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Sample records for regulatory commission safety

  1. Regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning

    International Nuclear Information System (INIS)

    Lipar, M.

    1997-01-01

    A review of regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning is given. It contains licensing steps in Slovakia during commissioning; Status and methodology of Mochovce safety analysis report; Mochovce NPP safety enhancement program; Regulatory body policy towards Mochovce NPP safety enhancement; Recent development in Mochovce pre-operational safety enhancement program review and assessment process; Licensing steps in Slovakia during commissioning

  2. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  3. Canada's regulatory framework: The Canadian Nuclear Safety Commission's regulatory framework

    International Nuclear Information System (INIS)

    Howard, D.

    2011-01-01

    This paper will discuss the Canadian Nuclear Safety Commission and Canada's Regulatory Framework with respect to Low- and Intermediate-Level Radioactive Waste. The management of low and intermediate level radioactive waste must be ensured in a consistent, environmentally responsible and economical manner throughout its lifecycle -- from its production to the final disposal option. Radioactive waste has been produced in Canada since the early 1930s when the first radium/uranium mine began operating at Port Radium in the Northwest Territories. Pitchblende ore was transported from the Port Radium mine to Port Hope, Ontario where it was refined to produce radium for medical purposes. At present, radioactive waste is generated in Canada from the various stages and uses associated with the nuclear fuel cycle from uranium mining/milling to nuclear reactor operations to radioisotope manufacture and use. The Canadian Nuclear Safety Commission (CNSC regulates the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; and to implement Canada's international commitments on the peaceful use of nuclear energy. The CNSC was established in 2000 under the Nuclear Safety and Control Act and reports to Parliament through the Minister of Natural Resources. The CNSC was created to replace the former Atomic Energy Control Board (AECB), which was founded in 1946. Under the Nuclear Safety and Control Act, CNSC's mandate involves four major areas: regulation of the development, production and use of nuclear energy in Canada to protect health, safety and the environment; regulation of the production, possession, use and transport of nuclear substances, and the production, possession and use of prescribed equipment and prescribed information; implementation of measures respecting international control of the development, production, transport and use of nuclear energy and substances, including measures respecting the

  4. 75 FR 52046 - Development of U.S. Nuclear Regulatory Commission Safety Culture Policy Statement: Public Meeting

    Science.gov (United States)

    2010-08-24

    ... is working towards increasing the attention that is given to safety culture as part of its efforts to... NUCLEAR REGULATORY COMMISSION Development of U.S. Nuclear Regulatory Commission Safety Culture..., Nevada hearing facility to solicit comments on the revision of its draft safety culture policy statement...

  5. U.S. Nuclear Regulatory Commission Safety Culture Oversight

    International Nuclear Information System (INIS)

    Sieracki, D. J.

    2016-01-01

    The NRC recognises that it is important for all organizations performing or overseeing regulated activities to establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The NRC’s approach to safety culture is based on the premise that licencees bear the primary responsibility for safety. The NRC provides oversight of safety culture through expectations detailed in policy statements, safety culture assessor training for NRC inspectors, the oversight process, and the Allegations and Enforcement Programs. The NRC’s Safety Culture Policy Statement (SCPS) sets forth the Commission’s expectation that individuals and organizations establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The SCPS is not a regulation. It applies to all licencees, certificate holders, permit holders, authorisation holders, holders of quality assurance program approvals, vendors and suppliers of safety-related components, and applicants for a licence, certificate, permit, authorisation, or quality assurance program approval, subject to NRC authority.

  6. Reactor safety: a discussion by officials of the Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Anders, W.A.; Rusche, B.C.; Stello, V. Jr.; Minogue, R.B.

    1976-01-01

    William A. Anders, Chairman of the Nuclear Regulatory Commission (NRC), and several senior officials spoke to the Joint Committee on Atomic Energy on the subject of nuclear safety, improvements in reactor plant safety, and quality assurance. The NRC, during its first year of organization, has developed new initiatives to improve safety and safeguards regulations. Anders stressed that NRC is not stifling internal discussion of opposing views, that it has been honest with the public, and that operating reactors are meeting rigorous safety standards. Other speakers discussed comparative safety of old and new reactors. Backfitting of older plants with new features is done when substantial safety protection can be added, but detuning an integrated system is not done indiscriminately. Officials of NRC do not agree with former General Electric employees, who testified that the regulatory procedure is inadequate. Safety improvements since August 28, 1962 and outlines of the review process are included in the Appendixes

  7. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1992-01-01

    This is the thirty-sixth volume of issuances (1-396) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. It covers the period from July 1, 1992-December 31, 1992. Atomic Safety and Licensing Boards are authorized by Section 191 of the Atomic Energy Act of 1954. These Boards, comprised of three members conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. Boards are drawn from the Atomic Safety and Licensing Board Panel, comprised of lawyers, nuclear physicists and engineers, environmentalists, chemists, and economists. The Atomic Energy Commission first established Licensing Boards in 1962 and the Panel in 1967

  8. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  9. Regulatory Commission of Alaska

    Science.gov (United States)

    Map Help Regulatory Commission of Alaska Login Forgot Password Arrow Image Forgot password? View Cart login Procedures for Requesting Login For Consumers General Information Telephone Electric Natural Gas

  10. The U.S. Nuclear Regulatory Commission seismic safety research program

    International Nuclear Information System (INIS)

    Kenneally, R.M.; Guzy, D.J.; Murphy, A.J.

    1988-01-01

    The seismic safety research program sponsored by the U.S. Nuclear Regulatory Commission is directed toward improving the evaluation of potential earthquake effects on nuclear power plant operations. The research has been divided into three major program areas: earth sciences, seismic design margins, and fragilities and response. A major thrust of this research is to assess plant behavior for seismic events more severe and less probable than those considered in design. However, there is also research aimed at improving the evaluation of earthquake input and plant response at plant design levels

  11. Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1983. Report to the Congress

    International Nuclear Information System (INIS)

    1982-02-01

    Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1983. The report contains a number of comments and recommendations

  12. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank

    International Nuclear Information System (INIS)

    Scofield, N.R.; Hardy, H.A.; Laats, E.T.

    1983-02-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water safety research programs. Local direction of the program is provided by E G and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data that is to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the NRC. The NRC/DAE Data Bank and the capabilities of the data access software are described

  13. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank. Revision 3

    International Nuclear Information System (INIS)

    Hardy, H.A.; Laats, E.T.

    1985-03-01

    The United States Nuclear Regulatory Commission (USNRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the USNRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

  14. The Canadian Nuclear Safety Commission regulatory process for decommissioning a uranium mining facility

    International Nuclear Information System (INIS)

    Scissons, K.; Schryer, D.M.; Goulden, W.; Natomagan, C.

    2002-01-01

    The Canadian Nuclear Safety Commission (CNSC) regulates uranium mining in Canada. The CNSC regulatory process requires that a licence applicant plan for and commit to future decommissioning before irrevocable decisions are made, and throughout the life of a uranium mine. These requirements include conceptual decommissioning plans and the provision of financial assurances to ensure the availability of funds for decommissioning activities. When an application for decommissioning is submitted to the CNSC, an environmental assessment is required prior to initiating the licensing process. A case study is presented for COGEMA Resources Inc. (COGEMA), who is entering the decommissioning phase with the CNSC for the Cluff Lake uranium mine. As part of the licensing process, CNSC multidisciplinary staff assesses the decommissioning plan, associated costs, and the environmental assessment. When the CNSC is satisfied that all of its requirements are met, a decommissioning licence may be issued. (author)

  15. Yellin's review of the Nuclear Regulatory Commission's Reactor Safety Study: comment

    International Nuclear Information System (INIS)

    Wilson, R.

    1976-01-01

    Joel Yellin (Bell J. Economics, Vol. 7, No. 1 (Spr. 1976)) reviewed the Reactor Safety Study (WASH-1400, or Rasmussen Report) published by the Nuclear Regulatory Commission and makes several criticisms. Wilson finds that some of these criticisms are much overstated, while others, although valid, are mainly criticisms of presentation. To be useful for public policy, reactor risks--and indeed all nuclear risks--must be compared with other risks society faces. Wilson feels that the Rasmussen Report is weak in these comparisons, primarily because there exist few estimates of risk in other places, but that the comparisons he does make indeed confirm that the risk is smaller than Yellin suggests. 20 references

  16. Regulation of chemical safety at fuel cycle facilities by the United States Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Ramsey, Kevin M.

    2013-01-01

    When the U.S. Nuclear Regulatory Commission (NRC) was established in 1975, its regulations were based on radiation dose limits. Chemical hazards rarely influenced NRC regulations. After the Three Mile Island reactor accident in 1979, the NRC staff was directed to address emergency planning at non-reactor facilities. Several fuel cycle facilities were ordered to submit emergency plans consistent with reactor emergency plans because no other guidance was available. NRC published a notice that it was writing regulations to codify the requirements in the Orders and upgrade the emergency plans to address all hazards, including chemical hazards. The legal authority of NRC to regulate chemical safety was questioned. In 1986, an overfilled uranium hexafluoride cylinder ruptured and killed a worker. The NRC staff was directed to address emergency planning for hazardous chemicals in its regulations. The final rule included a requirement for fuel cycle facilities to certify compliance with legislation requiring local authorities to establish emergency plans for hazardous chemicals. As with emergency planning, NRC's authority to regulate chemical safety during routine operations was limited. NRC established memoranda of understanding (MOUs) with other regulatory agencies to encourage exchange of information between the agencies regarding occupational hazards. In 2000, NRC published new, performance-based, regulations for fuel cycle facilities. The new regulations required an integrated safety analysis (ISA) which used quantitative standards to assess chemical exposures. Some unique chemical exposure cases were addressed while implementing the new regulations. In addition, some gaps remain in the regulation of hazardous chemicals at fuel cycle facilities. The status of ongoing efforts to improve regulation of chemical safety at fuel cycle facilities is discussed. (authors)

  17. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1981-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission Issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  19. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1993-08-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors; Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1992-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1994-03-01

    This report includes the issuances received during the specified period from Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1996-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This report includes the issuances received during the specified period from Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  6. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-11-01

    This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1994-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission Issuance

    International Nuclear Information System (INIS)

    1994-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1994-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. The Cold War legacy of regulatory risk analysis: The Atomic Energy Commission and radiation safety

    Science.gov (United States)

    Boland, Joseph B.

