor Leadership RoundtableViolations0MC

  18. SQA CGD NRC Vendor Workshop | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterestedReplacement-2-AA-1 SECTION J APPENDIXAllegations Related to theDoeSPRU

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

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties -Department of EnergyNEW1for AcquisitionNORTHEASTofOrganization |

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

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties -Department of EnergyNEW1for AcquisitionNORTHEASTofOrganization

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

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties -DepartmentAvailable forSite |n t eof Energy Program1183-20XXof

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverseIMPACT EVALUATIONIntroducing theActivationDept ofNERSCJenniferStandards and

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-in electric vehicle10 DOE ASSESSMENTathasBestI) AprilSupport Services

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

    Office of Environmental Management (EM)

    christopher.grossman@nrc.gov 301-415-0140 Interagency Performance and Risk Assessment Community of Practice May 20, 2015 Objective * Discuss the proposed revisions to the...

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    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 conducted. 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.

  11. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    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 conducted. 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.

  12. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    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 conducted.

  13. CH Packaging Program Guidance

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    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 conducted.

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

    SciTech Connect (OSTI)

    Not Available

    1981-07-01

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

  15. Guidance for Planning Exercises

    Office of Environmental Management (EM)

    blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools Guidance f Guidance f Guidance f Guidance f Guidance for Planning,...

  16. Food Landscapes Community Partners: The Neighborhood Resource Center (NRC); Transition Day Support Services

    E-Print Network [OSTI]

    Hammack, Richard

    of Internal Medicine; School of Allied Health Professions, Department of Health Administration; VCU Health, School of Allied Health Professions VCU Partners: School of Allied Health Professions, Department

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

    National Nuclear Security Administration (NNSA)

    2012 Kilograms Figure 1: Exports of U.S. HEU 1957 - 2012 used as fuel or targets in a nuclear research or test reactor HEU Exports HEU exports began in the 1957 time frame...

  18. 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)

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

    National Nuclear Security Administration (NNSA)

    30 days of submission 2 Inventory Reporting and Reconciliation-Licensees During 2013, - 309 RIS's Report Inventory to NMMSS - 283 RIS's reconcile their inventory with NMMSS...

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

    SciTech Connect (OSTI)

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

    1990-12-01

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

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

    National Nuclear Security Administration (NNSA)

    NMMSS operations - Ease of data collection (SAMS, Fillable Forms) - Efficiency of data processing (edit checks) - Flexibility of report productiondistribution...

  2. 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.

  3. 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)

  4. 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.

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

    National Nuclear Security Administration (NNSA)

    in U-235 2 Information in report * "Current" disposition of U.S. exports of HEU used as fuel or targets in research or test reactors and including: - Location of HEU - Whether HEU...

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

    National Nuclear Security Administration (NNSA)

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

  7. 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.

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

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About1996How to Applythe Public UtilitynDE-FOA-0000051.rtfMiddleReapsINDIANMinutes

  9. Operating Experience Level 3, NRC Notice: Antifreeze Agents in Fire Water

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergy Managing853926 NewsORMATDepartment of Energy|DepartmentDepartment

  10. Microsoft PowerPoint - 5_Pat Smith_NMMSS_2013_Presentation_NRC Reconciliation.pptx

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3Overview of DOE andSourceReconciliation

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA.MOX Adventure Tamara Reavis May 2015 Welcome

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 FederalRivers and StreamsyouREMS DataNews,ForA A20--

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 FederalRivers and StreamsyouREMS DataNews,ForA

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i pState Efficiency,Energy Newssuccessfully| Department of| Department

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

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties - WAPAEnergy May2.docTechnicalBARACK07 Annual Plan09 U . S .

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

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About1996HowFOAShowingFuelWeatherizeeEnergyMonumentWest From:

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-in electricLaboratory | version of the Frequently AskedResearchDepartment of

  18. Technical Guidance

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  19. 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.

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

    Office of Environmental Management (EM)

    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...

  1. 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 requires updating to comply with the newer DOT regulations. Similar challenges present themselves throughout the nuclear industry in both commercial and government operations and therefore, this is not only a Hanford Site problem. Shipping radioactive wastes as either LSA or SCO rather than repacking it is significantly cheaper than other DOT radioactive materials shipping classifications particularly when the cost of packages is included. Additionally, the need to 'repackage' materials for transport can often increase worker exposure, necessitated by 'repackaging' waste materials into DOT 7 A Type A containers.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 14824 Federal Register / Vol. 74, No. 61 / Wednesday, April 1, 2009 / Notices accordance with the NRC E-filing rule,

    E-Print Network [OSTI]

    .S. Nuclear Regulatory Commission, Washington, DC 20555­0001. Paul B. Abramson, U.S. Nuclear Regulatory Commission, Washington, DC 20555­0001. Bruce R. Matthews, U.S. Nuclear Regulatory Commission, Washington, DC and Licensing Board Panel. [FR Doc. E9­7284 Filed 3­31­09; 8:45 am] BILLING CODE 7590­01­P NUCLEAR REGULATORY

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

    SciTech Connect (OSTI)

    Vora, J.P.

    1993-12-01

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

  9. 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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo.Hydrogen4Energy Smooth Brome Monitoring

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3 Recognitions Brian Presented by:Staff

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3 Recognitions Brian Presented

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3Overview of DOE and NRCInspection

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3Overview of

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3Overview ofAgreementsMartynUseGlobaland

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA.MOX Adventure Tamara Reavis May 2015

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJessework uses concrete and realistic microscopic calculations Mr., 20149760127

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

    SciTech Connect (OSTI)

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

    1997-04-01

    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.

  18. Topical report review status. Volume 9, No. 1

    SciTech Connect (OSTI)

    NONE

    1995-02-01

    This report provides industry with procedures for submitting topical reports, guidance on how the US Nuclear Regulatory Commission (NRC) processes and responds to topical report submittals, and an accounting, with review schedules, of all topical reports currently accepted for review by the NRC. This report is published semiannually.

  19. Topical report review status. Volume 8, No. 1

    SciTech Connect (OSTI)

    Not Available

    1994-05-01

    This report provides industry with procedures for submitting topical reports, guidance on how the US Nuclear Regulatory Commission (NRC) will process and respond to topical report submissions, and an accounting of all topical reports currently being reviewed by the NRC staff. This report will be published semiannually.

  20. Topical report review status: Volume 10

    SciTech Connect (OSTI)

    NONE

    1996-03-01

    This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) processes and responds to topical report submittals, and an accounting, with review schedules, of all topical reports currently accepted for review by the NRC. This report is published annually.

  1. Radiation Safety Reference Material Policy: 7.01 Created: 08/29/2014 Version: 1.0 Revised

    E-Print Network [OSTI]

    Jia, Songtao

    ­ National Council on Radiation Protection and Measurements NRC ­ United States Nuclear Regulatory Commission NUREG ­ Regulatory guides published by NRC NYC ­ New York City NYS ­ New York State RARAF Safety program. After the list of regulatory codes there are some guidance documents listed for use

  2. Water Efficiency Goal Guidance

    Broader source: Energy.gov [DOE]

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

  3. LCC Guidance Rates

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  4. 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...

  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. Conservation of Information: Reverse engineering dark social systems

    E-Print Network [OSTI]

    2010-01-01

    NRC (Nuclear Regulatory Commission; at www.nrc.gov). SDT (gave the Nuclear Regulatory Commission the authority to

  7. A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles

    E-Print Network [OSTI]

    Djokic, Denia

    2013-01-01

    NRC  2008   Nuclear   Regulatory   Commission,   “Response  neptunium   Nuclear  Regulatory  Commission   Neptunium  (bodies,   the   Nuclear   Regulatory   Commission   (NRC)  

  8. PWR FLECHT SEASET 163-Rod Bundle Flow Blockage Task data report. NRC/EPRI/Westinghouse report No. 13, August-October 1982

    SciTech Connect (OSTI)

    Loftus, M J; Hochreiter, L E; McGuire, M F; Valkovic, M M

    1983-10-01

    This report presents data from the 163-Rod Bundle Blow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Systems Effects and Separate Effects Test Program (FLECHT SEASET). The task 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. These tests were designed to determine effects of flow blockage and flow bypass on reflooding behavior and to aid in the assessment of computational models in predicting the reflooding behavior of flow blockage in rod bundle arrays.

  9. 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.

  10. Can. J. Earth Sci. 43: 433446 (2006) doi:10.1139/E06-002 2006 NRC Canada Structural variation along the Devil's Mountain

    E-Print Network [OSTI]

    Nedimoviæ, Mladen R.

    2006-01-01

    - mation has focussed on the Devil's Mountain, Utsalady Point, and Strawberry Point faults to the east'Utsalady Point et de Strawberry Point à l'est de ~122,8º mais n'a pas touché la faille d'Utsalady Point à l

  11. Can. J. Earth Sci. 43: 533546 (2006) doi:10.1139/E06-003 2006 NRC Canada Coupled landscapelake evolution in High Arctic

    E-Print Network [OSTI]

    Vincent, Warwick F.

    2006-01-01

    of the ecosystems showed strong patterns of thermal, chemical, and biological stratification with subsurface (évolution du paysage). Tous les écosystèmes montraient de forts patrons de stratification thermique

  12. 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.

  13. 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.

  14. 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.

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

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. -71-3Overview ofAgreementsMartynUse of NMMSS

  16. Guidance Document Cryogenic Liquids

    E-Print Network [OSTI]

    . Liquid hydrogen, liquid methane or liquefied natural gas could form an extremely flammable mixtureGuidance Document Cryogenic Liquids [This is a brief and general summary. Read the full MSDS for more details before handling.] Introduction: All cryogenic liquids are gases at normal temperature

  17. Engineering Library Guidance

    E-Print Network [OSTI]

    Kaji, Hajime

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

  18. 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...

  19. 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.

  20. Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuelsof Energy ServicesContracting Oversight Committee onDepartment ofGuidance

  1. GUIDANCE ON IMPLEMENTING RADIONUCLIDE NESHAPS

    E-Print Network [OSTI]

    GUIDANCE ON IMPLEMENTING the RADIONUCLIDE NESHAPS U.S. Environmental Protection Agency Office . . . . . . . . . . . . . . . 2 1.3 Format of this Guidance Document . . . . . . . . . . . . . 3 2. Summaries of the NESHAPS - Radionuclide Emissions Other than Radon from DOE Facilities . . . . . . . . . . . . . . . . 13 2.2.2 Subpart I

  2. Topical report review status

    SciTech Connect (OSTI)

    NONE

    1997-08-01

    This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) processes and responds to topical report submittals, and an accounting, with review schedules, of all topical reports currently accepted for review schedules, of all topical reports currently accepted for review by the NRC. This report will be published annually. Each sponsoring organization with one or more topical reports accepted for review copies.

  3. Technical and Regulatory Guidance Technical and Regulatory Guidance for Design, Installation,

    E-Print Network [OSTI]

    Zornberg, Jorge G.

    Technical and Regulatory Guidance Technical and Regulatory Guidance for Design, Installation in the document. The technical implications of any information or guidance contained in this document may vary, ITRC recommends also consulting applicable standards, laws, regulations, suppliers of materials

  4. Technical Standards, Guidance on MELCOR computer code - May 3...

    Office of Environmental Management (EM)

    Standards, Guidance on MELCOR computer code - May 3, 2004 Technical Standards, Guidance on MELCOR computer code - May 3, 2004 May 3, 2004 MELCOR Computer Code Application Guidance...

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  7. Lead-Safe Housing Policy Guidance

    E-Print Network [OSTI]

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

  8. DOE NEPA Guidance and Requirements- Search Index

    Broader source: Energy.gov [DOE]

    The DOE 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.

  9. OFFSHORE WIND FARMS Guidance note for Environmental

    E-Print Network [OSTI]

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

  10. EPA -- Amended Environmental Impact Statement Filing System Guidance...

    Office of Environmental Management (EM)

    Amended Environmental Impact Statement Filing System Guidance EPA -- Amended Environmental Impact Statement Filing System Guidance Amended Environmental Impact Statement Filing...