    From its inception in 1946 the Atomic Energy Commission pioneered the use of risk analysis as a mode of regulatory rationality and political rhetoric, yet historical treatments of risk analysis nearly always overlook the important role it played in the administration of atomic energy during the early Cold War. How this absence from history has been achieved and why it characterizes most historical accounts are the subjects of Chapter II. From there, this study goes on to develop the thesis that the advent of the atomic bomb was a world-shattering event that forced the Truman administration to choose between two novel alternatives: (1) movement towards global governance based initially on cooperative control of atomic energy or (2) unsparing pursuit of nuclear superiority. I refer to these as nuclear internationalism and nuclear nationalism, respectively. Each defined a social risk hierarchy. With the triumph of nuclear nationalism, nuclear annihilation was designated the greatest risk and a strong nuclear defense the primary means of prevention. The AEC's mission in the 1950s consisted of the rapid development of a nuclear arsenal, continual improvements in weapons technologies, and the promotion of nuclear power. The agency developed a risk-based regulatory framework through its dominant position within the National Committee on Radiation Protection. It embraced a technocratic model of risk analysis whose articulation and application it controlled, largely in secret. It used this to undergird a public rhetoric of reassurance and risk minimization. In practice, safety officials adjusted exposure levels within often wide parameters and with considerable fluidity in order to prevent safety concerns from interfering with operations. Secrecy, the political climate of the time, and a lack of accountability enabled the agency to meld technical assessments with social value judgments in a manner reflective of nuclear nationalism's risk hierarchy. In the late fifties

  12. Nuclear regulatory commission issuances

    International Nuclear Information System (INIS)

    1989-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

  14. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1986-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Danials of Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1987-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1981-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

  3. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1987-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear regulatory commission issuances

    International Nuclear Information System (INIS)

    1990-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1986-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-01-01

    This report includes the issuance received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1988-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-06-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1987-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

  17. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety And Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1985-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission Issuances, November 1980

    International Nuclear Information System (INIS)

    1980-11-01

    Contents: Issuances of the Nuclear Regulatory Commission; Issuances of the Atomic Safety and Licensing Appeal Boards; Issuances of the Atomic Safety and Licensing Boards; and Issuances of the Directors Denial

  3. Nuclear Regulatory Commission Issuances, December 1980

    International Nuclear Information System (INIS)

    1980-12-01

    Contents: Issuances of the Nuclear Regulatory Commission; Issuances of the Atomic Safety and Licensing Appeal Boards; Issuances of the Atomic Safety and Licensing Boards; and Issuances of the Directors Denial

  4. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

  5. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety nd Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  6. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1994-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  7. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1997-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  8. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1997-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  9. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

  10. NRC [Nuclear Regulatory Commission] safety research in support of regulation, 1987

    International Nuclear Information System (INIS)

    1988-05-01

    This report, the third in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1987. The goal of this office is to ensure that research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  11. Nuclear Regulatory Commission information digest

    International Nuclear Information System (INIS)

    1990-03-01

    The Nuclear Regulatory Commission information digest provides summary information regarding the US Nuclear Regulatory Commission, its regulatory responsibilities, and areas licensed by the commission. This is an annual publication for the general use of the NRC Staff and is available to the public. The digest is divided into two parts: the first presents an overview of the US Nuclear Regulatory Commission and the second provides data on NRC commercial nuclear reactor licensees and commercial nuclear power reactors worldwide

  12. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1996-04-01

    This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services

  13. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services.

  14. U.S. Nuclear Regulatory Commission nuclear safety assistance to the CEE and NIS countries

    International Nuclear Information System (INIS)

    Blaha, J.

    2001-01-01

    NRC participates in bilateral and multilateral efforts to strengthen the regulatory authorities of countries in which Soviet design NPPs are operated. Countries involved are the New Independent States of the Soviet Union (Armenia, Kazakhstan, Russia and Ukraine) and of Central and Eastern Europe (Bulgaria, Czech Republic, Hungary, Lithuania and Slovak Republic). NRC's goal is to see that its counterparts receive the basic tools, knowledge and understanding needed to exercise effective regulatory oversight, consistent with internationally accepted norms and standards. The bilateral assistance started in 1991. $44 mill. are provided to the countries. The multilateral activities NRC participates in include: H-7 Nuclear Safety Working Group, EBRD - Administered Nuclear Safety Account and Chernobyl Sarcophagus Fund and IAEA

  15. Review and evaluation of the Nuclear Regulatory Commission Safety Research Program for Fiscal Years 1984 and 1985

    International Nuclear Information System (INIS)

    1983-02-01

    This is the sixth report by the Advisory Committee on Reactor Safeguards (ACRS) that has been prepared in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. Part I is a compilation of our general comments and recommendations regarding the NRC Safety Research Program, and includes budget recommendations and an identification of matters of special importance that deserve increased emphasis. It is intended to serve as an Executive Summary. Part II is divided into ten chapters, each of which represents a Decision Unit of the NRC research program. In each chapter, specific comments are included on the research involved in the Decision Unit, an assessment of priorities, and recommendations regarding new directions and levels of funding

  16. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  17. Fuel Receiving and Storage Station. Nuclear Regulatory Commission's safety evaluation report

    International Nuclear Information System (INIS)

    1976-01-01

    The safety evaluation report covers design of structures, components, equipment, and systems; nuclear criticality safety; radiological safety; accident analysis; conduct of operations; quality assurance; common defense and security; financial qualifications; financial protection and indemnity requirements; and technical specifications

  18. 75 FR 11166 - Joint Meeting of the Nuclear Regulatory Commission and the Federal Energy Regulatory Commission...

    Science.gov (United States)

    2010-03-10

    ... the Nuclear Regulatory Commission and the Federal Energy Regulatory Commission; Notice of Joint Meeting of the Nuclear Regulatory Commission and the Federal Energy Regulatory Commission March 2, 2010. The Federal Energy Regulatory Commission (FERC) and the Nuclear Regulatory Commission (NRC) will hold...

  19. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan

  20. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1996-05-01

    This report contains the issuances received during the specified period from the Atomic Safety and Licensing Board only. The two issuances included relate to: (1) suspension of byproduct material license for Eastern Testing and Inspection, Inc., and (2) license renewal for the Georgia Tech research reactor

  1. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 3, presents papers on: Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive light water researchers; Thermal Hydraulics; and Earth sciences. The individual papers have been cataloged separately

  2. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 2, presents papers on: Severe accident research; Severe accident and policy implementation; and Accident management. The individual papers have been cataloged separately

  3. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank

    International Nuclear Information System (INIS)

    Scofield, N.R.; Hardy, H.A.; Laats, E.T.

    1984-03-01

    The United States NRC has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data that is to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the NRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

  4. Assessment of operational safety data in the Nuclear Regulatory Commission (NRC)

    International Nuclear Information System (INIS)

    Michelson, C.; Heltemes, C.J.

    1981-01-01

    The collection, assessment, and dissemination of operational safety data, including the Licensee Event Reports (LERs) is the principal activity of the NRC's Office for Analysis and Evaluation of Operational Data (AEOD). This office was recently formed to provide a dedication to this activity. It has been staffed and fully operational since April 1980. The office programs are evolving and include some new ideas and techniques to aid in the assessment of LERs. For example, the office is managing the development of a computer-based Sequence Coding and Search (SCS) procedure which will have the capability to store and retrieve the detail and individual sequences associated with each LER. Such events may be rather complex and involve a number of isolated or unrelated happenings associated with multiple systems and components with various causes, failure modes, and failure effects. Thus, the SCS system is particularly useful because it documents in a computer-retrievable form not only the principal occurrence, but also related component and system responses which precede, accompany, follow, or result from the principal occurrence. Also noteworthy is the Power Reactor Watch List which is being developed and monitored as a part of the AEOD program

  5. Safety Commission databases support

    CERN Document Server

    Petit, S; CERN. Geneva. TS Department

    2005-01-01

    A collaboration project between the Safety Commission (SC) and the Controls, Safety and Engineering databases group (TS/CSE) started last year. The aim of this collaboration is to transfer several SC applications from their local environments onto the D7i-MTF EDMS framework, for which the TS/CSE group is responsible. Different domains of activity and projects have been defined in the areas of equipment management, safety inspections, accidents and risks management. Priorities have been established in collaboration with SC. This paper presents the new Safety Inspections Management system (SIM) which will be put in production before the summer 2005 and reviews the constraints of both the users and the development and operational framework that needed to be taken into account. The technical solutions adopted to assure a successful production start-up and operation of the SIM system are described. Progress on other on-going projects and plans for the next year are also reported.

  6. Nuclear Regulatory Commission 1989 Information Digest

    International Nuclear Information System (INIS)

    1989-03-01

    The Nuclear Regulatory Commission 1989 Information Digest provides summary information regarding the US Nuclear Regulatory Commission, its regulatory responsibilities, and areas licensed by the Commission. This is the first of an annual publication for the general use of the NRC staff and is available to the public. The Digest is divided into two parts: the first presents an overview of the US Nuclear Regulatory Commission and the second provides data on NRC commercial nuclear reactor licensees and commercial nuclear power reactors worldwide

  7. Nuclear Regulatory Commission issuances, March 1975

    International Nuclear Information System (INIS)

    1975-04-01

    Reactor licensing actions taken by the Nuclear Regulatory Commission, the Atomic Safety and Licensing Appeal Board and the Atomic Safety and Licensing Boards for March 1975 are presented. Action was included for the following reactors: Big Rock Point Nuclear Plant; West Valley Reprocessing Plant; Limerick Generating Station, Units 1 and 2; Midland Plants, Units 1 and 2; Wolf Creek Generating Station, Unit 1; Monticello Nuclear Generating Plant, Unit 1; Douglas Point Nuclear Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Vermont Yankee Nuclear Power Station; and WPPSS Hanford Units 1 and 4. (U.S.)

  8. Arrangement between the US Nuclear Regulatory Commission (USNRC) and the Belgian Government for Exchange of Technical Information in Regulatory Matters and in Cooperation in Safety Research and in Standards Development

    International Nuclear Information System (INIS)

    1978-01-01

    This Arrangement was concluded on 6 June 1978 between the United States Nuclear Regulatory Commission and the Belgian Government for exchange of technical information in regulatory matters and in co-operation in safety research and in standards development. Both Parties agree to exchange, as available, technical information related to the regulation of safety and the environmental impact of designated nuclear energy facilities and to safety research of designated types of nuclear facilities. As regards co-operation in safety research, the execution of joint programmes and projects under which activities are divided between the two Parties will be agreed on a case by case basis. The Parties further agree to co-operate in the development of regulatory standards applicable to the designated nuclear facilities. The Arrangement is valid for 5 years and may be extended. (NEA) [fr

  9. Federal Energy Regulatory Commission (FERC) Regions

    Data.gov (United States)

    Department of Homeland Security — Federal Energy Regulatory Commission (FERC) Regions. FERC is an independent agency that regulates the interstate transmission of electricity, natural gas, and oil....

  10. Nuclear Regulatory Commission issuances, May 1993

    International Nuclear Information System (INIS)

    1993-05-01

    This report contains the issuances received during the specified period (May 1993) from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not deemed a part of these opinions or have any independent legal significance. Contents of this document include an Issuance of the Nuclear Regulatory Commission with respect to the Sacramento Municipal Utility District and Issuances of Directors' Decisions concerning the Interstate Nuclear Service Corporation; Niagara Mohawk Power Corporation; and Texas Utilities Electric Company, et al. and All Nuclear Power Plants with Thermo-Lag Fire Barriers

  11. Nuclear Regulatory Commission issuances: August 1994. Volume 40, Number 2

    International Nuclear Information System (INIS)

    1994-08-01

    This report contains the collected issuances of the US Nuclear Regulatory Commission for the month of August, 1994. The report includes issuances of the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Some of the entities involved include Gulf States Utility company, Sequoyah Fuels Corporation and General Atomics, Georgia Power Company, and Arizona Public Service Company

  12. Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

    International Nuclear Information System (INIS)

    1995-09-01

    This book contains an issuance of the Atomic Safety and Licensing Board and a Director's Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director's Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant

  13. Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This book contains an issuance of the Atomic Safety and Licensing Board and a Director`s Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director`s Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant.

  14. Nuclear Regulatory Commission: more aggressive leadership needed

    International Nuclear Information System (INIS)

    Staats, E.B.

    1980-01-01

    The Energy Reorganization Act of 1974 which established the Nuclear Regulatory Commission required GAO to evaluate the Commission's performance by January 18, 1980. This report responds to that requirement. GAO concluded that, although improvements have been made, the Commission's nuclear regulatory performance can be characterized best as slow, indecisive, cautious - in a word, complacent. This has largely resulted from a lack of aggressive leadership as evidenced by the Commissioners' failure to establish regulatory goals, control policymaking, and most importantly, clearly define their roles in nuclear regulation

  15. Nuclear Regulatory Commission issuances, May 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Appeal Boards, the Atomic Safety and Licensing Boards, the Administrative Law Judge, the Directors' Decision, and the Denials of Petitions for Rulemaking

  16. Nuclear Regulatory Commission Issuances, August 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Contents include: Issuances of the Nuclear Regulatory Commission--Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit 1), Westinghouse Electric Corp. (Export of LEU to the Philippines); Issuances of Atomic Safety and Licensing Appeal Boards--Duke Power Company (Amendment to Materials License SNM-1773--Transportation of Spent Fuel from Oconee Nuclear Station for Storage at McGuire Nuclear Station); Issuances of the Atomic Safety Licensing Boards--Commonwealth Edison Company (Byron Station, Units 1 and 2), Dairyland Power Cooperative (La Crosse Boiling Water Reactor, Operating License and Show Cause), Florida Power and Light Company (St. Lucie Plant, Unit No. 2), Florida Power and Light Company (Turkey Point Nuclear Generating, Units 3 and 4), Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit 1) Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), The Regents of the University of California (UCLA Research Reactor), The Toledo Edison Company, et al. (Davis-Besse Nuclear Power Station, Units 2 and 3: Terminiation of Proceedings); Issuances of the Directors Denial--Florida Power and Light Company

  17. Nuclear Regulatory Commission Issuances, September 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Contents include: Issuances of the Nuclear Regulatory Commission--Commonwealth Edison Company (Dresden Nuclear Power Station, Unit 1), Consolidated Edison Company of New York (Indian Point, Unit 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit 1), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Power Authority of the State of New York (Indian Point, Unit 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2); Issuances of Atomic Safety and Licensing Appeal Boards--Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Philadelphia Electric Company, et al. (Peach Bottom Atomic Power Statin, Units 2 and 3), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Statin, Unit No. 2), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2), The Toledo Edison Company, et al. (Davis-Besse Nuclear Power Station, Units 2 and 3); Issuances of the Atomic Safety Licensing Boards--Cleveland Electric Illuminating Company, et al. (Perry Nuclear Power Plant, Units 1 and 2), Commonwealth Edison Company (Dresden Station, Units 2 and 3), Houston Lighting and Power Company (Allens Creek Nuclear Generating Station, Unit 1), Southern California Edison Company, et al. (San Onofre Nuclear Generating Station, Units 2 and 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2), Texas Utilities Generating Company, et al

  18. Commissioning of research reactors. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

  19. Indexes to Nuclear Regulatory Commission issuances, January--March 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    This document provides digests and indexes for issuances of the Nuclear Regulatory Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors Decisions, and the Decisions on Petitions for Rulemaking. These indexes and digests are intended to serve as a guide to the issuances.

  20. Indexes to Nuclear Regulatory Commission issuances, January--March 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This document provides digests and indexes for issuances of the Nuclear Regulatory Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors Decisions, and the Decisions on Petitions for Rulemaking. These indexes and digests are intended to serve as a guide to the issuances

  1. Nuclear Regulatory Commission issuances, October 1993

    International Nuclear Information System (INIS)

    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

  2. 78 FR 44165 - Nuclear Regulatory Commission Enforcement Policy

    Science.gov (United States)

    2013-07-23

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0159] Nuclear Regulatory Commission Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Enforcement policy; request for comment. SUMMARY: The U.S... Policy. In SRM-SECY-12-0047, ``Revisions to the Nuclear Regulatory Commission Enforcement Policy,'' dated...

  3. Nuclear Regulatory Commission issuances, January 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Defense (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances, May 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, July 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances, June 1992

    International Nuclear Information System (INIS)

    1992-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission issuances, April 1994

    International Nuclear Information System (INIS)

    1994-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances, December 1991

    International Nuclear Information System (INIS)

    1991-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances, December 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances, December 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances, September 1992

    International Nuclear Information System (INIS)

    1992-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances, February 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances, March 1993

    International Nuclear Information System (INIS)

    1993-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances, July 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances, August 1992

    International Nuclear Information System (INIS)

    1992-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances, August 1991

    International Nuclear Information System (INIS)

    1991-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances, February 1993

    International Nuclear Information System (INIS)

    1993-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances, November 1992

    International Nuclear Information System (INIS)

    1992-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances, April 1993

    International Nuclear Information System (INIS)

    1993-04-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission's dispositions

    International Nuclear Information System (INIS)

    Watanabe, Norio; Suzudo, Tomoaki

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission's (USNRC's) responses to the recommendations made by the NRC's study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC's dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  1. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

  2. Nuclear Regulatory Commission Staff practice and procedure digest. Commission, Appeal Board and Licensing Board Decision, July 1972 - June 1995

    International Nuclear Information System (INIS)

    1996-04-01

    This is the seventh edition of the Nuclear Regulatory Commission (NRC) Staff Practice and Procedure Digest. It contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 1995 interpreting the NRC rules of practice in 10 CFR part 2

  3. Nuclear Regulatory Commission issuances, April 1989

    International Nuclear Information System (INIS)

    1989-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances, July 1989

    International Nuclear Information System (INIS)

    1989-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, March 1989

    International Nuclear Information System (INIS)

    1989-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances, August 1990

    International Nuclear Information System (INIS)

    1990-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission issuances, December 1989

    International Nuclear Information System (INIS)

    1989-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances, May 1989

    International Nuclear Information System (INIS)

    1989-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances, September 1987

    International Nuclear Information System (INIS)

    1987-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances, May 1990

    International Nuclear Information System (INIS)

    1990-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances, May 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances, July 1988

    International Nuclear Information System (INIS)

    1988-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission Issuances, October 1986

    International Nuclear Information System (INIS)

    1986-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances, February 1989

    International Nuclear Information System (INIS)

    1989-02-01

    This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances, June 1987

    International Nuclear Information System (INIS)

    1987-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decision (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances, October 1989

    International Nuclear Information System (INIS)

    1989-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances, December 1990

    International Nuclear Information System (INIS)

    1990-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances, April 1991

    International Nuclear Information System (INIS)

    1991-04-01

    This report includes the issuances received during the specified period (April 1991) from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances, April 1987

    International Nuclear Information System (INIS)

    1987-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission Issuances, August 1986

    International Nuclear Information System (INIS)

    1986-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances, November 1988

    International Nuclear Information System (INIS)

    1988-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission Issuances, March 1990

    International Nuclear Information System (INIS)

    1990-01-01

    The report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances, November 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances, June 1990

    International Nuclear Information System (INIS)

    1990-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, February 1985

    International Nuclear Information System (INIS)

    1985-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances, November 1990

    International Nuclear Information System (INIS)

    1990-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission Information Digest 1992 edition

    International Nuclear Information System (INIS)

    Olive, K.

    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

  8. Nuclear Regulatory Commission Information Digest, 1991 edition

    International Nuclear Information System (INIS)

    Olive, K.L.

    1991-03-01

    The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, and the areas NRC licenses. This digest is a compilation of NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1990, with exceptions noted. For operating US commercial nuclear power reactors, information on generating capacity and average capacity factor is obtained from Monthly Operating Reports submitted to the NRC directly by the licensee. This information is reviewed for consistency only. No independent validation and/or verification is performed by the NRC. For detailed and complete information about tables and figures, refer to the source publications. This digest is published annually for the general use of the NRC staff and is available to the public. 30 figs., 12 tabs

  9. Nuclear Regulatory Commission Issuances, May 81

    International Nuclear Information System (INIS)

    1981-05-01

    Contents: Issuances of the Nuclear Regulatory Commission--Consolidated Edison Company of New York, Inc. (Indian Point, Unit No. 2), Power Authority of the State of New York (Indian Point, No. 3 Nuclear Power Plant), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Statement of Policy on Conduct of Licensing Proceedings, Uranium Mill Licensing Requirements; Issuances of Atomic Safety and Licensing Appeal Boards--Houston Lighting and Power Company, et al. (South Texas Project, Units 1 and 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit No. 2), Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (Susquehanna Steam Electric Station, Units 1 and 2), Philadelphia Electric Company et al. (Peach Bottom Atomic Power Station, Units 2 and 3), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2); Issuances of the Atomic Safety and Licensing Boards--Duke Power Company (William B. McGuire Nuclear Station, Units 1 and 2), Florida Light and Power Company (Turkey Point Nuclear Generating, Units 3 and 4), Illinois Power Company, et al. (Clinton Power Station, Units 1 and 2), Sacramento Municipal Utility District (Rancho Seco Nuclear Generating Station); Issuances of the Directors Denial--Commonwealth Edison Company (Byron Station, Units 1 and 2), Consolidated Edison Company of New York, Inc. (Indian Point Unit No. 2), Gulf States Utilities Company (River Bend Station Units 1 and 2), Petition to Suspend All Operating Licenses for Pressurized Water Reactors (River Bend Station Units 1 and 2), Portland General Electric Company (Trojan Nuclear

  10. Nuclear Regulatory Commission Information Digest: 1993 edition

    International Nuclear Information System (INIS)

    1993-03-01

    The Nuclear Regulatory Commission Information Digest (digest) provides a summary of information about the U.S. Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, the activities NRC licenses, and general information on domestic and worldwide nuclear energy. The digest, published annually, is a compilation of nuclear- and NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1992, with exceptions noted. Information on generating capacity and average capacity factor for operating U.S. 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. Comments and/or suggestions on the data presented are welcomed and should be directed to Karen Olive, United States Nuclear Regulatory Commission, Office of the Controller, Division of Budget and Analysis, Washington, D.C. 20555. For detailed and complete information about tables and figures, refer to the source publications

  11. 1992 Nuclear Regulatory Commission Annual Report

    International Nuclear Information System (INIS)

    1993-01-01

    This is the 18th annual report of the US Nuclear Regulatory Commission (NRC), covering events and activities occurring in fiscal year 1992 (the year ending September 30, 1992), with some treatment of events from the last quarter of calendar year 1992. The NRC was created by enactment in the Congress of the Energy Reorganization Act of 1974. It is an independent agency of the Federal Government. The five NRC Commissioners are nominated by the President and confirmed by the United States Senate. The Chairman of the Commission is appointed by the President from among the Commissioners confirmed

  12. H.R. 5448: a bill to amend the Atomic Energy Act of 1954, as amended, to reorganize the functions of the Nuclear Regulatory Commission by abolishing the Commission and in its place establishing the Nuclear Regulation and Safety Agency. Introduced in the House of Representatives, Ninety-Ninth Congress, Second Session, August 15, 1986

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The Omnibus Nuclear Safety Act of 1986 amends the Atomic Energy Act of 1954 by replacing the Nuclear Regulatory Commission with a new entity, the Nuclear Regulation and Safety Agency. The purposes are to promote an energy policy that is better coordinated and more consistent with the protection of public health and safety. The new agency would also expedite licensing for construction and operation of nuclear power plants by using pre-approved standardized designs and sites

  13. Canadian Nuclear Safety Commission's intern program

    International Nuclear Information System (INIS)

    Gilmour, P.E.