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

    Energy Savers [EERE]

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

  12. Rulemaking Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool FitsProject DevelopsforReportingResourcesDepartmentDepartmentRulemaking Guidance

  13. SEAB Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsofProgram: Report AppendicesA Token RequestingRoundtablesRussianGuidance SEAB

  14. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    United States Nuclear Regulatory Commission (2012). NRC:United States Nuclear Regulatory Commission (2013). NRC: Newreasons that the Nuclear Regulatory Commission was founded

  15. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    2012). NRC: Nuclear Security and Safeguards.nrc.gov.in nuclear reactor maintenance and security. However, when aof nuclear power plants, as well as physical security to

  16. Controlled guidance of handwriting in Parkinson's Disease patients. Can a sonic aid improve tau guidance measures 

    E-Print Network [OSTI]

    Baxter, Holly

    2006-01-01

    Aim: To identify, using “tau theory” (Lee, 1998), i) if there are significant differences in tau guidance of handwriting between PD patients and normal healthy controls, and if so, ii) whether tau guidance for these ...

  17. Energy Intensity Baselining and Tracking Guidance

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

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

  18. 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...

  19. 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...

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

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

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

  1. Energy Sector Cybersecurity Framework Implementation Guidance...

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

    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...

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

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

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

  3. 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...

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

    Office of Environmental Management (EM)

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

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

    Open Energy Info (EERE)

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

  6. Guidance for Radiation Accident Management

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journalvivo Low-Dose Lowï‚— WeUpdate Jon PeschongGuidance andProcedure

  7. Technical Standards, Guidance on MACCS2 Computer Code - June...

    Office of Environmental Management (EM)

    Guidance on MACCS2 Computer Code - June 30, 2004 Technical Standards, Guidance on MACCS2 Computer Code - June 30, 2004 June 30, 2004 MACCS2 Computer Code Application Guidance for...

  8. A robust guidance system for aircraft approach and landing 

    E-Print Network [OSTI]

    Yu, Ren-Jye

    1999-01-01

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

  9. 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.

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

    Energy Savers [EERE]

    Energy Department Releases New Greenhouse Gas Reporting Guidance, Seeks Public Comment Energy Department Releases New Greenhouse Gas Reporting Guidance, Seeks Public Comment March...

  11. Guidance on the Required Period for Grantees to Obligate Funds...

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

    Efficiency and Conservation Block Grant Financing Program Guidance Grantee Letter Guidance for Energy Efficiency and Conservation Block Grant Program Recipients on Formula Grants...

  12. 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

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

    Energy Savers [EERE]

    GUIDANCE FOR ENERGY EFFICIENCY AND CONSERVATION BLOCK GRANT RECIPIENTS ON CLOSEOUT PROCEDURES FOR NON-STATE ENERGY OFFICE RECIPIENTS. GUIDANCE FOR ENERGY EFFICIENCY AND...

  14. 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...

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

    Office of Environmental Management (EM)

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

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

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

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

  17. Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive...

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

    Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program This document contains the Final...

  18. Enforcement Guidance Supplement 00-03: Specific Issues on Applicabilit...

    Office of Environmental Management (EM)

    00-03: Specific Issues on Applicability of 10 CFR 830 Enforcement Guidance Supplements Enforcement Guidance Supplement 99-03: Limitation of 10 CFR Part 830 to Equipment...

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

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Application Submittal Guidance for Stormwater Permits and Post-Authorization...

  20. 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...

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

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

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

  2. 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...

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

    Energy Savers [EERE]

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

  4. Technical Standards, CFAST-Code Guidance- July 23, 2004

    Broader source: Energy.gov [DOE]

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

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

    Energy Savers [EERE]

    - 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...

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

    Energy Savers [EERE]

    POLICY GUIDANCE MEMORANDUM 33 - Requirements for DOE Delegated Examining Procedures POLICY GUIDANCE MEMORANDUM 33 - Requirements for DOE Delegated Examining Procedures The...

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  9. POLICY GUIDANCE MEMORANDUM #23 Permanent and Nonpermanent Positions...

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  11. 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...

  12. 2012 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

    Workforce Analysis and Staffing Plan Report Memo, Guidance and Template 2012 Workforce Analysis and Staffing Plan Report Memo, Guidance and Template The Department of Energy...

  13. 2011 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

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

  14. 2013 Workforce Analysis and Staffing Plan Report Memo, Guidance...

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

    Draft 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...

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

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

    1 STATE ENERGY PROGRAM NOTICE 10-02 EFFECTIVE DATE: 122209 SUBJECT: RETOOLING AND MANUFACTURING PROGRAM GUIDANCE USING STATE ENERGY PROGRAM (SEP) FUNDS PURPOSE: Provides guidance...

  17. 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.

  18. Interaction of Polycrystalline CVD

    E-Print Network [OSTI]

    Adler, Joan

    , and for a personal caring manner. Thanks to Dr. Irina Gouzman - for her guidance at Soreq NRC, introduction to the world of vacuum science, and friendship throughout this study. Special thanks to Prof. Tim K. Minton for performing, and sharing the density functional theory direct dynamic calculations. Thanks to Ms. Roza

  19. 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.

  20. EPA 520/1-89-002 A GUIDE FOR DETERMINING COMPLIANCE WITH THE

    E-Print Network [OSTI]

    apply to certain facilities licensed by the Nuclear Regulatory Commission (NRC) or its Agreement States

  1. MARSAME Appendix B B. SOURCES OF BACKGROUND RADIOACTIVITY

    E-Print Network [OSTI]

    : · The Nuclear Regulatory Commission (NRC) provides information concerning background radioactivity in Background

  2. 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.

  3. 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.

  4. 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.

  5. Safety of magnetic fusion facilities: Guidance

    SciTech Connect (OSTI)

    NONE

    1996-05-01

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

  6. Energy.gov Article Guidance | Department of Energy

    Energy Savers [EERE]

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

  7. Final For-Profit Audit Guidance (FY 2011 and Following)

    Broader source: Energy.gov [DOE]

    NOTE THE ATTACHED IS THE MOST RECENT GUIDANCE AND APPLIES TO AUDITS FOR RECIPIENT’S FYS 2011, 2012, 2013, and 2014.  NEW GUIDANCE WILL BE ISSUED IN DECEMBER 2015 WHICH WILL APPLY TO AUDITS OF...

  8. 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.

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

    Energy Savers [EERE]

    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...

  10. Guidance for Environmental Background Analysis Volume III: Groundwater

    E-Print Network [OSTI]

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

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

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

    Guidance Memorandum 34B serves as an amendment to Policy Guidance Memorandum 34A regarding the use of the Direct Hire Authority for Contract Specialist positions. As stated in...

  12. POLICY GUIDANCE MEMORANDUM #20A Crediting Directly-Related Experience...

    Office of Environmental Management (EM)

    0A Crediting Directly-Related Experience for Annual Leave POLICY GUIDANCE MEMORANDUM 20A Crediting Directly-Related Experience for Annual Leave Guidance for the provision of the...

  13. 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 performance assessment to demonstrate protection of the general population from releases of radioactivity, an assessment to demonstrate protection of a potential inadvertent intruder, and a long-term analysis to assess how the design of the facility considers the potential radiological impacts associated with disposal of long-lived waste streams. Concurrently, the NRC staff intends to propose associated guidance to facilitate the implementation of the requirements to conduct site-specific analyses. In proposing these amendments to the regulation and associated guidance, the NRC staff has conducted extensive public outreach since 2009 including three public meetings and four briefings of the NRC's Advisory Committee on Reactor Safeguards. The NRC staff plans to submit the proposed amendments to the regulations to the Commission in early 2012. Subsequently, the proposed amendments and associated guidance would be published in the Federal Register for public comment pending approval of the proposed amendments to the regulations by the Commission. Following the public comment period, NRC staff plans to address public comments and revise, as necessary, the regulations and associated guidance before publishing a final rule, which is anticipated in 2013. (authors)

  14. 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.

  15. WPN 16-1: Program Year 2016 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) 2016.

  16. 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.

  17. WPN 13-1: Program Year 2013 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) 2013.

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

    Office of Environmental Management (EM)

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

  19. 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) 

  20. Enforcement Guidance Supplement 01-01: Nuclear Weapon Program...

    Office of Environmental Management (EM)

    This enforcement guidance focuses on the applicability of 10 CFR Part 830 to nuclear weapon programs and...

  1. SUMMARY GUIDANCE FOR BENCHMARK PERFORMANCE STANDARDS Performance

    E-Print Network [OSTI]

    SUMMARY GUIDANCE FOR BENCHMARK PERFORMANCE STANDARDS Performance Attributes 0-39% 40-59% 60-79% 80 technical knowledge/skill General technical understanding Superior technical knowledge in all tasks Exceptional technical knowledge; beyond expectations for position Quality Work did not meet minimum

  2. Use of a Machine Control & Guidance System Determination of Performance

    E-Print Network [OSTI]

    1 Use of a Machine Control & Guidance System Determination of Performance Protection against. Dr. P. Rausch Why Machine Guidance? 1 Introduction Machine Guidance allows higher performance. Higher someone checking down below: 09.07.2008 3 ,,Machine control by shout and gesture". Planned Excavator Job

  3. QA in Design Guidance | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget || DepartmentPutting Solar Panels toin Design Guidance

  4. Guidance & Opinions | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuelsof Energy ServicesContracting Oversight Committee on HomelandBusinessGuidance

  5. Policy and Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuelsof EnergyAprilEnergyPartnership forHydrogenandGuidance Policy and

  6. Policy, Guidance & Reports | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuelsof EnergyAprilEnergyPartnership forHydrogenandGuidance Policy andReports

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

    SciTech Connect (OSTI)

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

    2009-09-30

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

  8. Guidance for Federal Departments and Agencies on Establishing...

    Energy Savers [EERE]

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

  9. Final Guidance on Improving the Process for Preparing Efficient...

    Energy Savers [EERE]

    the Process for Preparing Efficient and Timely Environmental Reviews Under the National Environmental Policy Act Final Guidance on Improving the Process for Preparing Efficient...

  10. Final Guidance for Consideration of Environmental Justice in...

    Office of Environmental Management (EM)

    Consideration of Environmental Justice in Clean Air Act 309 Reviews Final Guidance for Consideration of Environmental Justice in Clean Air Act 309 Reviews This Environmental...

  11. Nuclear Safety Policy, Guidance & Reports | Department of Energy

    Office of Environmental Management (EM)

    and guidance including policy and requirements relating to hazard and accident analysis, facility design and operation, and Quality Assurance. The DOE Technical...

  12. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    Fuel Cell Technologies Publication and Product Library (EERE)

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

  13. Guidance for Energy Efficiency and Conservation Block Grant Program...

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

    for Energy Efficiency and Conservation Block Grant Program Recipients on Formula Grants Guidance for Energy Efficiency and Conservation Block Grant Program Recipients on Formula...

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

    Energy Savers [EERE]

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

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

    Energy Savers [EERE]

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

  16. RCRA ground-water monitoring: Draft technical guidance

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    The manual was prepared to provide guidance for implementing the ground-water monitoring regulations for regulated units contained in 40 CFR Part 264 Subpart F and the permitting standards of 40 CFR Part 270. The manual also provides guidance to owners and operators of treatment, storage, and disposal facilities (TSDFs) that are required to comply with the requirements of 40 CFR Part 264 Subparts J (Tank Systems), K (Surface Impoundments), L (Waste Piles), N (Landfills), and X (Miscellaneous Units). This document updates technical information contained in other sources of U.S. EPA guidance, such as chapter eleven of SW-846 (Revision O, September 1986) and the Technical Enforcement Guidance Document (TEGD).

  17. Energy Department Releases Guidance for Implementation of Cybersecurit...

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

    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...

  18. Guidance on Basic Best Practices in Management of Energy Performance...

    Energy Savers [EERE]

    on Basic Best Practices in Management of Energy Performance Buildings Guidance on Basic Best Practices in Management of Energy Performance Buildings Building energy management best...

  19. H2 Refuel H-Prize Safety Guidance Webinar

    Broader source: Energy.gov [DOE]

    Access the recording and download the presentation slides from the Fuel Cell Technologies Office webinar "H2 Refuel H-Prize Safety Guidance" held on August 6, 2015.

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

    Open Energy Info (EERE)

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

  1. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    SciTech Connect (OSTI)

    U.S. Department of Energy Fuel Cell Technologies Program

    2010-04-01

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

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

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

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

  3. POLICY GUIDANCE MEMORANDUM #14 Establishing a Residence for a...

    Office of Environmental Management (EM)

    4 Establishing a Residence for a Relocation Incentive POLICY GUIDANCE MEMORANDUM 14 Establishing a Residence for a Relocation Incentive An employee who is relocating to a new...