    2002-01-01

    The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

  14. Nuclear Regulatory Commission issuances, September 1988

    International Nuclear Information System (INIS)

    1988-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

  15. Law of the Energy Regulatory Commission

    International Nuclear Information System (INIS)

    1995-01-01

    This Decree-Law consist of three chapters each on divided in articles and subsections and came into force in November 1 st., 1995. Chapter I, with the heading 'Nature and Powers', defines the Energy Regulatory Commission as a decentralized organ of the Energy Secretariat with technical and operative autonomy in terms of the law, and establish the conditions for the sell, generation, exportation and importation of electricity with destination to particular and public services. The sell transport, storage and distribution of natural gas, as well as the gas liquefied from petroleum are also considered. Chapter II with the heading 'Organization and duties' establish that the Commission is integrated by five Committee, the President included. The Committee members will deliberate in collegiate manner and the decisions are by majority, having the President a vote of quality. Chapter III for 'General provisions' is related to the lawsuits arises between the Commission and the users of services. (Author)

  16. Nuclear Regulatory Commission issuances, January 1997. Volume 45, Number 1

    International Nuclear Information System (INIS)

    1997-01-01

    This book contains issuances of the Atomic Safety and Licensing Board, Nuclear Regulatory Commission and Director's Decision for January 1997. The issuances concern Sequoyah Fuels Corporation and General Atomics Gore, Oklahoma Site decontamination and decommissioning funding; Louisiana Energy Services, Claiborne Enrichment Center denies appeal to review emergency planning; General Public Utilities Nuclear Corporation, Oyster Creek Nuclear Generating station, challenges to technical specifications concerning spent fuel pool; and Consumers Power Company, Palisades Nuclear Plant dry cask storage of spent nuclear fuel

  17. Indexes to Nuclear Regulatory Commission issuances, July--September 1997

    International Nuclear Information System (INIS)

    1998-01-01

    This digest and index lists the Nuclear Regulatory Commission (NRC) issuances for July to September 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. There are five sections to this index: (1) case name index, (2) headers and digests, (3) legal citations index, (4) subject index, and (5) facility index. The digest provides a brief narrative of the issue, including the resolution of the issue and any legal references used for resolution

  18. Indexes to Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1996-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and licensing Board Panel (LBP), the Administrative Law Judges (ALJ) the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Headers and Digests; Legal Citations Index; Subject Index; and Facility Index

  19. Indexes to Nuclear Regulatory Commission Issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and licensing Board Panel (LBP), the Administrative Law Judges (ALJ) the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Headers and Digests; Legal Citations Index; Subject Index; and Facility Index.

  20. Nuclear Regulatory Commission: 1981 annual report

    International Nuclear Information System (INIS)

    1981-01-01

    This seventh annual report of the US Nuclear Regulatory Commission covers major actions, events and planning that occurred during fiscal year 1981, with some coverage of later events, where appropriate. Chapters of the report address the agency's various functions or areas of activity: regulating nuclear power plants; evaluating reactor operating experience; licensing nuclear materials and their transportation; safeguarding nuclear plants and materials; managing nuclear wastes; inspection and enforcement; cooperation with state governments; international activities; research and standards development; hearings; decisions and litigation; and administrative and public communications matters. Each chapter presents a detailed review of program accomplishments during the report period, fiscal year 1981

  1. Official communication of the Safety Commission

    CERN Multimedia

    DG Unit

    2009-01-01

    The Prevention and Training section of the Safety Commission, would like to inform you that the new Safety Awareness course for newcomers will replace the welcome video in building 55 as of 2 April. The 3 levels (‘Safety at CERN’, ‘General Risks’ and ‘Specific Risks’) followed by 3 tests will determine access to CERN. Thanks to the SIR (Safety Information Registration, http://sir.cern.ch) application, it will be possible for you to follow the awareness course from your computer. For more information, go to the Safety Commission web site: http://safety-commission.web.cern.ch

  2. Official communication of the Safety Commission

    CERN Multimedia

    DG Unit

    2009-01-01

    We, the Prevention and Training section of the Safety Commission, would like to inform you that the new Safety Awareness course for newcomers will replace the welcome video in building 55 as of the 2nd April. The 3 levels (‘Safety at CERN’, ‘General Risks’ and ‘Specific Risks’) followed by 3 tests will determine access to CERN. Thanks to the SIR (Safety Information Registration, http://sir.cern.ch) application, it will be possible for you to follow the awareness course from your computer. For more information, go to the Safety Commission web site: http://safety-commission.web.cern.ch

  3. Nuclear Regulatory Commission issuances: Volume 39, Number 6

    International Nuclear Information System (INIS)

    1994-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). Issuances of the Nuclear Regulatory Commission include: (1) Advanced Medical Systems, Inc.; (2) Henry Allen, Diane Marrone, and Susan Settino; and (3) Westinghouse Electric Corporation. Issuances of the Atomic Safety and Licensing Boards include: (1) Sequoyah Fuels Corporation and General Atomics Corporation and (2) Umetco Minerals Corporation. Issuances of Director's Decisions include: (1) Advanced Medical Systems, Inc., and (2) Boston Edison Company and all boiling water reactors. The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  4. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    International Nuclear Information System (INIS)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T

  5. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

  6. Permanent Commission for Health and Safety

    CERN Multimedia

    Association du personnel

    2007-01-01

    The mandate of the Staff Association's permanent commission for Health and Safety is to examine all aspects of health and safety related to the working environment at CERN. In no way does it wish to be a substitute for the official bodies that are responsible for these matters. The Commission's aim is to formulate remarks on and make proposals about these questions to the relevant bodies and the CERN Management. Its main focus is the safety of the CERN staff but it is also concerned with the safety of the installations and of the CERN environment. The Commission reports to the Staff Council and the Executive Committee of the Staff Association.

  7. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    International Nuclear Information System (INIS)

    Ferguson, J.B.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance

  8. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    Energy Technology Data Exchange (ETDEWEB)

    Ferguson, J. B. [ed.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance.

  9. Steam Generator tube integrity -- US Nuclear Regulatory Commission perspective

    International Nuclear Information System (INIS)

    Murphy, E.L.; Sullivan, E.J.

    1997-01-01

    In the US, the current regulatory framework was developed in the 1970s when general wall thinning was the dominant degradation mechanism; and, as a result of changes in the forms of degradation being observed and improvements in inspection and tube repair technology, the regulatory framework needs to be updated. Operating experience indicates that the current U.S. requirements should be more stringent in some areas, while in other areas they are overly conservative. To date, this situation has been dealt with on a plant-specific basis in the US. However, the NRC staff is now developing a proposed steam generator rule as a generic framework for ensuring that the steam generator tubes are capable of performing their intended safety functions. This paper discusses the current U.S. regulatory framework for assuring steam generator (SG) tube integrity, the need to update this regulatory framework, the objectives of the new proposed rule, the US Nuclear Regulatory Commission (NRC) regulatory guide (RG) that will accompany the rule, how risk considerations affect the development of the new rule, and some outstanding issues relating to the rule that the NRC is still dealing with

  10. Statement of Robert Bernero, Deputy Director, Office of Nuclear Material Safety and Safeguards, Nuclear Regulatory Commission: Accompanied by Robert Browning, Director, Division of High-Level Waste Management

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    Mr. Chairman, members of the Committee, thank you for this opportunity to present the views of the Nuclear Regulatory Commission (NRC) on the Department of Energy's (DOE) program for disposal of civilian high-level wastes. I have with me Mr. Robert Browning, Director of NRC's Division of High-Level Waste Management. As you know, we are in the pre-licensing consultation phase of the repository program. DOE has the responsibility to conduct site characterization activities to acquire data necessary to evaluate the suitability of each candidate site for an application to the Commission for construction authorization. I would like to discuss some of our concerns about site characterization at the three sites recommended to an approved by the President for characterization as candidate sites. It will then discuss our comments on DOE's Draft Mission Plan Amendment dated January, 1987 and, more generally, our interaction with DOE. Finally, I would like to describe our quality assurance activities. I will be happy to respond to any questions from the Committee

  11. Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

  12. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Stuller, J.; Brandejs, P.; Miasnikov, A.; Svab, M.

    1999-01-01

    In beginning, a history of legislative process regulating industrial utilisation of nuclear energy is given, including detailed list of decrees issued by the first regulatory body supervising Czech nuclear installations - Czechoslovak Atomic Energy Commission (CSKAE). Current status of nuclear regulations and radiation protection, especially in connection with Atomic Act (Act No 18/1997 Coll.), is described. The Atomic Act transfers into the Czech legal system a number of obligations following from the Vienna Convention on Civil Liability for Nuclear Damage and Joint Protocol relating to the Application of the Vienna and Paris Convention, to which the Czech Republic had acceded. Actual duties and competence of current nuclear regulatory body - State Office for Nuclear Safety (SUJB) - are given in detail. Execution of the State supervision of peaceful utilisation of nuclear energy and ionising radiation is laid out in several articles of the Act, which comprises: control activities of the SUJB, remedial measures, penalties. Material and human resources are sufficient for fulfilment of the basic functions for which SUJB is authorised by the law. For 1998, the SUJB allotted staff of 149, approximately 2/3 of that number are nuclear safety and radiation protection inspectors. The SUJB budget for 1998 is approximately 180 million Czech crowns (roughly 6 million US dollars). Inspection activity of SUJB is carried out in three different ways: routine inspections, planned specialised inspections, inspections as a response to a certain situation (ad-hoc inspections). Approach to the licensing of major plant upgrades and backfittings are mainly illustrated on the Temelin NPP licensing. Regulatory position and practices concerning review activities are presented. (author)

  13. 77 FR 34379 - Notice of Joint Meeting of the Nuclear Regulatory Commission and the Federal Energy Regulatory...