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

    Office of Environmental Management (EM)

    0 Job Opportunity Announcement Template Implementation POLICY GUIDANCE MEMORANDUM 30 Job Opportunity Announcement Template Implementation This memorandum is to announce the...

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

    Office of Environmental Management (EM)

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

  6. POLICY GUIDANCE MEMORANDUM #11A Approval Process for Dual Compensation...

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

    5 Procedures for Compliance with Nepotism and Misuse of Position POLICY GUIDANCE MEMORANDUM 35 Procedures for Compliance with Nepotism and Misuse of Position The purpose of this...

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

    8 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES POLICY GUIDANCE MEMORANDUM 38 EXCEPTION TO POLICY REGARDING QUALITY STEP INCREASES This has been rescinded and incorporated...

  12. POLICY GUIDANCE MEMORANDUM #07 Current Appropriations Law and...

    Office of Environmental Management (EM)

    7 Current Appropriations Law and Compensation of Foreign Nationals POLICY GUIDANCE MEMORANDUM 07 Current Appropriations Law and Compensation of Foreign Nationals Due to recent...

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

    Office of Environmental Management (EM)

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

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

    Open Energy Info (EERE)

    BLM Manual 8270 - General Procedural Guidance for Paleontological Resource Management Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory...

  15. Guidance for State Energy Programs on Revolving Loan Funds |...

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

    funded through the Department of Energy's (DOE's) State Energy Program (SEP) (Grantees). Scope: The provisions of this guidance apply to recipients of SEP funds, pursuant...

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

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

    (Program Notice 10-015) Guidance for Efficiency and Conservation Block Grant Program grantees on consumer rebate programs for Energy Star and other qualified energy efficiency...

  17. Guidance document publications list - Office of Environmental Policy and Assistance RCRA/CERCLA Division (EH-413)

    SciTech Connect (OSTI)

    1995-08-01

    This document provides a listing of Guidance Documents from the RCRA/CERCLA Division for August 1995. Documents are listed under the following categories: RCRA Guidance Manuals; RCRA Information Briefs; CERCLA Guidance Manuals; CERCLA Regulatory Bulletins; RCRA/CERCLA Guidance Manuals; TSCA Guidance Manuals; TSCA Information Briefs; and, Cross Cut Manuals.

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-inPPLforLDRD Report11, SolarMatFermi Nationalannual reports, guidance

  19. NEPA Contracting Reform Guidance | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergy Managing SwimmingMicrosoft The basics of05/24/2011 |guidance on NEPA

  20. Guidance and Opinions | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journalvivo Low-Dose Lowï‚— WeUpdate Jon PeschongGuidance and Opinions

  1. Reproduction of Cnidaria

    E-Print Network [OSTI]

    Fautin, Daphne G.

    2002-01-01

    fission chez les Can. J. Zool. 80: 1735–1754 (2002) DOI: 10.1139/Z02-133 © 2002 NRC Canada 1735 Received 21 November 2001. Accepted 16 May 2002. Published on the NRC Research Press Web site at http://cjz.nrc.ca on 19 November 2002. D.G. Fautin. Department... fission chez les Can. J. Zool. 80: 1735–1754 (2002) DOI: 10.1139/Z02-133 © 2002 NRC Canada 1735 Received 21 November 2001. Accepted 16 May 2002. Published on the NRC Research Press Web site at http://cjz.nrc.ca on 19 November 2002. D.G. Fautin. Department...

  2. International Conference on Machine Control & Guidance 2008 1 Use of a Machine Control & Guidance System, Deter-

    E-Print Network [OSTI]

    & Guidance System, Deter- mination of Excavator Performance, Cost Calculation and Protection Against Damaging with permanent pressure regarding costs due to: · increasing expenses, especially those affecting labor and energy; · shortened schedules for completion of projects; · a highly complex legal system with a growing

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

    SciTech Connect (OSTI)

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

    2011-09-19

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

  4. Guidance for generating legally defensible data

    SciTech Connect (OSTI)

    Rosecrance, A.; Kibler, L. [Core Labs., Houston, TX (United States). Analytical Chemistry Division

    1994-12-31

    The current emphasis on enforcement to achieve compliance with environmental regulations places increased demands on environmental professionals to generate legally defensible data. Since any environmental data may potentially be used in civil or criminal litigation, it must be suitable for use as admissible evidence. Although data cannot be guaranteed to be legally defensible because the proof of defensibility can only be determined in actual legal proceedings, there are steps that can be taken to enhance or increase the chances of admissibility. In order for data to be defensible and of known and documented quality, all sampling and analysis activities must meet applicable technical standards and be fully documented. Record keeping must be stressed throughout all sampling and analysis activities; failure to keep proper records is a common allegation in enforcement actions and a cause for lack of data defensibility. Though there is extensive reference documentation on the requirements for technical data quality, there is limited guidance available on data defensibility procedures. This paper provides guidance to assist field samplers, laboratory personnel, and project managers in planning for and generating legally defensible data. A example checklist that can be used in the planning and verification stages of the data generation process is provided.

  5. Federal Building Metering Guidance (Per U.S.C. 8253(e), Metering...

    Office of Environmental Management (EM)

    Guidance (Per U.S.C. 8253(e), Metering of Energy Use) Federal Building Metering Guidance (Per U.S.C. 8253(e), Metering of Energy Use) Guidance defines which federal buildings are...

  6. Washington and Lee University Guidance on Information Security

    E-Print Network [OSTI]

    Marsh, David

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

  7. Haptic Guidance Improves the Visuo-Manual Tracking of Trajectories

    E-Print Network [OSTI]

    Payan, Yohan

    tasks. The effects of two types of haptic guidances-control in position (HGP) or in force (HGF)­on visuo: Three training techniques of haptic guidance (HGP, HGF or control condition, NHG, without haptic of the visuo-manual tracking of trajectories while no significant improvement was found for HGP or NHG

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

    SciTech Connect (OSTI)

    Not Available

    1987-11-01

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

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

    E-Print Network [OSTI]

    : conserving and enhancing biodiversity climate change mitigation maintaining the peat and soil resource on these sites over the next 15 years. 1 Forest Research, A Strategic Assessment of Afforested Peat ResourceGuidance on peat soils 1 | Peat | Helen Cariss Forestry and deep peat Purpose This policy guidance

  10. Guidance manual for hazardous waste incinerator permits. Final report

    SciTech Connect (OSTI)

    Not Available

    1983-07-01

    The manual provides guidance to the permit writer for designating facility - specific operating conditions necessary to comply with the RCRA standards for hazardous waste incinerators. Each section of the incineration regulation is addressed, including: waste analysis, designation of principal organic hazardous constituents and requirements for operation, inspection and monitoring. Guidance is also provided for evaluating incinerator performance data and trial burn procedures.

  11. Guidance on Microbial Contamination in Previously Flooded Outdoor Areas

    E-Print Network [OSTI]

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

  12. Guidance for the Quality Assurance of Fire Protection Systems

    Broader source: Energy.gov [DOE]

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

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

    E-Print Network [OSTI]

    initiated a process to facilitate the development of small- scale hydro-electricity schemes on land ownedForestry Commission Wales Guidance on rental levels for Hydro Power Guidance on rental levels for hydro power projects Tel: 02920 475961 Email: hydrowales@forestry.gsi.gov.uk Version 1.0 Mike Pitcher 17

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

    E-Print Network [OSTI]

    Casillas Barranquero, Jorge

    safety [4], a minimization of the energy consumption, and others. A Vehicle Guidance System (VGS) assists and collaborate to produce global solution. The global system behavior is made of several emergent phenomenaAn Adaptive Vehicle Guidance System instigated from Ant Colony Behavior Habib M. Kammoun, Ilhem

  15. Annex 2 Risk Guidance Science Programme Office Project Management

    E-Print Network [OSTI]

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

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

    E-Print Network [OSTI]

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

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

    E-Print Network [OSTI]

    Henderson, Gideon

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

  18. Climate Change Guidance: A Pragmatic Approach to Client

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

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

  19. Waypoint Guidance for Small UAVs in Wind John Osborne

    E-Print Network [OSTI]

    Waypoint Guidance for Small UAVs in Wind John Osborne and Rolf Rysdyk University of Washington of guidance algorithms. For small UAVs exposed to strong winds, wind has a very significant nonlinear effect, Seattle, WA, 98115,USA I. abstract Wind is often ignored or only implicitly addressed in design

  20. A guide to CERCLA site assessment. Environmental Guidance

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    This Pocket Guide is a condensed version of information provided in three EPA documents: Guidance for Performing Preliminary Assessments Under CERCLA, Guidance for Performing Site Inspections Under CERCLA, and Hazard Ranking System Guidance Manual. Additionally the guide provides a DOE perspective on site assessment issues and information on the Federal Agency Hazardous Waste Compliance Docket as well as data sources for DOE site assessments. The guide is intended to present this information in a simple, portable, and direct manner that will allow the user to effectively focus on those aspects of the site assessment process of interest. The guide is not intended as a substitute for the three EPA guidance documents mentioned previously. DOE investigators should be thoroughly familiar with the EPA guidance before conducting site assessments. Use this pocketguide as an overview of procedures and requirements and as a field guide.

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

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

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

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

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

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

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

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

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

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

    E-Print Network [OSTI]

    Jones, Graeme A.

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

  5. Technical guidance for siting criteria development

    SciTech Connect (OSTI)

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

    1982-12-01

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

  6. Guidelines for inservice testing at nuclear power plants

    SciTech Connect (OSTI)

    Campbell, P.

    1995-04-01

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

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

    SciTech Connect (OSTI)

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

    1997-05-01

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

  8. Identification and evaluation of PWR in-vessel severe accident management strategies

    SciTech Connect (OSTI)

    Dukelow, J S [Pacific Northwest Lab., Richland, WA (United States); Harrison, D G [Jason Associates, Idaho Falls, ID (United States); Morgenstern, M [Battelle Human Affairs Research Center, Seattle, WA (United States)

    1992-03-01

    This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents.

  9. Specific topics in severe accident management

    SciTech Connect (OSTI)

    Meyer, J.F.; Chung, D.T.; Panciera, V.W.; Traver, L.E.; Humphries, D.S. (SCIENTECH, Inc., Rockville, MD (USA))

    1991-05-01

    This report examines five topical areas of concern to severe accident management. These areas are as follows: Human Factors, Accident Management During Shutdown, Information Needs, Long-term Implications, and Uncertainties. The objective of this report is to assist the NRC in performing its research function and to provide guidance to the industry on accident management strategies, as well as to accident management programs in general. 47 refs., 4 figs., 5 tabs.

  10. Guidance on Dependence Assessment in SPAR-H

    SciTech Connect (OSTI)

    April M. Whaley

    2012-06-01

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

  11. Design of highwall mining equipment electronic guidance package

    SciTech Connect (OSTI)

    Brenden, B.B.; Morgen, G.P.; Shorpik, J.R.; Farrar, R.

    1981-11-01

    This report provides design specifics and guidance software for a guidance system intended for use in guiding an auger type highwall mining head through thin coal seams to depths of up to 600 ft. A small desk top computer is used at the operator's station to send and receive signals in serialized bit streams to a downhole microprocessor. The guidance system accepts signals from a variety of sensors and uses these signals to plot and control the course of the auger head automatically using computer algorithms designed to keep the auger head in the coal seam and maintain a specified stump thickness.

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

    SciTech Connect (OSTI)

    2008-03-26

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

  13. Hanford Site C Tank Farm Meeting Summary

    Office of Environmental Management (EM)

    RPP-45135, Rev. 0 Page 5 of 16 Roster of Participants Name Organization E-Mail Lyon, Jeff Ecology jlyo461@ecy.wa.gov McKenney, Chris NRC Christepher.Mckenney@nrc.gov...

  14. U.S. DEPARTMENT OF ENERGY ENVIRONMENTAL IMPACT STATEMENTS AND...

    Energy Savers [EERE]

    this FEIS issued by NRC, which approved a license to construct and operate the centrifuge plant on 41307. NRC EIS number is NUREG-1834. Adoption (76 FR 29240). Project on hold,...