    Science.gov (United States)

    2012-06-11

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. AD06-6-000] Notice of Joint Meeting of the Nuclear Regulatory Commission and the Federal Energy Regulatory Commission The Federal Energy Regulatory Commission (FERC) and the Nuclear Regulatory Commission (NRC) will hold a joint meeting...

  14. Problems and experience of regulatory review associated with plant construction and commissioning

    International Nuclear Information System (INIS)

    Commander, W.

    1979-01-01

    The work of the Assessment Branch of NII covering the regulatory review during design safety assessment, construction, commissioning and operation is described commencing with the nuclear licensing procedure through licence variations and conditions attached to the licence, to the final stages of plant construction up to commercial operation and full power production. The importance of the application of safety assessment principles is outlined, the importance of the Safety Inspectorate Schedule described, and the need to retain organisational and regulatory flexibility emphasised. (author)

  15. The role of effective communications in Nuclear Regulatory Commission licensing

    International Nuclear Information System (INIS)

    Counsil, W.G.

    1991-01-01

    Communications are essential to the licensing and general regulatory program of the Nuclear Regulatory Commission. This paper attempts to identify and address certain aspects of, and approaches to, maintaining effective and efficient communications. It considers, from the perspective of the high-level radioactive waste repository program, both internal communication within the DOE itself and external communication with the Nuclear Regulatory Commission and interested parties. Many of the points presented are based on lessons learned from electric utility experience with nuclear plants

  16. Federal Energy Regulatory Commission fiscal year 1997 annual financial statements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-24

    This report presents the results of the independent certified public accountants` audit of the Federal Energy Regulatory commission`s statements of financial position, and the related statements of operations and changes in net position. The auditors` work was conducted in accordance with generally accepted government auditing standards. An independent public accounting firm conducted the audit. The auditors` reports on the Commission`s internal control structure and compliance with laws and regulations disclosed no reportable conditions or instances of noncompliance.

  17. United States Nuclear Regulatory Commission staff practice and procedure digest

    International Nuclear Information System (INIS)

    1991-02-01

    This Revision 9 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to September 30, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 9 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through September 30, 1990. This edition of the Digest was prepared by attorneys from Aspen Systems Corporation pursuant to Contract number 18-89-346. Persons using this Digest are placed on notice that it may not be used as an authoritative citation in support of any position before the Commission or any of its adjudicatory tribunals. Persons using this Digest are also placed on notice that it is intended for use only as an initial research tool, that it may, and likely does, contain errors, including errors in analysis and interpretation of decisions, and that the user should not rely on the Digest analyses and interpretations but must read, analyze and rely on the user's own analysis of the actual Commission, Appeal Board and Licensing Board decisions cited. Further, neither the United States, the Nuclear Regulatory Commission, Aspen Systems Corporation, nor any of their employees makes any expressed or implied warranty or assumes liability or responsibility for the accuracy, completeness or usefulness of any material presented in the Digest. The Digest is roughly structured in accordance with the chronological sequence of the nuclear facility licensing process as set forth in Appendix A to 10 CFR Part 2. Those decisions which did not fit into that structure are dealt with in a section on general matters. Where appropriate, particular decisions are indexed under more than one heading. (JF)

  18. Regulatory Expectations for Safety Culture

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Su Jin; Oh, Jang Jin; Choi, Young Sung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    The oversight of licensee's safety culture becomes an important issue that attracts great public and political concerns recently in Korea. Beginning from the intended violation of rules, a series of corruptions, documents forgery and disclosure of wrong-doings made the public think that the whole mindset of nuclear workers has been inadequate. Thus, they are demanding that safety culture shall be improved and that regulatory body shall play more roles and responsibilities for the improvements and oversight for them. This paper introduces, as an effort of regulatory side, recent changes in the role of regulators in safety culture, regulatory expectations on the desired status of licensee's safety culture, the pilot inspection program for safety culture and research activity for the development of oversight system. After the Fukushima accident in Japan 2011, many critics has searched for cultural factors that caused the unacceptable negligence pervaded in Japan nuclear society and the renewed emphasis has been placed on rebuilding safety culture by operators, regulators, and relevant institutions globally. Significant progress has been made in how to approach safety culture and led to a new perspective different from the existing normative assessment method both in operators and regulatory side. Regulatory expectations and oversight of them are based on such a new holistic concept for human, organizational and cultural elements to maintain and strengthen the integrity of defense in depth and consequently nuclear safety.

  19. Regulatory Expectations for Safety Culture

    International Nuclear Information System (INIS)

    Jung, Su Jin; Oh, Jang Jin; Choi, Young Sung

    2014-01-01

    The oversight of licensee's safety culture becomes an important issue that attracts great public and political concerns recently in Korea. Beginning from the intended violation of rules, a series of corruptions, documents forgery and disclosure of wrong-doings made the public think that the whole mindset of nuclear workers has been inadequate. Thus, they are demanding that safety culture shall be improved and that regulatory body shall play more roles and responsibilities for the improvements and oversight for them. This paper introduces, as an effort of regulatory side, recent changes in the role of regulators in safety culture, regulatory expectations on the desired status of licensee's safety culture, the pilot inspection program for safety culture and research activity for the development of oversight system. After the Fukushima accident in Japan 2011, many critics has searched for cultural factors that caused the unacceptable negligence pervaded in Japan nuclear society and the renewed emphasis has been placed on rebuilding safety culture by operators, regulators, and relevant institutions globally. Significant progress has been made in how to approach safety culture and led to a new perspective different from the existing normative assessment method both in operators and regulatory side. Regulatory expectations and oversight of them are based on such a new holistic concept for human, organizational and cultural elements to maintain and strengthen the integrity of defense in depth and consequently nuclear safety

  20. Nuclear Regulatory Commission issuances, April 1995. Volume 41, Number 4

    International Nuclear Information System (INIS)

    1995-04-01

    This book contains issuances of the Nuclear Regulatory Commission and of the Atomic Safety and Licensing Boards, and an issuance of the Director's decision. The issuances concern a petition filed by Dr. James E Bauer seeking interlocutory Commission review of the Atomic Safety and Licensing Board's order imposing several restrictions on Dr. Bauer; a denial of an Interveners' Petition for Review addressing the application of Babcock and Wilcox for a renewal of its Special Nuclear Materials License; granting a motion for a protective order, by Sequoyah Fuel Corporation and General Atomics, limiting the use of the protected information to those individuals participating in the litigation and for the purposes of the litigation only; granting a Petitioner's petition for leave to intervene and request for a hearing concerning Georgia Institute of Technology (Georgia Tech Research Reactor) renewal of a facility license; and a denial of a petition filed by Mr. Ted Dougherty requesting a shutdown of the San Onofre Nuclear Generating Station based on concerns regarding the vulnerability of the plant to earthquakes and defensibility of the plant to a terrorist threat

  1. Nuclear Regulatory Commission issuances, April 1995. Volume 41, Number 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This book contains issuances of the Nuclear Regulatory Commission and of the Atomic Safety and Licensing Boards, and an issuance of the Director`s decision. The issuances concern a petition filed by Dr. James E Bauer seeking interlocutory Commission review of the Atomic Safety and Licensing Board`s order imposing several restrictions on Dr. Bauer; a denial of an Interveners` Petition for Review addressing the application of Babcock and Wilcox for a renewal of its Special Nuclear Materials License; granting a motion for a protective order, by Sequoyah Fuel Corporation and General Atomics, limiting the use of the protected information to those individuals participating in the litigation and for the purposes of the litigation only; granting a Petitioner`s petition for leave to intervene and request for a hearing concerning Georgia Institute of Technology (Georgia Tech Research Reactor) renewal of a facility license; and a denial of a petition filed by Mr. Ted Dougherty requesting a shutdown of the San Onofre Nuclear Generating Station based on concerns regarding the vulnerability of the plant to earthquakes and defensibility of the plant to a terrorist threat.

  2. Nuclear Regulatory Commission issuances. Volume 23, No. 3

    International Nuclear Information System (INIS)

    1986-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), and the Directors' Decisions (DD)

  3. U.S. Nuclear Regulatory Commission human factors program plan

    International Nuclear Information System (INIS)

    1986-04-01

    The purpose of the U.S. Nuclear Regulatory Commission (NRC) Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design and operation of nuclear facilities. This revised plan addresses human factors issues related to the operation of nuclear power plants (NPPs). The three issues of concern are (1) the activities planned to provide the technical bases to resolve the remaining tasks related to human factors as described in NUREG-0660, The NRC Action Plan Developed as a Result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the need to address the additional human factors efforts that were identified during implementation of the Action Plan; and (3) the actual fulfillment of those developmental activities specified in Revision 1 of this plan. The plan represents a systematic approach for addressing high priority human factors concerns important to NPP safety in FY 1986 through 1987

  4. The Spanish energy regulatory body: the national energy commission (CNE)

    International Nuclear Information System (INIS)

    Merono, P. M.

    2002-01-01

    The National Energy Commission (CNE) is the Spanish Energy Regulatory body. This paper presents its scope and purpose, organisation, resources and financing, financial and performance control, functions, and legal provisions. (author)

  5. United States Nuclear Regulatory Commission staff practice and procedure digest

    International Nuclear Information System (INIS)

    1990-03-01

    This document contains procedures for review by US Nuclear Regulatory Commission for reviewing and deciding on matters pertaining to nuclear power plant licensing. Also, contained within the document are decisions the Commission has made between July 1972 to September 1989. (F.S.D.)

  6. US Nuclear Regulatory Commission annual report, 1985. Volume 2

    International Nuclear Information System (INIS)

    1986-01-01

    The decisions and actions of the Nuclear Regulatory Commission (NRC) during fiscal year 1985 are reported. Areas covered include reactor regulation, cleanup at Three Mile Island, analysis and evaluation of operational experience, nuclear materials, waste management, safeguards, inspection, enforcement, quality assurance, emergency preparedness, and nuclear regulatory research. Also, cooperation with the states, international programs, proceedings and litigation, and management are discussed

  7. Securities and Exchange Commission Semiannual Regulatory Agenda

    Science.gov (United States)

    2010-12-20

    ... Flexibility Analysis Required: Yes Agency Contact: Alicia Goldin, Division of Trading and Markets, Securities...: Alicia Goldin, Division of Trading and Markets, Securities and Exchange Commission, 100 F Street NE... Flexibility Analysis Required: Yes Agency Contact: Alicia Goldin, Division of Trading and Markets, Securities...

  8. Federal Energy Regulatory Commission`s fiscal year 1996 financial statement audit

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-14

    This report presents the results of the independent certified public accountants` audit of the Federal Energy Regulatory Commission`s (FERC) financial statements as of September 30, 1996. The auditors have expressed an unqualified opinion on the 1996 statement of financial position and the related statements of operations and changes in net position.

  9. Nuclear Regulatory Commission Issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders: July 1, 1992--December 31, 1992, Volume 36, Pages 1--396

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    This is the thirty-sixth volume of issuances (1-396) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. It covers the period from July 1, 1992-December 31, 1992. Atomic Safety and Licensing Boards are authorized by Section 191 of the Atomic Energy Act of 1954. These Boards, comprised of three members conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. Boards are drawn from the Atomic Safety and Licensing Board Panel, comprised of lawyers, nuclear physicists and engineers, environmentalists, chemists, and economists. The Atomic Energy Commission first established Licensing Boards in 1962 and the Panel in 1967.

  10. Nuclear Regulatory Commission and its role in environmental standards

    International Nuclear Information System (INIS)

    Mattson, R.J.

    1976-01-01

    The NRC and its predecessors in the Atomic Energy Commission represent considerable experience in environmental standards setting. The Atomic Energy Act of 1954, the 1970 Supreme Court decision on Federal pre-emption of radiation standards, the Calvert Cliffs decision of 1971, the Energy Reorganization Act of 1974, and the Appendix I ''as low as reasonably achievable'' decision of 1975, to name a few of our landmarks, are representative of the scars and the achievements of being in a role of national leadership in radiation protection. The NRC, through a variety of legislative authorities, administrative regulations, regulatory guides, and national consensus standards regulates the commercial applications of nuclear energy. The purposes of regulation are the protection of the environment, public health and safety, and national security. To understand NRC's responsibilities relative to those of other Federal and state agencies concerned with environmental protection, we will briefly review the legislative authorities which underlie our regulatory program. Then we will examine the intent or the spirit of that program as embodied in our system of regulations, guides, and standards. Finally we will speak to what's happening today and what we see in the future for environmental standards

  11. Federal Trade Commission Semiannual Regulatory Agenda

    Science.gov (United States)

    2010-12-20

    ...) Retail Food Store Advertising and Marketing Practices, 16 CFR 424; (8) the Negative Option Rule, 16 CFR... Deregulatory Actions includes The Regulatory Plan, which appears in both the online Unified Agenda and in part... available online at www.reginfo.gov , in a format that offers users a greatly enhanced ability to obtain...

  12. US Nuclear Regulatory Commission 1983 annual report

    International Nuclear Information System (INIS)

    1984-01-01

    The thirteen chapters of this annual report are titled: 1983 highlights/1984 planning; reactor regulation; cleanup at TMI-2; operational experience; nuclear materials; safeguards; waste management; inspection, enforcement and emergency preparedness; cooperation with the states; international programs; nuclear regulatory research; proceedings and litigation; and management and communication

  13. Securities and Exchange Commission Semiannual Regulatory Agenda

    Science.gov (United States)

    2010-04-26

    ...: 3235-AK58 420. REVISIONS TO REGULATION D Legal Authority: 15 USC 77b(a)(15); 15 USC 77b(b); 15 USC 77d; 15 USC 77r; 15 USC 77s; 15 USC 77s(a); 15 USC 77z-3 Abstract: The Division is considering... SOLICITATION ENHANCEMENTS Legal Authority: 15 USC 78n Abstract: The Commission proposed amendments to its proxy...

  14. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Kastchiev, G.

    1999-01-01

    Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

  15. Safety research programs sponsored by Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Weiss, A.J.; Azarm, A.; Baum, J.W.

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988

  16. Nuclear Regulatory Commission issuances, March 1995. Volume 41, No. 3

    International Nuclear Information System (INIS)

    1995-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances, May 1995. Volume 41, No. 5

    International Nuclear Information System (INIS)

    1995-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances. Volume 42, No. 6

    International Nuclear Information System (INIS)

    1995-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  19. Regulatory view on licensing and commissioning of Temelin NPP

    International Nuclear Information System (INIS)

    Drabova, D.; Boehm, K.; Brandejs, P.; Tipek, Z.

    2004-01-01

    The competencies delegated to the Czech State Office for Nuclear Safety by Czech legislation are highlighted and the history of construction and commissioning of the Temelin nuclear power plant in relation to the licensing process is described. (P.A.)

  20. Nuclear Regulatory Commission issuances, April 1994. Volume 39, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  1. Nuclear Regulatory Commission issuances, March 1995. Volume 41, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  2. Nuclear Regulatory commission issuances, Volume 42, No. 5

    International Nuclear Information System (INIS)

    1995-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances. Volume 42, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  4. Nuclear Regulatory Commission issuances, September 1994. Volume 40, No. 3

    International Nuclear Information System (INIS)

    1994-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, December 1994. Volume 40, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  6. Nuclear Regulatory Commission issuances, Volume 47, No. 1

    International Nuclear Information System (INIS)

    1998-01-01

    This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

  7. Nuclear Regulatory Commission issuances, May 1995. Volume 41, No. 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  8. Nuclear Regulatory Commission issuances, Volume 45, No. 2

    International Nuclear Information System (INIS)

    1997-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances. Volume 42, No. 4

    International Nuclear Information System (INIS)

    1995-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances, February 1996: Volume 43, No. 2

    International Nuclear Information System (INIS)

    1996-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances. Volume 38, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors; Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  12. Nuclear Regulatory Commission issuances, February 1996: Volume 43, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  13. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately

  14. Audit of the Federal Energy Regulatory Commission`s Office of Chief Accountant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-07

    The Federal Energy Regulatory Commission`s (Commission) mission is to oversee America`s natural gas and oil pipeline transportation, electric utility, and hydroelectric power industries to ensure that consumers receive adequate energy supplies at just and reasonable rates. To carry out this mission, the Commission issues regulations covering the accounting, reporting, and rate-making requirements of the regulated utility companies. The Commission`s Office of Chief Accountant performs financial related audits at companies to ensure compliance with these regulations. The purpose of this audit was to evaluate the office of Chief Accountant`s audit performance. Specifically, the objectives were to determine if the most appropriate audit approach was used and if a quality assurance process was in place to ensure reports were accurate and supported by the working papers.

  15. U.S. Nuclear Regulatory Commission natural analogue research program

    International Nuclear Information System (INIS)

    Kovach, L.A.; Ott, W.R.

    1995-01-01

    This article describes the natural analogue research program of the U.S. Nuclear Regulatory Commission (US NRC). It contains information on the regulatory context and organizational structure of the high-level radioactive waste research program plan. It also includes information on the conditions and processes constraining selection of natural analogues, describes initiatives of the US NRC, and describes the role of analogues in the licensing process

  16. Implementation of safety goals in NRC's regulatory process

    International Nuclear Information System (INIS)

    Murley, T.E.

    1985-01-01

    In May 1983 the Nuclear Regulatory Commission issued a policy statement on Safety Goals For Nuclear Power Plant Operation. The Commission at the same time judged that a two-year evaluation period was necessary to judge the effectiveness of the goals and design objectives, and directed the staff to develop information and understanding as to how to further define and use the design objectives and the cost-benefit guidelines. In carrying out the Commission's mandate, the staff framed three major questions to be addressed during the safety goal evaluation period. These three questions are: 1) to what extent is it practical to use safety goals in the regulatory process. 2) Should the quantitative design objectives be modified or supplemented. If so, how. 3) How should the safety goals be implemented at the end of the evaluation period. The staff's conclusions are discussed

  17. Nuclear Regulatory Commission issuances, April 1986. Volume 23, No. 4

    International Nuclear Information System (INIS)

    1986-04-01

    This report includes the issuances recieved during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances, Volume 18, No. 5

    International Nuclear Information System (INIS)

    1983-11-01

    This report includes the issuances received during November, 1983, from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances. Volume 17, No. 4

    International Nuclear Information System (INIS)

    1983-04-01

    This report includes the issuances received during the specified period from the Commission (CLi), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Indexes to Nuclear Regulatory Commission issuances, January-June 1987

    International Nuclear Information System (INIS)

    1988-02-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  1. Nuclear Regulatory Commission issuances. Vol. 16, No. 5

    International Nuclear Information System (INIS)

    1982-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

  2. Nuclear Regulatory Commission Issuances. Volume 23, No. 1

    International Nuclear Information System (INIS)

    1986-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Indexes to Nuclear Regulatory Commission issuances, January-March 1987

    International Nuclear Information System (INIS)

    1987-09-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document

  4. Indexes to Nuclear Regulatory Commission issuances, January--March 1989

    International Nuclear Information System (INIS)

    1989-07-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

  5. Indexes to Nuclear Regulatory Commission issuances, January-June 1982

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  6. Nuclear Regulatory Commission issuances. Volume 20, No. 4

    International Nuclear Information System (INIS)

    1984-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Indexes to Nuclear Regulatory Commission issuances, July-December 1986

    International Nuclear Information System (INIS)

    1987-07-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  8. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1992-08-01

    This 2nd revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to September 30, 1991, interpreting the NRC's Rules of Pratice in 10 CFR Part 2

  9. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1990-08-01

    This Revision Number 7 of the fifth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to March 31, 1990, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  10. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1992-02-01

    This revision of the sixth edition of the NRC Practice and Procedure Digest contains a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to March 31, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  11. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1992-05-01

    This 2nd revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to June 30, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  12. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1993-08-01

    This 7th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to September 30, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  13. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1993-05-01

    This 6th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to June 30, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  14. Nuclear Regulatory Commission issuances. Volume 20, No. 2

    International Nuclear Information System (INIS)

    1984-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances. Volume 21, No. 6

    International Nuclear Information System (INIS)

    1985-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances. Volume 21, No. 5

    International Nuclear Information System (INIS)

    1985-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances. Vol. 16, No. 4

    International Nuclear Information System (INIS)

    1982-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances, December 1982. Vol. 16, No. 6

    International Nuclear Information System (INIS)

    1982-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuance, pages 933-1089

    International Nuclear Information System (INIS)

    1981-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Denial (DD), and the Denial of Petitions for Rulemaking

  20. Nuclear Regulatory Commission issuances. Volume 22, No. 6

    International Nuclear Information System (INIS)

    1985-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Indexes to Nuclear Regulatory Commission issuances, July-September 1986

    International Nuclear Information System (INIS)

    1987-06-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  2. Indexes to Nuclear Regulatory Commission issuances, July-December 1987

    International Nuclear Information System (INIS)

    1988-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  3. Nuclear Regulatory Commission Issuances. Volume 22, No. 1

    International Nuclear Information System (INIS)

    1985-07-01

    This report includes the issuances received during July 1985 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances, June 1986. Volume 23, No. 6

    International Nuclear Information System (INIS)

    1986-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances. Vol. 16, No. 1

    International Nuclear Information System (INIS)

    1982-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

  6. Indexes to Nuclear Regulatory Commission issuances, July-September 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as guide to the issuances

  7. Indexes to Nuclear Regulatory Commission issuances, July--December 1989

    International Nuclear Information System (INIS)

    1990-05-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  8. Nuclear Regulatory Commission Issuances. Volume 23, No. 2

    International Nuclear Information System (INIS)

    1986-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances. Volume 22, No. 5

    International Nuclear Information System (INIS)

    1985-11-01

    This report includes the issuances received during November 1985 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. KWOC [Key-Word-Out-of-Context] Index of US Nuclear Regulatory Commission Regulatory Guide Series

    International Nuclear Information System (INIS)

    Jennings, S.D.