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

    Energy Savers [EERE]

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

  16. Slide 1

    National Nuclear Security Administration (NNSA)

    NRC - NMMSS I * Germantown, MD May 23-26, 2016 NMMSS Annual Users Training Meeting Philadelphia, PA June 7-9, 2016 DOE - NMMSS II Germantown, MD July 12-14, 2016 NRC - NMMSS I *...

  17. Comparative Assessment of Status and Opportunities for CO2 Capture and Storage and Radioactive Waste Disposal in North America

    E-Print Network [OSTI]

    Oldenburg, C.

    2010-01-01

    2004. NRC (Nuclear Regulatory Commission), Yucca MountainPlan, In: U.S. Nuclear Regulatory Commission, Report NUREG-mrem. The U.S. Nuclear Regulatory Commission (NRC) is the

  18. The Ghost of the Bomb : the Bravo Medical Program, scientific uncertainty, and the legacy of U.S. Cold War science, 1954-2005

    E-Print Network [OSTI]

    Harkewicz, Laura J.

    2010-01-01

    the AEC. The Nuclear Regulatory Commission (NRC) took overfor the U.S. Nuclear Regulatory Commission. 426 Bertell’s1990, the U.S. Nuclear Regulatory Commission (NRC) adopted

  19. Disposal of Specific Articles Containing Radioactive Materials

    E-Print Network [OSTI]

    Jia, Songtao

    Am-241 3. NRC: United States Nuclear Regulatory Commission 4. Sodium Iodide (NaI) Detector: Uses. Disposal of these signs is governed by United States Nuclear Regulatory Commission (NRC) regulations, 10

  20. Pete_Lyons_Nomination_Testimony

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

    where I worked for nearly 30 years. In 2005, I was nominated to the Nuclear Regulatory Commission (NRC), where I served until my term ended in June of 2009. At the NRC, I...

  1. VerDate 112000 15:58 May 15, 2001 Jkt 194001 PO 00000 Frm 00001 Fmt 4717 Sfmt 4717 E:\\FR\\FM\\16MYR2.SGM pfrm10 PsN: 16MYR2 May 16, 2001

    E-Print Network [OSTI]

    Nuclear Regulatory Commission (NRC) or NRC Agreement State license. Today's rule also exempts LLMW regulatory docket at no charge. Additional copies cost $0.15/page. The index and some supporting materials

  2. ENGINEERING ASSOCIATES ENGINEERING

    E-Print Network [OSTI]

    on all sources and source manufacturers listed on the US Nuclear Regulatory Commission (NRC) license by the NRC and published in February 2000 as NUREG/CR-6642, "Risk Analysis And Evaluation Of Regulatory Options For Nuclear Byproduct Mate

  3. Perspectives from the Board's Technical Staff

    Office of Environmental Management (EM)

    Hotspot Yes a -NRC Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants b -NRC Regulatory Guide 1.145 Rev 1 c -DOE letter dated July 18, 2006 from...

  4. CONTAIN independent peer review

    SciTech Connect (OSTI)

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

    1995-01-01

    The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code`s targeted applications include support for containment-related experimental programs, light water and advanced light water reactor plant analysis, and analytical support for resolution of specific technical issues such as direct containment heating. The NRC decided that a broad technical review of the code should be performed by technical experts to determine its overall technical adequacy. For this purpose, a six-member CONTAIN Peer Review Committee was organized and a peer review as conducted. While the review was in progress, the NRC issued a draft ``Revised Severe Accident Code Strategy`` that incorporated revised design objectives and targeted applications for the CONTAIN code. The committee continued its effort to develop findings relative to the original NRC statement of design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications were considered by the Committee in assigning priorities to the Committee`s recommendations. The Committee determined some improvements are warranted and provided recommendations in five code-related areas: (1) documentation, (2) user guidance, (3) modeling capability, (4) code assessment, and (5) technical assessment.

  5. Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado

    SciTech Connect (OSTI)

    NONE

    1997-04-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney disposal site. The site is in Mesa County near Grand Junction, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects public health and safety and the environment. Before each disposal site may be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Cheney disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete and the NRC formally accepts this plan. This document describes the long-term surveillance program the DOE will implement to ensure that the Cheney disposal site performs as designed. The program is based on site inspections to identify potential threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  6. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1996-05-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  7. Long-term surveillance plan for the Gunnison, Colorado, disposal site

    SciTech Connect (OSTI)

    NONE

    1996-02-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  8. Long-term surveillance plan for the Gunnison, Colorado disposal site

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  9. COL Application Content Guide for HTGRs: Revision to RG 1.206, Part 1 - Status Report

    SciTech Connect (OSTI)

    Wayne Moe

    2012-08-01

    A combined license (COL) application is required by the Nuclear Regulatory Commission (NRC) for all proposed nuclear plants. The information requirements for a COL application are set forth in 10 CFR 52.79, “Contents of Applications; Technical Information in Final Safety Analysis Report.” An applicant for a modular high temperature gas-cooled reactor (HTGR) must develop and submit for NRC review and approval a COL application which conforms to these requirements. The technical information necessary to allow NRC staff to evaluate a COL application and resolve all safety issues related to a proposed nuclear plant is detailed and comprehensive. To this, Regulatory Guide (RG) 1.206, “Combined License Applications for Nuclear Power Plants” (LWR Edition), was developed to assist light water reactor (LWR) applicants in incorporating and effectively formatting required information for COL application review (Ref. 1). However, the guidance prescribed in RG 1.206 presumes a LWR design proposal consistent with the systems and functions associated with large LWR power plants currently operating under NRC license.

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

    SciTech Connect (OSTI)

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

    1994-08-01

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

  11. Human Factors Engineering Program Review Model (NUREG-0711)Revision 3: Update Methodology and Key Revisions

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.; Fleger, S.

    2012-07-22

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

  12. Guidance for Energy Efficiency and Conservation Block Grant Program...

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

    U.S. Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) Energy Efficiency and Conservation Block Grant (EECBG) Program Guidance 10-011 dealing with...

  13. OfficeGovernmentEthicsGuidanceEthicsandProcurementIntegrity.pdf...

    Energy Savers [EERE]

    OfficeGovernmentEthicsGuidanceEthicsandProcurementIntegrity.pdf More Documents & Publications Procurement Integrity AcqGuide3pt1.doc&0; PI Brief 6 15 07 final2&0;...

  14. WPN 12-10: Guidance for Returning Interest Earned

    Broader source: Energy.gov [DOE]

    To provide guidance on options available for Grantees and Recipients returning interest earned on advanced federal funds under the U.S. Department of Energy (DOE) Weatherization Assistance Program (WAP).

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

    SciTech Connect (OSTI)

    NONE

    1998-06-01

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

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

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

    on the Statutory Definition of EnergyWater Conservation Measures (ECMs), and Determining Life-Cycle Cost-Effectiveness for ESPCs with Multiple or Single ECMs DOE Guidance on the...

  17. Webinar: H2 Refuel H-Prize Safety Guidance

    Broader source: Energy.gov [DOE]

    The Fuel Cell Technologies Office will present a live webinar entitled "H2 Refuel H-Prize Safety Guidance" on Thursday, August 6, from 1 to 2 p.m. Eastern Daylight Time.

  18. IRS Announces New Tribal Economic Development Bond Allocation Guidance

    Broader source: Energy.gov [DOE]

    Treasury and the IRS published new guidance today allocating Tribal Economic Development Bonds (TEDBs) for Tribes that have projects that are in the final stages of going to the market to receive financing.

  19. NUMERICAL SIMULATION OF VORTEX BREAKDOWN

    E-Print Network [OSTI]

    Prete, Vincenza Del

    2011-01-01

    irrotational vortex. NRC Con. Aero Rep. LR-378. Hald, O. &vortex breakdown" phenomenon. Aero Dept. , Imperial ColI.

  20. Hybrid Simulation of the Seismic Response of Squat Reinforced Concrete Shear Walls

    E-Print Network [OSTI]

    Whyte, Catherine Alexandra

    2012-01-01

    in 1980 when the Nuclear Regulatory Commission’s Office ofthis site from the Nuclear Regulatory Commission (NRC). They

  1. Responding to WMD Terrorism Threats: The Role of Insurance Markets

    E-Print Network [OSTI]

    Jaffee, Dwight M.; Russell, Thomas

    2007-01-01

    to the U.S. Nuclear Regulatory commission. The study isthe U.S. Nuclear Regulatory Commission (NRC) sets standards

  2. US Nuclear Regulatory Commission functional organization charts. Revision 6

    SciTech Connect (OSTI)

    Not Available

    1984-01-01

    The report consists entirely of organizational charts of the US NRC, with functional notes for each office. (GHT)

  3. RCRA (Resource Conservation and Recovery Act) final authorization guidance manual

    SciTech Connect (OSTI)

    Not Available

    1983-06-10

    The document provides guidance regarding final authorization of State Hazardous Waste programs for the pre-HSWA RCRA program. The manual establishes a process and schedule for State Authorization applications, and provides detailed guidance on what State programs must contain in order to qualify for final authorization. The primary audience is U.S. EPA Headquarters and Regional offices and also State agencies, but public requests have also been received so they are included in that broad audience.

  4. WIPP waste characterization program sampling and analysis guidance manual

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) Waste Characterization Program Sampling and Analysis Guidance Manual (Guidance Manual) provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Quality Assurance Program Plan (QAPP) for the WIPP Experimental-Waste Characterization Program (the Program). This Guidance Manual includes all of the sampling and testing methodologies accepted by the WIPP Project Office (DOE/WPO) for use in implementing the Program requirements specified in the QAPP. This includes methods for characterizing representative samples of transuranic (TRU) wastes at DOE generator sites with respect to the gas generation controlling variables defined in the WIPP bin-scale and alcove test plans, as well as waste container headspace gas sampling and analytical procedures to support waste characterization requirements under the WIPP test program and the Resource Conservation and Recovery Act (RCRA). The procedures in this Guidance Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site specific procedures. The use of these procedures is intended to provide the necessary sensitivity, specificity, precision, and comparability of analyses and test results. The solutions to achieving specific program objectives will depend upon facility constraints, compliance with DOE Orders and DOE facilities' operating contractor requirements, and the knowledge and experience of the TRU waste handlers and analysts. With some analytical methods, such as gas chromatography/mass spectrometry, the Guidance Manual procedures may be used directly. With other methods, such as nondestructive/destructive characterization, the Guidance Manual provides guidance rather than a step-by-step procedure.

  5. Organization of the circadian clock and control of rhythmicity in fungi 

    E-Print Network [OSTI]

    Greene, Andrew Vanderford

    2006-10-30

    the components of the FLO. To investigate how an oscillator controls circadian output, we characterized the role of N. crassa NRC-2. The nrc-2 gene is under control of the clock and encodes a putative serine-threonine protein kinase. In a NRC-2-null strain...

  6. United States Nuclear Regulatory

    E-Print Network [OSTI]

    United States Nuclear Regulatory Commission United States Department of Energy United States.S. Nuclear Regulatory Commission Washington, DC 20555-0001 E-mail: DISTRIBUTION@nrc.gov Facsimile: 301; and Commission papers and their attachments. NRC publications in the NUREG series, NRC regulations, and Title 10

  7. Environmental Conservation/Studies "focus area" (with potential courses listed) Urban Stewardship

    E-Print Network [OSTI]

    Schweik, Charles M.

    -SCI 360 Economic Geography GEO-SCI 362 Land Use & Society GEO-SCI 370 Urban Geography GEO-SCI 372 Urban-SCI 597K ST-Conservation Geography HISTORY 383 American Env History HT-MGT 230 Introduction to Travel of Arboriculture NRC 597WR Water Resources Management & Policy NRC 597R Watershed Science and Management NRC 597T

  8. Environmental guidance for public participation in environmental restoration activities

    SciTech Connect (OSTI)

    Not Available

    1991-11-01

    The US Department of Energy (DOE) is issuing this document, entitled Guidance on Public Participation for US Department of Energy Environmental Restoration Activities, to summarize policy and provide guidance for public participation in environmental restoration activities at DOE Headquarters, Field Offices, facilities, and laboratories. While the Office of Environmental Restoration and Waste Management (EM) has environmental restoration responsibility for the majority of DOE sites and facilities, other DOE Project Offices have similar responsibilities at their sites and facilities. This guidance is applicable to all environment restoration activities conducted by or for DOE under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA); the Resource Conservation and Recovery Act of 1976 (RCRA) as amended by the Hazardous and Solid Waste Amendments of 1984 (HSWA) (corrective actions only); and the National Environmental Policy Act of 1969 (NEPA). This guidance also is applicable to CERCLA remedial action programs under the Uranium Mill Tailings Radiation Control Act of 1978 and the Formerly Utilized Sites Remedial Action Program, where DOE is the designated lead. The primary objectives of this guidance document are as follows: acclimate DOE staff to a changing culture that emphasizes the importance of public participation activities; provide direction on implementing these public participation activities; and, provide consistent guidance for all DOE Field Offices and facilities. The purpose of this document is to provide guidance on conducting effective public participation activities for environmental restoration activities under CERCLA; RCRA corrective actions under sections 3004(u), 3004(v), and 3008(h); and NEPA public participation activities.

  9. Review of Quantitative Software Reliability Methods

    SciTech Connect (OSTI)

    Chu, T.L.; Yue, M.; Martinez-Guridi, M.; Lehner, J.

    2010-09-17

    The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on deterministic engineering criteria. In its 1995 probabilistic risk assessment (PRA) policy statement, the Commission encouraged the use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. Although many activities have been completed in the area of risk-informed regulation, the risk-informed analysis process for digital systems has not yet been satisfactorily developed. Since digital instrumentation and control (I&C) systems are expected to play an increasingly important role in nuclear power plant (NPP) safety, the NRC established a digital system research plan that defines a coherent set of research programs to support its regulatory needs. One of the research programs included in the NRC's digital system research plan addresses risk assessment methods and data for digital systems. Digital I&C systems have some unique characteristics, such as using software, and may have different failure causes and/or modes than analog I&C systems; hence, their incorporation into NPP PRAs entails special challenges. The objective of the NRC's digital system risk research is to identify and develop methods, analytical tools, and regulatory guidance for (1) including models of digital systems into NPP PRAs, and (2) using information on the risks of digital systems to support the NRC's risk-informed licensing and oversight activities. For several years, Brookhaven National Laboratory (BNL) has worked on NRC projects to investigate methods and tools for the probabilistic modeling of digital systems, as documented mainly in NUREG/CR-6962 and NUREG/CR-6997. However, the scope of this research principally focused on hardware failures, with limited reviews of software failure experience and software reliability methods. NRC also sponsored research at the Ohio State University investigating the modeling of digital systems using dynamic PRA methods. These efforts, documented in NUREG/CR-6901, NUREG/CR-6942, and NUREG/CR-6985, included a functional representation of the system's software but did not explicitly address failure modes caused by software defects or by inadequate design requirements. An important identified research need is to establish a commonly accepted basis for incorporating the behavior of software into digital I&C system reliability models for use in PRAs. To address this need, BNL is exploring the inclusion of software failures into the reliability models of digital I&C systems, such that their contribution to the risk of the associated NPP can be assessed.

  10. Regulatory and technical reports (abstract index journal): Annual compilation for 1994. Volume 19, Number 4

    SciTech Connect (OSTI)

    1995-03-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order. These precede the following indexes: secondary report number index, personal author index, subject index, NRC originating organization index (staff reports), NRC originating organization index (international agreements), NRC contract sponsor index (contractor reports), contractor index, international organization index, and licensed facility index. A detailed explanation of the entries precedes each index.

  11. Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

    SciTech Connect (OSTI)

    1995-04-01

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR).

  12. LLW Notes, Volume 12, Number 8

    SciTech Connect (OSTI)

    Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

    1997-12-31

    Contents include articles entitled: Chem-Nuclear documents new plan for Barnwell; Nebraska releases technical analysis of LLRW facility; Southeast Compact suspends funding for NC facility development; NC governor and Southeast Compact differ on proposed MOU; Midwest Compact to return export fees; State legislators` group revises radioactive waste policy; Internal documents discuss administration`s policy on Ward Valley; BLM issues EA for Ward Valley testing; California DHS, NRC criticize DOI`s testing protocols; Army removes training mines from Ward Valley site; The 1997 gubernatorial elections and a look ahead to 1998; Court throws out case challenging Pennsylvania`s siting law; DOE files notice of appeal in WCS suit; Central Compact moves to dismiss ``Veto`` authority suit; Congress exempts NAS from FACA; Judge sets schedule for Ward Valley case; Court won`t order DOE to accept spent fuel by deadline; NRC chairman expresses concern re CERCLA reauthorization; Senators question EPA`s guidance on remediation; EPA issues guidance, criticizes NRC decommissioning rule; Members of Congress clarify FUSRAP transfer; HLW legislation passes House by wide margin; Takings legislation passes House; Energy and water bill signed into law; and Senate confirms 5 of 6 DOE appointees.

  13. Regulatory analysis technical evaluation handbook. Final report

    SciTech Connect (OSTI)

    NONE

    1997-01-01

    The purpose of this Handbook is to provide guidance to the regulatory analyst to promote preparation of quality regulatory analysis documents and to implement the policies of the Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission (NUREG/BR-0058 Rev. 2). This Handbook expands upon policy concepts included in the NRC Guidelines and translates the six steps in preparing regulatory analyses into implementable methodologies for the analyst. It provides standardized methods of preparation and presentation of regulatory analyses, with the inclusion of input that will satisfy all backfit requirements and requirements of NRC`s Committee to Review Generic Requirements. Information on the objectives of the safety goal evaluation process and potential data sources for preparing a safety goal evaluation is also included. Consistent application of the methods provided here will result in more directly comparable analyses, thus aiding decision-makers in evaluating and comparing various regulatory actions. The handbook is being issued in loose-leaf format to facilitate revisions. NRC intends to periodically revise the handbook as new and improved guidance, data, and methods become available.

  14. Semi-Annual Davis-Bacon Act Enforcement Report Form Guidance...

    Energy Savers [EERE]

    Semi-Annual Davis-Bacon Act Enforcement Report Form Guidance Semi-Annual Davis-Bacon Act Enforcement Report Form Guidance Semi-Annual Davis-Bacon Act Enforcement Report Form...

  15. MaGKeyS : a haptic guidance keyboard system for facilitating sensorimotor training and rehabilitation

    E-Print Network [OSTI]

    Lewiston, Craig Edwin

    2009-01-01

    The Magnetic Guidance Keyboard System (MaGKeyS) embodies a new haptic guidance technology designed to facilitate sensorimotor training and rehabilitation. MaGKeyS works by employing active magnetic force to guide finger ...

  16. H2 Refuel H-Prize Safety Guidance | Department of Energy

    Office of Environmental Management (EM)

    Safety Guidance H2 Refuel H-Prize Safety Guidance August 6, 2015 1:00PM to 2:00PM EDT The Fuel Cell Technologies Office will present a live webinar entitled "H2 Refuel H-Prize...

  17. Spreading The Word: Capital Market Consequences of Business Press Coverage of Management Earnings Guidance 

    E-Print Network [OSTI]

    Twedt, Brady J

    2013-06-21

    This study investigates the role of the business press in disseminating management earnings guidance news to capital market participants. Using a unique sample of over 55,000 articles that relate specifically to management guidance, I find that 48...

  18. Guidance on Life-Cycle Cost Analysis Required by Executive Order...

    Energy Savers [EERE]

    Guidance on Life-Cycle Cost Analysis Required by Executive Order 13123 Guidance on Life-Cycle Cost Analysis Required by Executive Order 13123 Guide describes the clarification of...

  19. CEQ Issues Revised Draft NEPA Guidance on GHG Emissions and Climate...

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

    Revised Draft NEPA Guidance on GHG Emissions and Climate Change CEQ Issues Revised Draft NEPA Guidance on GHG Emissions and Climate Change March 3, 2015 - 10:37am Addthis CEQ...

  20. Draft Guidance for Section 242 of the Energy Policy Act of 2005...

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

    Draft Guidance for Section 242 of the Energy Policy Act of 2005 - Hydroelectric Production Incentive Program - July 2014 Draft Guidance for Section 242 of the Energy Policy Act of...

  1. International Conference on Machine Control & Guidance 2008 1 Universal Developer Platform for Machine Control

    E-Print Network [OSTI]

    . Furthermore 1D, 2D or 3D guidance or control of complex machinery generally includes heavy and diverse (design) · display hints (for guidance) or control actuators (e.g. engines or valves) 2 MACHINE AUTOMATION

  2. Guidance Document Quick Guide to Assess Risk for Hazardous Chemicals

    E-Print Network [OSTI]

    Guidance Document Quick Guide to Assess Risk for Hazardous Chemicals The following outline provides a summary of the steps that laboratory workers should use to assess the risks of handling toxic chemicals with each chemical involved in the proposed work. Are any of the chemicals carcinogens or suspected

  3. Rev: June 24, 2013 1 Guidance on Workplace Hazards Impacting

    E-Print Network [OSTI]

    is available to assist in evaluating risks, and to advise on steps that can help reduce potential for risks for students and instructors. And this guidance may alert an individual about risks in the home environment radiation exposures. The Washington Department of Labor and Industries performed a detailed evaluation

  4. WPN 11-6 A: Supplemental Health and Safety Guidance

    Broader source: Energy.gov [DOE]

    To update and provide additional time for implementation of WPN 11-6 as part of the U.S. Department of Energy (DOE) Weatherization Assistance Program (WAP). This guidance also provides direction to Grantees as they develop their health and safety plans and procedures.

  5. THE INDUSTRIAL EXCELLENCE AWARD AS A TRAINING GUIDANCE TOOL

    E-Print Network [OSTI]

    Aristomenis, Antoniadis

    THE INDUSTRIAL EXCELLENCE AWARD AS A TRAINING GUIDANCE TOOL NICHOLAS BILALIS, Professor Department. Introduction This paper presents an approach for meeting the current educational needs of industry on industrial excellence. The methodology is based on the Industrial Excellence model developed by INSEAD

  6. Soil Vapor Extraction System Optimization, Transition, and Closure Guidance

    SciTech Connect (OSTI)

    Truex, Michael J.; Becker, Dave; Simon, Michelle A.; Oostrom, Martinus; Rice, Amy K.; Johnson, Christian D.

    2013-02-08

    Soil vapor extraction (SVE) is a prevalent remediation approach for volatile contaminants in the vadose zone. A diminishing rate of contaminant extraction over time is typically observed due to 1) diminishing contaminant mass, and/or 2) slow rates of removal for contamination in low-permeability zones. After a SVE system begins to show indications of diminishing contaminant removal rate, SVE performance needs to be evaluated to determine whether the system should be optimized, terminated, or transitioned to another technology to replace or augment SVE. This guidance specifically addresses the elements of this type of performance assessment. While not specifically presented, the approach and analyses in this guidance could also be applied at the onset of remediation selection for a site as a way to evaluate current or future impacts to groundwater from vadose zone contamination. The guidance presented here builds from existing guidance for SVE design, operation, optimization, and closure from the U.S. Environmental Protection Agency, U.S. Army Corps of Engineers, and the Air Force Center for Engineering and the Environment. The purpose of the material herein is to clarify and focus on the specific actions and decisions related to SVE optimization, transition, and/or closure.

  7. Massachusetts Policy Guidance for Regulating Solar Energy Systems

    Broader source: Energy.gov [DOE]

    This policy guidance was established to summarize, explain, and help communities apply four of the Massachusetts statutes that apply to solar energy systems. These statutes include: Chapter 40A Section 3 (solar exemptions), Chapter 40A Section 9B (solar access), Chapter 187 Section 1A (solar easements), and Chapter 40C (Historic Districts).

  8. Guidance Note 052 RISK ASSESSMENTS FOR HAZARDOUS CHEMICALS

    E-Print Network [OSTI]

    Guidance Note 052 RISK ASSESSMENTS FOR HAZARDOUS CHEMICALS as required under the CONTROL OF SUBSTANCES HAZARDOUS TO HEALTH REGULATIONS (COSHH) and the DANGEROUS SUBSTANCES AND EXPLOSIVE ATMOSPHERES Involving the Use of Hazardous Chemicals. COSHH requires health risks to be assessed and controlled

  9. Guidance Document Quick Guide to Assess Risk for Hazardous Chemicals

    E-Print Network [OSTI]

    Guidance Document Quick Guide to Assess Risk for Hazardous Chemicals The following outline provides) or other sources of information. In cases where substances with significant or unusual potential hazards of experience and the degree of potential hazard associated with the proposed experiment, it may be necessary

  10. Microfluidic control of axonal guidance *, Bryan Black1

    E-Print Network [OSTI]

    Texas at Arlington, University of

    Microfluidic control of axonal guidance Ling Gu1 *, Bryan Black1 *, Simon Ordonez1 , Argha Mondal1, producing turning angles of up to 906. Microfluidic flow simulations indicate that an axon may experience, no evidence exists to confirm the direct influence of microfluidic flow on axonal outgrowth and migration

  11. Last Updated: August 2008 Data Protection Guidance: Student Finance

    E-Print Network [OSTI]

    Mumby, Peter J.