    1990-04-01

    To meet the objectives of the program funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a Performance Assurance Information Program that collects, compiles, and distributes program-related information, reports, and publications for the benefit of the DOE-NE program participants. THE ''KWOC Index of US Nuclear Regulatory Commission Regulatory Guide Series'' is prepared as an aid in searching for specific topics in the US Nuclear Regulatory Commission, Regulatory Guide Series

  11. US Nuclear Regulatory Commission organization charts and functional statements

    International Nuclear Information System (INIS)

    1997-01-01

    This document contains organization charts for the U.S. Nuclear Regulatory Commission (NRC) and for the five offices of the NRC. Function statements are provided delineating the major responsibilities and operations of each office. Organization and function are provided to the branch level. The head of each office, division, and branch is also listed

  12. US Nuclear Regulatory Commission organization charts and functional statements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    This document contains organization charts for the U.S. Nuclear Regulatory Commission (NRC) and for the five offices of the NRC. Function statements are provided delineating the major responsibilities and operations of each office. Organization and function are provided to the branch level. The head of each office, division, and branch is also listed.

  13. Regulatory measures for traffic safety

    International Nuclear Information System (INIS)

    Veerapur, R.D.; Bharambe, S.D.; Patnaik, S.K.; Tandle, A.K.; Sonawane, K.A.; Kumar, Rajesh; Venkat Subramanian, K.

    2017-01-01

    Traffic safety is an issue related to occupational safety not restricted alone to the transportation but extends beyond. BARC has many facilities spread across large area in Mumbai and outside Mumbai. BARC deploys large number of buses, mini buses, jeeps and cars for commuting its employees to reach BARC and for commuting within BARC premises. Additionally, trucks, fire tenders, trailers etc. are also deployed for transportation of materials. No moving vehicle is ever free of the possibility of involvement in an accident. Vehicular accidents and the fatalities on road are the result of inter-play of a number of factors. The vehicle population has been steadily increasing with the pace picking up significantly in recent past. Increase in vehicle population in the face of limited road space used by a large variety of traffic has heightened the need and urgency for a well-thought-out road safety. Therefore, existence of regulatory authority to regulate traffic and vehicles to ensure safety of its employees and vehicles is very essential. BARC Traffic Safety Committee (BTSC), which is the regulating body for traffic safety is responsible for ensuring overall traffic safety. (author)

  14. Nuclear Regulatory Commission issuances. Volume 47, Number 3

    International Nuclear Information System (INIS)

    1998-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The two issuances included here are: (1) the Commission issuance to the US Enrichment Corporation and (2) the Director's Decision to the North Atlantic Energy Service Corporation

  15. Probabilistic safety assessment - regulatory perspective

    International Nuclear Information System (INIS)

    Solanki, R.B.; Paul, U.K.; Hajra, P.; Agarwal, S.K.

    2002-01-01

    Full text: Nuclear power plants (NPPs) have been designed, constructed and operated mainly based on deterministic safety analysis philosophy. In this approach, a substantial amount of safety margin is incorporated in the design and operational requirements. Additional margin is incorporated by applying the highest quality engineering codes, standards and practices, and the concept of defence-in-depth in design and operating procedures, by including conservative assumptions and acceptance criteria in plant response analysis of postulated initiating events (PIEs). However, as the probabilistic approach has been improved and refined over the years, it is possible for the designer, operator and regulator to get a more detailed and realistic picture of the safety importance of plant design features, operating procedures and operational practices by using probabilistic safety assessment (PSA) along with the deterministic methodology. At present, many countries including USA, UK and France are using PSA insights in their decision making along with deterministic basis. India has also made substantial progress in the development of methods for carrying out PSA. However, consensus on the use of PSA in regulatory decision-making has not been achieved yet. This paper emphasises on the requirements (e.g.,level of details, key modelling assumptions, data, modelling aspects, success criteria, sensitivity and uncertainty analysis) for improving the quality and consistency in performance and use of PSA that can facilitate meaningful use of the PSA insights in the regulatory decision-making in India. This paper also provides relevant information on international scenario and various application areas of PSA along with progress made in India. The PSA perspective presented in this paper may help in achieving consensus on the use of PSA for regulatory / utility decision-making in design and operation of NPPs

  16. Nuclear Regulatory Commission issuances: Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1 - December 31, 1996. Volume 44, Pages 1 - 432

    International Nuclear Information System (INIS)

    1997-01-01

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors' Decisions--DD, and Decisions on Petitions for Rulemaking--DPRM

  17. Nuclear Regulatory Commission issuances: Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1--December 31, 1996. Volume 44, Pages 1--432

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors` Decisions--DD, and Decisions on Petitions for Rulemaking--DPRM.

  18. U.S. Nuclear Regulatory Commission Process for Risk-Informing the Nuclear Waste Arena

    International Nuclear Information System (INIS)

    Leslie, B. W.

    2003-01-01

    The U.S. Nuclear Regulatory Commission (NRC) is increasing the use of risk insights and information in its regulation of nuclear materials and waste. The objective of this risk-informed regulatory effort is to improve the effectiveness and efficiency of the agency, while maintaining or increasing its focus on safety. The agency's Office of Nuclear Material Safety and Safeguards (NMSS) proposed a five-step process to carry out a framework for increasing the use of risk information and insights in its regulation of nuclear materials and waste. The office is carrying out the five-step process to risk-inform the nuclear materials and waste arenas. NMSS's actions included forming a Risk Task Group and the use of case studies to test and complete screening criteria for identifying candidate regulatory applications amenable for risk-informing. Other actions included involving stakeholders through enhanced public participation, developing safety goals for materials and waste regulatory applications, and establishing a risk training program for staff. Through the case studies, NRC staff found the draft screening criteria to be effective in deciding regulatory areas that may be amenable to an increased use of risk insights. NRC staff also found that risk information may have the potential to reduce regulatory burden and improve staff's efficiency in making decisions, while maintaining safety. Finally, staff found that it would be possible to develop safety goals for the nuclear materials and waste arenas

  19. Nuclear Regulatory Commission Issuances: February 1995. Volume 41, Number 2

    International Nuclear Information System (INIS)

    1995-02-01

    This book contains an issuance of the Nuclear Regulatory Commission and a Director's Decision. The issuance concerns consideration by the Commission of appeals from both the Initial Decision and a Reconsideration Order issued by the Presiding Officer involving two materials license amendment applications filed by the University of Missouri. The Director's Decision from the Office of Enforcement denies petitions filed by Northeast Utilities employees requesting that accelerated enforcement action be taken against Northeast Utilities for activities concerned with NU's fitness-for-duty program

  20. Regulatory Control of Radiation Sources. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This Safety Guide is intended to assist States in implementing the requirements established in Safety Standards Series No. GS-R-1, Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, for a national regulatory infrastructure to regulate any practice involving radiation sources in medicine, industry, research, agriculture and education. The Safety Guide provides advice on the legislative basis for establishing regulatory bodies, including the effective independence of the regulatory body. It also provides guidance on implementing the functions and activities of regulatory bodies: the development of regulations and guides on radiation safety; implementation of a system for notification and authorization; carrying out regulatory inspections; taking necessary enforcement actions; and investigating accidents and circumstances potentially giving rise to accidents. The various aspects relating to the regulatory control of consumer products are explained, including justification, optimization of exposure, safety assessment and authorization. Guidance is also provided on the organization and staffing of regulatory bodies. Contents: 1. Introduction; 2. Legal framework for a regulatory infrastructure; 3. Principal functions and activities of the regulatory body; 4. Regulatory control of the supply of consumer products; 5. Functions of the regulatory body shared with other governmental agencies; 6. Organization and staffing of the regulatory body; 7. Documentation of the functions and activities of the regulatory body; 8. Support services; 9. Quality management for the regulatory system.

  1. US Nuclear Regulatory Commission, 1984 annual report. Volume 1

    International Nuclear Information System (INIS)

    1985-01-01

    This is the 10th annual report of the US Nuclear Regulatory Commission (NRC). This report covers the major activities, events, decisions and planning that took place during fiscal year 1984 (October 1983 through September 1984) within the NRC or involving the NRC. Information is presented concerning 1984 highlights and planning for 1985; reactor regulation; cleanup at Three Mile Island Unit 2; operational experience; nuclear materials; safeguards; waste management; inspection, enforcement, quality assurance, and emergency preparedness; cooperation with the States; international programs; nuclear regulatory research; proceedings and litigation; and management and communication

  2. Nuclear Regulatory Commission issuances. Volume 22, No. 4

    International Nuclear Information System (INIS)

    1985-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

  3. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1991-12-01

    This sixth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This sixth edition replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1990

  4. Indexes to Nuclear Regulatory Commission issuances, January--June 1989

    International Nuclear Information System (INIS)

    1989-09-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats. These formats are case named index digests and headers, legal citations index, subject index, and facility index

  5. Indexes to Nuclear Regulatory Commission issuances, July--December 1988

    International Nuclear Information System (INIS)

    1989-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

  6. Indexes to Nuclear Regulatory Commission issuances, July--September 1988

    International Nuclear Information System (INIS)

    1989-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These information elements are displayed in one or more of five separate formats. These formats are case name index, digests and headers, legal citations index, subject index and facility index

  7. The United States nuclear regulatory commission license renewal process

    International Nuclear Information System (INIS)

    Holian, B.E.