    Last Updated: August 2008 Data Protection Guidance: Student Finance Student finance information The University will not release any information to third parties without consent. From time to time the Finance Protection Authority Form, these are available from Finance Services and only relate to information

  12. SPAR-H Step-by-Step Guidance

    SciTech Connect (OSTI)

    April M. Whaley; Dana L. Kelly; Ronald L. Boring; William J. Galyean

    2012-06-01

    Step-by-step guidance was developed recently at Idaho National Laboratory for the US Nuclear Regulatory Commission on the use of the Standardized Plant Analysis Risk-Human Reliability Analysis (SPAR-H) method for quantifying Human Failure Events (HFEs). This work was done to address SPAR-H user needs, specifically requests for additional guidance on the proper application of various aspects of the methodology. This paper overviews the steps of the SPAR-H analysis process and highlights some of the most important insights gained during the development of the step-by-step directions. This supplemental guidance for analysts is applicable when plant-specific information is available, and goes beyond the general guidance provided in existing SPAR-H documentation. The steps highlighted in this paper are: Step-1, Categorizing the HFE as Diagnosis and/or Action; Step-2, Rate the Performance Shaping Factors; Step-3, Calculate PSF-Modified HEP; Step-4, Accounting for Dependence, and; Step-5, Minimum Value Cutoff.

  13. School of Engineering Guidance on Completing a Risk Assessment

    E-Print Network [OSTI]

    Neri, Peter

    April 2013 School of Engineering Guidance on Completing a Risk Assessment Based on HSE Five steps to risk assessment INDG163(rev2) What is risk assessment? A risk assessment is simply a careful if necessary When thinking about your risk assessment, remember: A hazard is anything that may cause harm

  14. Climate policy and competitiveness: Policy guidance and quantitative evidence

    E-Print Network [OSTI]

    Climate policy and competitiveness: Policy guidance and quantitative evidence Jared C. Carbone NicholasRivers July 2014 Abstract When considering adoption of a domestic climate change policy survey the literature on the quantitative impacts of unilateral climate change policy derived from

  15. Real-time Navigation, Guidance, and Control of a UAV using Low-cost Sensors

    E-Print Network [OSTI]

    Kim, Jonghyuk "Jon"

    maneuvering scenarios. Index Terms-- Autonomous UAV, low cost sensors, Kalman filter, guidance and controlReal-time Navigation, Guidance, and Control of a UAV using Low-cost Sensors Jong-Hyuk Kim, Stuart, Australia Email: {s.wishart}@acfr.usyd.edu.au Abstract-- Applying low-cost sensors for the Guidance, Navi

  16. Enhancement-led Institutional Review (ELIR): Follow-up Reports guidance

    E-Print Network [OSTI]

    Neirotti, Juan Pablo

    1 Enhancement-led Institutional Review (ELIR): Follow-up Reports guidance Purpose of this guidance-up Reports. Guidance from the ELIR Handbook 2 The ELIR Handbook states: Follow-up Reports One year after publication of the ELIR Outcome and Technical Reports, the institution will submit a Follow-up Report

  17. Developing Data Management Policy and Guidance Documents for your NARSTO Program or Project

    E-Print Network [OSTI]

    Developing Data Management Policy and Guidance Documents for your NARSTO Program or Project of data management policy and guidance documents for program and project use in developing data management within the NARSTO context. Add additional project-specific guidance as needed. Document Development

  18. Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177

    SciTech Connect (OSTI)

    Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre; Day, Neil; Gambone Rodriguez, Kimberly; Cruz, Luis; Sotomayor-Rivera, Alexis; Vechioli, Lucieann; Vera, John; Pstrak, David

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (?49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leaving the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)

  19. NGNP Project Regulatory Gap Analysis for Modular HTGRs

    SciTech Connect (OSTI)

    Wayne Moe

    2011-09-01

    The Next Generation Nuclear Plant (NGNP) Project Regulatory Gap Analysis (RGA) for High Temperature Gas-Cooled Reactors (HTGR) was conducted to evaluate existing regulatory requirements and guidance against the design characteristics specific to a generic modular HTGR. This final report presents results and identifies regulatory gaps concerning current Nuclear Regulatory Commission (NRC) licensing requirements that apply to the modular HTGR design concept. This report contains appendices that highlight important HTGR licensing issues that were found during the RGA study. The information contained in this report will be used to further efforts in reconciling HTGR-related gaps in the NRC licensing structure, which has to date largely focused on light water reactor technology.

  20. Planning guidance for the Chemical Stockpile Emergency Preparedness Program

    SciTech Connect (OSTI)

    Shumpert, B.L.; Watson, A.P.; Sorensen, J.H. [and others] and others

    1995-02-01

    This planning guide was developed under the direction of the U.S. Army and the Federal Emergency Management Agency (FEMA) which jointly coordinate and direct the development of the Chemical Stockpile Emergency Preparedness Program (CSEPP). It was produced to assist state, local, and Army installation planners in formulating and coordinating plans for chemical events that may occur at the chemical agent stockpile storage locations in the continental United States. This document provides broad planning guidance for use by both on-post and off-post agencies and organizations in the development of a coordinated plan for responding to chemical events. It contains checklists to assist in assuring that all important aspects are included in the plans and procedures developed at each Chemical Stockpile Disposal Program (CSDP) location. The checklists are supplemented by planning guidelines in the appendices which provide more detailed guidance regarding some issues. The planning guidance contained in this document will help ensure that adequate coordination between on-post and off-post planners occurs during the planning process. This planning guide broadly describes an adequate emergency planning base that assures that critical planning decisions will be made consistently at every chemical agent stockpile location. This planning guide includes material drawn from other documents developed by the FEMA, the Army, and other federal agencies with emergency preparedness program responsibilities. Some of this material has been developed specifically to meet the unique requirements of the CSEPP. In addition to this guidance, other location-specific documents, technical studies, and support studies should be used as needed to assist in the planning at each of the chemical agent stockpile locations to address the specific hazards and conditions at each location.

  1. Guidance for Energy Efficiency and Conservation Block Grant Grantees on

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing Programs | Department of Energy Guidance for Energy

  2. Guidance for FY2014 Facilities Information Management System Data

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing Programs | Department of Energy Guidance

  3. Guidance for Federal Departments and Agencies on Establishing, Applying,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing Programs | Department of Energy GuidanceManagement |and

  4. Guidance for Site-wide Environmental Impact Statements | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing Programs | Department of Energy June 2015 Guidance

  5. Facility Safety Policy, Guidance & Reports | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuelsof Energy Services » Program ManagementAct4Facility Safety Policy, Guidance

  6. Security Policy, Guidance & Reports | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsofProgram: Report AppendicesAVideo » Search resultsEnergyPolicy, Guidance &

  7. Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

    SciTech Connect (OSTI)

    Chopra, Omesh K.; Diercks, Dwight R.; Ma, David Chia-Chiun; Garud, Yogendra S.

    2013-12-17

    At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC’s assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and 1988. All of the reports reviewed were the regulator’s assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants.

  8. Long-Term Stewardship Baseline Report and Transition Guidance

    SciTech Connect (OSTI)

    Kristofferson, Keith

    2001-11-01

    Long-term stewardship consists of those actions necessary to maintain and demonstrate continued protection of human health and the environment after facility cleanup is complete. As the Department of Energy’s (DOE) lead laboratory for environmental management programs, the Idaho National Engineering and Environmental Laboratory (INEEL) administers DOE’s long-term stewardship science and technology efforts. The INEEL provides DOE with technical, and scientific expertise needed to oversee its long-term environmental management obligations complexwide. Long-term stewardship is administered and overseen by the Environmental Management Office of Science and Technology. The INEEL Long-Term Stewardship Program is currently developing the management structures and plans to complete INEEL-specific, long-term stewardship obligations. This guidance document (1) assists in ensuring that the program leads transition planning for the INEEL with respect to facility and site areas and (2) describes the classes and types of criteria and data required to initiate transition for areas and sites where the facility mission has ended and cleanup is complete. Additionally, this document summarizes current information on INEEL facilities, structures, and release sites likely to enter long-term stewardship at the completion of DOE’s cleanup mission. This document is not intended to function as a discrete checklist or local procedure to determine readiness to transition. It is an overarching document meant as guidance in implementing specific transition procedures. Several documents formed the foundation upon which this guidance was developed. Principal among these documents was the Long-Term Stewardship Draft Technical Baseline; A Report to Congress on Long-Term Stewardship, Volumes I and II; Infrastructure Long-Range Plan; Comprehensive Facility Land Use Plan; INEEL End-State Plan; and INEEL Institutional Plan.

  9. LEDS Tool: Step-By-Step Guidance to a Long-Term Framework for...

    Open Energy Info (EERE)

    Guidance to a Long-Term Framework for Continuous Sustainable Development Cooperation AgencyCompany Organization: International Partnership on Mitigation and MRV Partner:...

  10. Webinar: Guidance for Filling Out a Detailed H2A Production Case Study

    Broader source: Energy.gov [DOE]

    Video recording and text version of the webinar titled, Guidance for Filling Out a Detailed H2A Production Case Study, originally presented on July 9, 2013.

  11. CEQ Guidance on the Application of NEPA to Proposed Federal Actions...

    Office of Environmental Management (EM)

    with the governments of Mexico and Canada to develop an agreement on transboundary environmental impact assessment in North America, the guidance pertains to all federal agency...

  12. WPN 12-9: Weatherization Assistance Program Incidental Repair Measure Guidance

    Broader source: Energy.gov [DOE]

    To provide guidance on incidental repair measures (IRM) allowable under the U.S. Department of Energy Weatherization Assistance Program (WAP).

  13. Learning to perform a new movement with robotic assistance: comparison of haptic guidance and visual demonstration

    E-Print Network [OSTI]

    Liu, J; Cramer, SC; Reinkensmeyer, DJ

    2006-01-01

    perform a new movement with robotic assistance: comparisonMechanical guidance with a robotic device is a candidatereproduce the path without robotic demonstration. Results:

  14. Lessons and Guidance on Securing financing for RE/EE projects...

    Open Energy Info (EERE)

    Lessons and Guidance on Securing financing for REEE projects in Southern Africa through Gold Standard Carbon Revenues Jump to: navigation, search Tool Summary LAUNCH TOOL Name:...

  15. DOE Guidance on the Statutory Definition of Energy/Water Conservation...

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

    Statutory Definition of EnergyWater Conservation Measures (ECMs), and Determining Life-Cycle Cost-Effectiveness for ESPCs with Multiple or Single ECMs DOE Guidance on the...

  16. Guidance for State Energy Program Grantees on Sub-Recipient Monitoring...

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

    Guidance for energy efficiency and conservation block grants grantees on sub-recipient monitoring. eecbg10-019subgranteemonitoringguidance.pdf More Documents & Publications...

  17. ICDF Complex Waste Profile and Verification Sample Guidance

    SciTech Connect (OSTI)

    W. M. Heileson

    2006-10-01

    This guidance document will assist waste generators who characterize waste streams destined for disposal at the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) Complex. The purpose of this document is to develop a conservative but appropriate way to (1) characterize waste for entry into the ICDF; (2) ensure compliance with the waste acceptance criteria; and (3) facilitate disposal at the ICDF landfill or evaporation pond. In addition, this document will establish the waste verification process used by ICDF personnel to ensure that untreated waste meets applicable ICDF acceptance limits

  18. Resource Conservation and Recovery Act (RCRA) facility assessment guidance

    SciTech Connect (OSTI)

    Rastatter, C.; Fagan, D.; Foss, D.

    1986-10-01

    Facilities that manage hazardous wastes are required to obtain permits under the Resource Conservation and Recovery Act (RCRA) of 1976. This guidance document informs RCRA permit writers and enforcement officials of procedures to be used in conducting RCRA Facility Assessments. The RCRA corrective-action program was established to investigate and require clean up of releases of hazardous wastes or constituents to the environment at facilities subject to RCRA permits. Releases to ground water, surface water, air, soil, and subsurface strata may be addressed.

  19. Guidance on Meeting Executive Order 13693 Water Provisions | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool Fits the Bill Financing Tool Fits27,NetworkEnergy Guidance forEx

  20. Guidance on New Construction under an Energy Savings Performance Contract |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool Fits the Bill Financing Tool Fits27,NetworkEnergy Guidance forExDepartment of

  1. Guidance on New Construction under an Energy Savings Performance Contract

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing Programs | Department of Energy June 2015onGuidance on

  2. Guidance on Reading the Scorecard | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing Programs | Department of Energy June 2015onGuidance

  3. Perspectives on plant vulnerabilities & other plant and containment improvements

    SciTech Connect (OSTI)

    LaChance, J.; Kolaczkowski, A.; Kahn, J. [and others

    1996-01-01

    The primary goal of the Individual Plant Examination (IPE) Program was for licensees to identify plant-unique vulnerabilities and actions to address these vulnerabilities. A review of these vulnerabilities and plant improvements that were identified in the IPEs was performed as part of the IPE Insights Program sponsored by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this effort was to characterize the identified vulnerabilities and the impact of suggested plant improvements. No specific definition for {open_quotes}vulnerability{close_quotes} was provided in NRC Generic Letter 88-20 or in the subsequent NRC IPE submittal guidance documented in NUREG-1335. Thus licensees were left to use their own definitions. Only 20% of the plants explicitly stated that they had vulnerabilities. However, most licensees identified other plant improvements to address issues not explicitly classified as vulnerabilities, but pertaining to areas in which overall plant safety could potentially be increased. The various definitions of {open_quotes}vulnerability{close_quotes} used by the licensees, explicitly identified vulnerabilities, proposed plant improvements to address these vulnerabilities, and other plant improvements are summarized and discussed.

  4. Low-Level Waste Regulation: Putting Principles Into Practice - 13297 - The Richard S. Hodes, M.D., Honor Lecture Award

    SciTech Connect (OSTI)

    Kennedy, James E.

    2013-07-01

    In carrying out its mission to ensure the safe use of radioactive materials for beneficial civilian purposes while protecting people and the environment, the U.S. Nuclear Regulatory Commission (NRC) adheres to its Principles of Good Regulation. The Principles-Independence, Openness, Efficiency, Clarity, and Reliability-apply to the agency as a whole in its decision-making and to the individual conduct of NRC employees. This paper describes the application of the Principles in a real-life staff activity, a guidance document used in the NRC's low-level radioactive waste (LLW) program, the Concentration Averaging and Encapsulation Branch Technical Position (CA BTP). The staff's process to revise the document, as well as the final content of the document, were influenced by following the Principles. For example, consistent with the Openness Principle, the staff conducted a number of outreach activities and received many comments on three drafts of the document. Stakeholder comments affected the final staff positions in some cases. The revised CA BTP, once implemented, is expected to improve management and disposal of LLW in the United States. Its positions have an improved nexus to health and safety; are more performance-based than previously, thus providing licensees with options for how they achieve the required outcome of protecting an inadvertent human intruder into a disposal facility; and provide for disposal of more sealed radioactive sources, which are a potential threat to national security. (author)

  5. Guidance for Human-system Interfaces to Automatic Systems

    SciTech Connect (OSTI)

    O'Hara, J.M.; Higgins, J.; Stephen Fleger; Valerie Barnes

    2010-09-27

    Automation is ubiquitous in modern complex systems, and commercial nuclear- power plants are no exception. Automation is applied to a wide range of functions, including monitoring and detection, situation assessment, response planning, and response implementation. Automation has become a 'team player' supporting personnel in nearly all aspects of system operation. In light of its increasing use and importance in new- and future-plants, guidance is needed to conduct safety reviews of the operator's interface with automation. The objective of this research was to develop such guidance. We first characterized the important HFE aspects of automation, including six dimensions: Levels, functions, processes, modes, flexibility, and reliability. Next, we reviewed literature on the effects of all of these aspects of automation on human performance, and on the design of human-system interfaces (HSIs). Then, we used this technical basis established from the literature to identify general principles for human-automation interaction and to develop review guidelines. The guidelines consist of the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration.

  6. COMBINED ADAPTIVE CONTROLLER FOR UAV GUIDANCE B.R. Andrievsky, A.L. Fradkov

    E-Print Network [OSTI]

    COMBINED ADAPTIVE CONTROLLER FOR UAV GUIDANCE B.R. Andrievsky, A.L. Fradkov Institute for Problems vehicle (UAV) homing guidance system is pro- posed. The adaptation algorithm provides prescribed attitude adaptive controller in the case of significant uncertainty of the UAV parameters and time dependence

  7. UAV Control and Guidance for Autonomous Cooperative Tracking of a Moving Target

    E-Print Network [OSTI]

    UAV Control and Guidance for Autonomous Cooperative Tracking of a Moving Target Richard Wise;#12;University of Washington Abstract UAV Control and Guidance for Autonomous Cooperative Tracking of a Moving Unmanned Aerial Vehicles (UAVs). Relative position coordination of UAVs is en- forced. The comparison

  8. USU WEB SITE POLICIES AND GUIDELINES GUIDANCE FOR PUBLISHING CONTENT TO THE USU WEB SITE

    E-Print Network [OSTI]

    USU WEB SITE POLICIES AND GUIDELINES June, 2015 GUIDANCE FOR PUBLISHING CONTENT TO THE USU WEB SITE/ APPLICATION AND WEB DEVELOPMENT/ USU WEB MASTER #12;CONTENTS USU Web Site Policies and Guidelines..........................................................................................................1 Guidance for Publishing Content to the USU Web Site

  9. THIRD-YEAR REVIEW OF POSTGRADUATE RESEARCH STUDENTS: REPORT FORM AND GUIDANCE

    E-Print Network [OSTI]

    Wright, Francis

    THIRD-YEAR REVIEW OF POSTGRADUATE RESEARCH STUDENTS: REPORT FORM AND GUIDANCE Please complete Development Activity Record. #12;THIRD-YEAR REVIEW OF POSTGRADUATE RESEARCH STUDENTS: REPORT FORM AND GUIDANCE. The process should ideally be completed by the end of the third year of registration, i.e., by 30th September

  10. DEVELOPMENT OF A TRACKING AND GUIDANCE SYSTEM FOR A FIELD ROBOT

    E-Print Network [OSTI]

    DEVELOPMENT OF A TRACKING AND GUIDANCE SYSTEM FOR A FIELD ROBOT J.W. Hofstee1 , T.E. Grift2 , L, Urbana, IL 61801, USA ABSTRACT Small robots operating between crop rows need another guidance system than. INTRODUCTION Automatically guided robotic vehicles will perform many agricultural operations in the future

  11. Multi-robot Human Guidance using Topological Graphs Piyush Khandelwal and Peter Stone

    E-Print Network [OSTI]

    Stone, Peter

    Multi-robot Human Guidance using Topological Graphs Piyush Khandelwal and Peter Stone Department,pstone}@cs.utexas.edu Abstract Prior approaches to human guidance using robots in- side a building have typically been limited to a single robot guide that navigates a human from start to goal. However, due to their limited mobility

  12. Design Guidance for Bolted Connections in Structures of Pultruded Shapes: Gaps in Knowledge

    E-Print Network [OSTI]

    Mottram, Toby

    Design Guidance for Bolted Connections in Structures of Pultruded Shapes: Gaps in Knowledge J. T, design guidance, frame structures. ABSTRACT The purpose of this paper is to introduce a brand new standard for the design of frame structures of pultruded Fibre-Reinforced Polymer (FRP) shapes

  13. 1182 J. GUIDANCE, VOL. 19, NO. 5: ENGINEERING NOTES Fig. 2 Fixed and optimized flight paths.

    E-Print Network [OSTI]

    Singh, Tarunraj

    and optimized flight paths. Conclusion A simple guidance law for operation of dual-fuel SSTO launch vehicles hasbeen developed andused to determine the optimal value of the transition Mach number from dual fuel higher dynamic pressure than the fixed, particularly in dual-fuel mode. In the future, the guidance

  14. ITL BULLETIN FOR AUGUST 2013 ITL PUBLISHES GUIDANCE ON ENTERPRISE PATCH MANAGEMENT TECHNOLOGIES

    E-Print Network [OSTI]

    ITL BULLETIN FOR AUGUST 2013 ITL PUBLISHES GUIDANCE ON ENTERPRISE PATCH MANAGEMENT TECHNOLOGIES published guidance on patch management technologies. Written by Murugiah Souppaya of NIST and Karen Scarfone Technologies, is designed to assist organizations in understanding the basics of enterprise patch management

  15. Defense Transuranic Waste Program. Transuranic waste transportation assessment and guidance report

    SciTech Connect (OSTI)

    Not Available

    1985-08-01

    The Transportation Assessment and Guidance Report (TAGR) is designed to provide DOE-managed defense sites with guidance and citable analyses addressing National Environmental Policy Act (NEPA) requirements for qualifying and transporting transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico.

  16. Introduction This Guidance Note provides advice and information on how to address historic

    E-Print Network [OSTI]

    and other sources of information at the end of this Guidance Note.) As outlined above, historic environmentIntroduction This Guidance Note provides advice and information on how to address historic of whether or not a particular project requires formal planning permission. Key documents are: n England

  17. Characterization of axon guidance cue sensitivity of human embryonic stem cell-derived dopaminergic neurons

    E-Print Network [OSTI]

    McConnell, Susan

    Characterization of axon guidance cue sensitivity of human embryonic stem cell-derived dopaminergic derived from human embryonic stem cells will be useful in future transplantation studies of Parkinson of hESC-derived neurons to respond to axon guidance cues will be critical. Both Netrin-1 and Slit-2

  18. Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report

    SciTech Connect (OSTI)

    Donoghue, J.E.; Donohew, J.N.; Golub, G.R.; Kenneally, R.M.; Moore, P.B.; Sands, S.P.; Throm, E.D.; Wetzel, B.A. [Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal

    1994-02-01

    This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC`s ``Statement of Policy for the Regulation of Advanced Nuclear Power Plants`` (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC`s preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant`s research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified.

  19. Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah

    SciTech Connect (OSTI)

    NONE

    1997-05-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Mexican Hat, Utah, disposal site. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Mexican Hat disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the disposal site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Mexican Hat disposal site performs as designed. The program is based on two distinct types of activities: (1) site inspections to identify potential threats to disposal cell integrity, and (2) monitoring of selected seeps to observe changes in flow rates and water quality. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03. 18 refs., 6 figs., 1 tab.

  20. Scientific Guidance, Research, and Educational Outreach for the ARM Climate Research Facility (ACRF) in the Southern Great Plains

    SciTech Connect (OSTI)

    Lamb, Peter J.

    2013-06-13

    Scientific Guidance, Research, and Educational Outreach for the ARM Climate Research Facility (ACRF) in the Southern Great Plains

  1. Office of Legacy Management. Information and Records Management. Transition Guidance

    SciTech Connect (OSTI)

    none,

    2004-03-01

    The Office of Legacy Management (LM) is an integral part of the U.S. Department of Energy’s (DOE’s) strategy to ensure that legacy liabilities of former nuclear weapons production sites are properly managed following the completion of environmental cleanup activities. LM will work with each site using an integrated team approach to ensure a successful transition. Part of this process will include transition of Government records and information. The Office of Legacy Management Information and Records Management Transition Guidance focuses on LM’s goal to preserve and protect legacy records and information. This guidance document establishes a framework for the transfer of records management responsibilities for sites transferring to LM. It describes the requirements, responsibilities, and procedures for the efficient and cost-effective transfer of custody, ownership, and management of records and other information products from the transfer site to LM. Records management practices are critical to the functions of Federal agencies because records provide information about, or evidence of, the organization, functions, policies, decisions, procedures, operations, or other activities. Therefore, the information generated by an agency is created, maintained, and dispositioned through records management processes that ensure the appropriate preservation and retrieval of essential information. Because of their intrinsic value, best practices to preserve information and records should be utilized when records are transferred from one organization to another. As the transfer program completes cleanup activities at closure sites, a transitional process will facilitate the transparent shift in the management of site records activities to LM. The roles and responsibilities of the transfer site and/or program and LM described in this document are a necessary foundation for cooperation and coordination and are essential to the successful transition of records and information responsibilities. The DOE Office of the Chief Information Officer (OCIO) has a central role in DOE records management by providing guidance, expertise, and coordination to all DOE offices and organizations and coordination with the National Archives and Records Administration (NARA). LM and the transfer site will complete an integrated transition plan which will integrate all transition elements including information and records. As part of the overall transition plan, an Information and Records Transition Plan will be developed consistent with the integrated transition plan for the site transfer and included as an attachment. The Information and Records Management Transition Plan will be developed to assist both organizations in organizing the tasks; establishing a timetable and milestones for their completion; and identifying manpower, funding and other resources that will be needed to complete the ownership transfer. In addition, the plan will provide a valuable exchange of institutional knowledge that will assist LM in meeting the obligations of responsibly managing legacy records. Guidance for the development of the plan is included in this document. Records management concerns that may arise during site closure, such as management support, contract language and agreements, interactions with the OCIO and NARA, resource and budget considerations, and procedures to safeguard records are addressed. Guidelines and criteria for records management transition activities are also provided. These include LM expectations for the inventory, scheduling, and disposition of records; the management and transfer of electronic files, including databases and software; records finding aids, indices, and recordkeeping systems; and the process for the transfer of hard copy and electronic records to LM.

  2. Guidance for identifying, reporting and tracking nuclear safety noncompliances

    SciTech Connect (OSTI)

    1995-12-01

    This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

  3. SPAR-H Step-by-Step Guidance

    SciTech Connect (OSTI)

    W. J. Galyean; A. M. Whaley; D. L. Kelly; R. L. Boring

    2011-05-01

    This guide provides step-by-step guidance on the use of the SPAR-H method for quantifying Human Failure Events (HFEs). This guide is intended to be used with the worksheets provided in: 'The SPAR-H Human Reliability Analysis Method,' NUREG/CR-6883, dated August 2005. Each step in the process of producing a Human Error Probability (HEP) is discussed. These steps are: Step-1, Categorizing the HFE as Diagnosis and/or Action; Step-2, Rate the Performance Shaping Factors; Step-3, Calculate PSF-Modified HEP; Step-4, Accounting for Dependence, and; Step-5, Minimum Value Cutoff. The discussions on dependence are extensive and include an appendix that describes insights obtained from the psychology literature.

  4. Deep Energy Retrofit Guidance for the Building America Solutions Center

    SciTech Connect (OSTI)

    Less, Brennan; Walker, Iain

    2015-01-01

    The U.S. DOE Building America program has established a research agenda targeting market-relevant strategies to achieve 40% reductions in existing home energy use by 2030. Deep Energy Retrofits (DERs) are part of the strategy to meet and exceed this goal. DERs are projects that create new, valuable assets from existing residences, by bringing homes into alignment with the expectations of the 21st century. Ideally, high energy using, dated homes that are failing to provide adequate modern services to their owners and occupants (e.g., comfortable temperatures, acceptable humidity, clean, healthy), are transformed through comprehensive upgrades to the building envelope, services and miscellaneous loads into next generation high performance homes. These guidance documents provide information to aid in the broader market adoption of DERs.

  5. Questions and answers based on revised 10 CFR Part 20

    SciTech Connect (OSTI)

    Borges, T.; Stafford, R.S.; Lu, P.Y.; Carter, D.

    1994-05-01

    NUREG/CR-6204 is a collection of questions and answers that were originally issued in seven sets and which pertain to revised 10 CFR Part 20. The questions came from both outside and within the NRC. The answers were compiled and provided by NRC staff within the offices of Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, the Office of State Programs, and the five regional offices. Although all of the questions and answers have been reviewed by attorneys in the NRC Office of the General Counsel, they do not constitute official legal interpretations relevant to revised 10 CFR Part 20. The questions and answers do, however, reflect NRC staff decisions and technical options on aspects of the revised 10 CFR Part 20 regulatory requirements. This NUREG is being made available to encourage communication among the public, industry, and NRC staff concerning the major revisions of the NRC`s standards for protection against radiation.

  6. Nuclear Regulatory Commission Information Digest 1992 edition. Volume 4

    SciTech Connect (OSTI)

    Olive, K [ed.] [ed.

    1992-03-01

    The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, the activities NRC licenses, and general information on domestic and worldwide nuclear energy. This digest is a compilation of nuclear- and NRC-related data and is designed to provide a quick reference to major facts about the agency and industry it regulates. In general, the data cover 1975 through 1991, with exceptions noted. Information on generating capacity and average capacity factor for operating US commercial nuclear power reactors is obtained from monthly operating reports that are submitted directly to the NRC by the licensee. This information is reviewed by the NRC for consistency only and no independent validation and/or verification is performed.

  7. A Framework for Evaluating the Effects of Degraded Digital I and C Systems on Human Performance

    SciTech Connect (OSTI)

    OHara,J.; Gunther, B.; Hughes, N.; Barnes, V.

    2009-04-09

    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 situation awareness and performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission has initiated a research project to investigate the effects of degraded I&C systems on human performance and plant operations. The ultimate objective of this project is to develop the technical basis for human factors review guidance for conditions of degraded I&C, including complete failure. Based on the results of this effort, NRC will determine the need for developing new guidance or revising NUREG-0800, NUREG-0711, NUREG-0700 and other pertinent NRC review guidance. This paper reports on the first phase of the research, the development of a framework for linking degraded I&C system conditions to human performance. The framework consists of three levels: I&C subsystems, human-system interfaces, and human performance. Each level is composed of a number of discrete elements. This paper will describe the elements at each level and their integration. In the next phase of the research, the framework will be used to systematically investigate the human performance consequences of various classes of failures.

  8. Nuclear Regulatory Commission issuances, October 1993. Volume 38, No. 4

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    This document contains a Commission issuance in which the Commission denies the petitioners` motion to quash or modify a subpoena issued by the NRC staff in the course of an investigation to determine if the petitioners` have violated NRC regulations and to determine if safety-related problems exist at NRC-licensed facilities. The pertinent regulations and the Commission`s Memorandum and Order are included.

  9. Title list of documents made publicly available, June 1-30, 1997

    SciTech Connect (OSTI)

    1997-08-01

    This document is a monthly publication describing information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, {open_quotes}docketed{close_quotes} does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records.

  10. Requirements, guidance and logic in planning environmental investigations: Approval versus implementation

    SciTech Connect (OSTI)

    Brice, D.A. [3D/Environmental Services, Inc., Cincinnati, OH (United States); Meredith, D.V.; Harris, M.Q. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States). Fernald Environmental Management Project

    1993-09-09

    In today`s litigious society, it is important for both private parties and government to plan and conduct environmental investigations in a scientifically sound manner, documenting the purpose, methods, and results in a consistent fashion throughout the exercise. Planning documents are prepared during the initial phases of environmental investigations. Project objectives, including data quality requirements, specific work to be conducted to fulfill data needs, and operating procedures are specified. Regulatory agency approval of these documents is often required prior to plan implementation. These approvals are necessary and appropriate to fulfilling the agency`s mandated role. Many guidance documents prepared by regulatory agencies suggest the content and format of various scoping documents. These guidances help standardize thought processes and considerations in planning, and provide a template to ensure that both the plan and the proposed work will fulfill regulatory requirements. This work describes the preparation and use of guidance documents for planning environmental studies. The goals and some of the pitfalls of such documents are discussed. Guidance should include the following elements: the purpose of the guidance and a description of where it applies; the type of items to be addressed in planning; identification of requirements are applicable to all projects for which the guidance is intended; identification of requirements only applicable in certain situations; a description of items to facilitate planning; a suggested format for fulfilling requirements; example applications of the guidance. Disagreements arise between planners and reviewers/approvers when elements of guidance are used as leverage to require work not directly related to project objectives. Guidance may be inappropriately used as a milestone by which site-specific plans are judged. Regulatory agency review and approval may be regarded as a primary objective of the plan.

  11. Miscellaneous Waste-Form FEPs

    SciTech Connect (OSTI)

    A. Schenker

    2000-12-08

    The US DOE must provide a reasonable assurance that the performance objectives for the Yucca Mountain Project (YMP) potential radioactive-waste repository can be achieved for a 10,000-year post-closure period. The guidance that mandates this direction is under the provisions of 10 CFR Part 63 and the US Department of Energy's ''Revised Interim Guidance Pending Issuance of New US Nuclear Regulatory Commission (NRC) Regulations (Revision 01, July 22, 1999), for Yucca Mountain, Nevada'' (Dyer 1999 and herein referred to as DOE's Interim Guidance). This assurance must be demonstrated in the form of a performance assessment that: (1) identifies the features, events, and processes (FEPs) that might affect the performance of the potential geologic repository; (2) examines the effects of such FEPs on the performance of the potential geologic repository; (3) estimates the expected annual dose to a specified receptor group; and (4) provides the technical basis for inclusion or exclusion of specific FEPs.

  12. Overview of the Advanced Combustion Engine R&D

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

    for light-duty vehicles for many years, probably decades ..." NRC Report 1 * Advanced engines in conventional, hybrid electric vehicles (HEVs) and plug-in hybrid electric...

  13. Microsoft PowerPoint - NMMSS Role in Preparing a New Facility...

    National Nuclear Security Administration (NNSA)

    to ensure that the U.S. Government deadlines and commitments are met 4 Communication Flow to Define Reporting Requirements Overall direction provided by NRC 5 Louisiana...

  14. SAPHIRE 8 Software Acceptance Test Plan

    SciTech Connect (OSTI)

    Ted S. Wood; Curtis L. Smith

    2009-07-01

    This document describe & report the overall SAPHIRE 8 Software acceptance test paln to offically release the SAPHIRE version 8 software to the NRC custoer for distribution.

  15. Security Rulemaking

    Office of Environmental Management (EM)

    use of material - Mitigate consequences * Orders were issued to NRC licensees that transport: - Spent Nuclear Fuel - IAEA Code of Conduct Category 1 and 2 quantities of...

  16. Microsoft PowerPoint - 7_LAUREN_GIBSON_NMMSS Presentation Gibson...

    National Nuclear Security Administration (NNSA)

    Update: Fukushima Lessons Learned Lauren Gibson, U.S. Nuclear Regulatory Commission Agenda Overview of the Accident NRC Response Identifying Lessons-Learned ...

  17. Halting_Title_XVII_Nuclear_Loan_Guarantees.pdf

    Energy Savers [EERE]

    Department of Energy 1000 Independence Ave., SW Washington, DC 20585 NRC Reveals AP1000 Nuclear Reactor Design Problems, DOE Must Halt Issuance of Conditional Loan Guarantees to...

  18. Prioritizing Climate Change Mitigation Alternatives: Comparing Transportation Technologies to Options in Other Sectors

    E-Print Network [OSTI]

    Lutsey, Nicholas P.

    2008-01-01

    Technology Support Unit (ETSU), 1994. "An Appraisal of UKNRC, 1992; IPCC, 1999; ETSU, 1994; CAEP, 1995; DCAD, 1997;Baseline NRC, 1992 IPCC, 1999 ETSU, 1994 (low) ETSU, 1994 (

  19. Estimating the Benefits of Government-Sponsored Energy R&D: Synthesis of Conference Discussions

    SciTech Connect (OSTI)

    Lee, R.

    2003-11-14

    In 2001, a National Research Council (NRC) committee conducted a retrospective study of the benefits of some of the energy efficiency and fossil energy programs in the U.S. Department of Energy (DOE). As part of its study, the NRC committee developed a methodological framework for estimating these benefits. Following the NRC report, a conference was organized by Oak Ridge National Laboratory to discuss ways of adapting and refining the NRC framework for possible use by DOE offices to help plan and manage their R&D. This report is a synthesis of the discussions at the conference.

  20. Impacts of Maternal Obesity on Metabolic Profiles in Postpartum Ewes 

    E-Print Network [OSTI]

    McKnight, Jason Ray

    2011-10-21

    .01 0.25 0.21 NRC nutrient requirements (control group) and 24 ewes had free access to feed (obesity induction). Beginning on day 42 of gestation...