    2009-01-01

    The United States (U.S.) Nuclear Regulatory Commission (NRC) license renewal process establishes the technical and administrative requirements for the renewal of operating power plant licenses. Reactor ope-rating licenses were originally issued for 40 years and are allowed to be renewed. The review process for license renewal applications (L.R.A.) provides continued assurance that the level of safety provided by an applicant's current licensing basis is maintained for the period of extended operation. The license renewal review focuses on passive, long-lived structures and components of the plant that are subject to the effects of aging. The applicant must demonstrate that programs are in place to manage those aging effects. The review also verifies that analyses based on the current operating term have been evaluated and shown to be valid for the period of extended operation. The NRC has renewed the licenses for 52 reactors at 30 plant sites. Each applicant requested, and was granted, an extension of 20 years. Applications to renew the licenses of 20 additional reactors at 13 plant sites are under review. As license renewal is voluntary, the decision to seek license renewal and the timing of the application is made by the licensee. However, the NRC expects that, over time, essentially all U.S. operating reactors will request license renewal. In 2009, the U.S. has 4 plants that enter their 41. year of ope-ration. The U.S. Nuclear Industry has expressed interest in 'life beyond 60', that is, requesting approval of a second renewal period. U.S. regulations allow for subsequent license renewals. The NRC is working with the U.S. Department of Energy (DOE) on research related to light water reactor sustainability. (author)

  8. Nuclear Regulatory Commission issuances. Volume 46, Number 2

    International Nuclear Information System (INIS)

    1997-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  9. Nuclear Regulatory Commission issuances: Volume 46, Number 6

    International Nuclear Information System (INIS)

    1997-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decision (DD), and the Decision on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  10. Nuclear Regulatory Commission issuances. Volume 47, Number 2

    International Nuclear Information System (INIS)

    1998-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). They involve: 21st Century Technologies, Inc.; Hydro Resources, Inc.; Northeast Utilities; and Northern States Power Company

  11. Nuclear Regulatory Commission issuances. Volume 46, Number 1

    International Nuclear Information System (INIS)

    1997-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  12. Nuclear Regulatory Commission issuances, June 1997. Volume 45, Number 6

    International Nuclear Information System (INIS)

    1997-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  13. Nuclear Regulatory Commission issuances: June 1995. Volume 41, Number 6

    International Nuclear Information System (INIS)

    1995-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). This report contains four issuances by the CLI, 5 issuances by the LBP, and 1 issuance by the DD

  14. Nuclear Regulatory Commission issuances, Volume 45, No. 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

  15. Indexes to Nuclear Regulatory Commission Issuances, January--June 1994

    International Nuclear Information System (INIS)

    1994-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  16. Nuclear Regulatory Commission issuances: Volume 46, Number 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decision (DD), and the Decision on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

  17. Nuclear Regulatory Commission issuances, Volume 45, No. 5

    International Nuclear Information System (INIS)

    1997-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  18. Indexes to Nuclear Regulatory Commission issuances, January--March 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is the 1st quarter 1996 index to issuances by the US NRC. These include issuances by the Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

  19. Nuclear Regulatory Commission issuances: June 1995. Volume 41, Number 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). This report contains four issuances by the CLI, 5 issuances by the LBP, and 1 issuance by the DD.

  20. Specific problems and practical experience of regulatory inspection during commissioning in the United Kingdom

    International Nuclear Information System (INIS)

    Lewis, G.

    1977-01-01

    The commissioning of nine Magnox and two Advanced Gas-cooled Reactor Nuclear Power Plants in the United Kingdom during the last sixteen years under the regulatory control of the Nuclear Installations Inspectorate of the Health and Safety Executive has been based on a Stage Approval Philosophy starting with proof-testing of the primary gas circuit and concluding with tests on the reactor at full power. The practical experience gained during this period has enabled the Nuclear Installations Inspectorate to rationalise the procedures and test requirements without comporomising safety standards. The Operating Rules and Maintenance Schedules are approved for commissioning and during this period are reviewed for their adequacy for future power operation of the plant. The organisation, documentation, test procedures and the commissioning programme used for the Advanced Gas-cooled Reactors are briefly explained. (author)

  1. Safety analysis - current and future regulatory challenges

    Energy Technology Data Exchange (ETDEWEB)

    Jamieson, T., E-mail: Terry.Jamieson@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

    2015-07-01

    'Full text:' The current and future regulatory challenges associated with deterministic safety analysis are reviewed, including: 1. The CNSC's and safety control areas. 2. Traditional safety analysis approach. 3. Experience gained and impact. 4. Current analysis and regulatory approaches. 5. Current status. 6. Complexity and challenges In particular, the technical, regulatory and strategic aspects of these challenges are discussed. (author)

  2. Safety analysis - current and future regulatory challenges

    International Nuclear Information System (INIS)

    Jamieson, T.

    2015-01-01

    'Full text:' The current and future regulatory challenges associated with deterministic safety analysis are reviewed, including: 1. The CNSC's and safety control areas. 2. Traditional safety analysis approach. 3. Experience gained and impact. 4. Current analysis and regulatory approaches. 5. Current status. 6. Complexity and challenges In particular, the technical, regulatory and strategic aspects of these challenges are discussed. (author)

  3. Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

    International Nuclear Information System (INIS)

    Lipar, M.

    1998-01-01

    Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

  4. Nuclear Regulatory Commission issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1994--December 31, 1994. Volume 40, Pages 1--387

    International Nuclear Information System (INIS)

    1994-01-01

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. This book covers the following: issuances of the NRC; issuances of the Atomic Safety and Licensing Boards; and issuances of Directors' decisions

  5. Nuclear Regulatory Commission issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1994--December 31, 1994. Volume 40, Pages 1--387

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. This book covers the following: issuances of the NRC; issuances of the Atomic Safety and Licensing Boards; and issuances of Directors` decisions.

  6. Nuclear Regulatory Commission Issuances. Volume 45, No. 3

    International Nuclear Information System (INIS)

    1997-03-01

    This report includes the issuances received in March 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. 10 issuances were received: Louisiana Energy Services (2 issuances); Illinois Power Company and Soyland Power Cooperative; Ralph. L. Tetrick; University of Cincinnati; Consumers Power Company; Entergy Operations, Inc.; Georgia Power Company; Westinghouse Electric Corporation; and Wisconsin Electric Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  7. Indexes to Nuclear Regulatory Commission issuances, January--March 1992

    International Nuclear Information System (INIS)

    1992-06-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index; Digests and headers; Legal citations index; subject index; and facility index

  8. Indexes to Nuclear Regulatory Commission Issuances, July--December 1993

    International Nuclear Information System (INIS)

    1994-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Digests and Headers; Legal Citations Index; Subject Index, and Facility Index

  9. Indexes to Nuclear Regulatory Commission Issuances, January 1996--June 1996

    International Nuclear Information System (INIS)

    1996-09-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Board Panel, The Administrative Law Judges, the Director's Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. The digests and indexes are intended to serve as a guide to the issuances. Information elements common the cases hear and ruled upon are displayed in one or more of five formats: case name index, headers and digests, legal citations index, subject index, and facility index

  10. Indexes to Nuclear Regulatory Commission issuances, January--June 1992

    International Nuclear Information System (INIS)

    1992-09-01

    Digests and indexes for insurances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index

  11. Indexes to Nuclear Regulatory Commission issuances, July--September 1993

    International Nuclear Information System (INIS)

    1994-01-01

    Digest and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. these digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index, and facility index

  12. Nuclear Regulatory Commission Issuances. Volume 45, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This report includes the issuances received in March 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 10 issuances were received: Louisiana Energy Services (2 issuances); Illinois Power Company and Soyland Power Cooperative; Ralph. L. Tetrick; University of Cincinnati; Consumers Power Company; Entergy Operations, Inc.; Georgia Power Company; Westinghouse Electric Corporation; and Wisconsin Electric Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  13. Indexes to Nuclear Regulatory Commission Issuances, January 1996--June 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Board Panel, The Administrative Law Judges, the Director`s Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. The digests and indexes are intended to serve as a guide to the issuances. Information elements common the cases hear and ruled upon are displayed in one or more of five formats: case name index, headers and digests, legal citations index, subject index, and facility index.

  14. Indexes to Nuclear Regulatory Commission issuances, July--December, 1991

    International Nuclear Information System (INIS)

    1991-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Digests and Headers; Legal Citations Index; Subject Index; and Facility Index

  15. Indexes to Nuclear Regulatory Commission issuances, January--March 1993

    International Nuclear Information System (INIS)

    1993-07-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index

  16. Indexes to Nuclear Regulatory Commission issuances, July-December 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index; digests and headers; legal citations index; subject index; and facility index

  17. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1990-11-01

    This Revision 8 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 8 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1990

  18. Indexes to Nuclear Regulatory Commission issuances, January--June 1991

    International Nuclear Information System (INIS)

    1991-10-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index, digest and headers, legal citations index, subject index, and facility index

  19. Indexes to Nuclear Regulatory Commission issuances, July--September 1990

    International Nuclear Information System (INIS)

    1990-12-01

    Digests and indexes for issuances of the commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. The information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

  20. Indexes to Nuclear Regulatory Commission issuances, July--December 1990

    International Nuclear Information System (INIS)

    1991-03-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers legal citations index, subject index, and facility index

  1. Indexes to Nuclear Regulatory Commission issuances, January-March 1982

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. This information is displayed in one or more of five separate formats arranged as follows: case name index; digests and headers; legal citations index; subject index; and facility index

  2. Indexes to Nuclear Regulatory Commission issuances, January--June 1990

    International Nuclear Information System (INIS)

    1990-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALI), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

  3. Indexes to Nuclear Regulatory Commission issuances, January--March 1991

    International Nuclear Information System (INIS)

    1991-06-01

    Digests and indexes for Issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, logical citations index, subject index and facility index

  4. Managing the high level waste nuclear regulatory commission licensing process

    International Nuclear Information System (INIS)

    Baskin, K.P.

    1992-01-01

    This paper reports that the process for obtaining Nuclear Regulatory Commission permits for the high level waste storage facility is basically the same process commercial nuclear power plants followed to obtain construction permits and operating licenses for their facilities. Therefore, the experience from licensing commercial reactors can be applied to the high level waste facility. Proper management of the licensing process will be the key to the successful project. The management of the licensing process was categorized into four areas as follows: responsibility, organization, communication and documentation. Drawing on experience from nuclear power plant licensing and basic management principles, the management requirement for successfully accomplishing the project goals are discussed

  5. Nuclear safety research at the European Commission's Joint Research Centre

    International Nuclear Information System (INIS)

    Toerroenen, K.

    2003-01-01

    Nuclear power plants currently generate some 35 % of electricity used in the European Union and applicant countries. Nuclear safety will therefore remain a priority for the EU, particularly in view of enlargement, the need to monitor ageing nuclear installations and the licencing of advanced new reactor systems. The European Commission's Joint Research Centre (JRC), with its long involvement and recognised competence in nuclear safety related activities, provides direct support to the European Commission services responsible for nuclear safety and civil protection. (author)

  6. Special committee review of the Nuclear Regulatory Commission's severe accident risks report (NUREG--1150)

    International Nuclear Information System (INIS)

    Kouts, H.J.C.; Apostolakis, G.; Kastenberg, W.E.; Birkhofer, E.H.A.; Hoegberg, L.G.; LeSage, L.G.; Rasmussen, N.C.; Teague, H.J.; Taylor, J.J.

    1990-08-01

    In April 1989, the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research (RES) published a draft report ''Severe Accident Risks: An Assessment for Five US Nuclear Power Plants,'' NUREG-1150. This report updated, extended and improved upon the information presented in the 1974 ''Reactor Safety Study,'' WASH-1400. Because the information in NUREG-1150 will play a significant role in implementing the NRC's Severe Accident Policy, its quality and credibility are of critical importance. Accordingly, the Commission requested that the RES conduct a peer review of NUREG-1150 to ensure that the methods, safety insights and conclusions presented are appropriate and adequately reflect the current state of knowledge with respect to reactor safety. To this end, RES formed a special committee in June of 1989 under the provisions of the Federal Advisory Committee Act. The Committee, composed of a group of recognized national and international experts in nuclear reactor safety, was charged with preparing a report reflecting their review of NUREG-1150 with respect to the adequacy of the methods, data, analysis and conclusions it set forth. The report which precedes reflects the results of this peer review

  7. 17 CFR 201.421 - Commission consideration of determinations by self-regulatory organizations.

    Science.gov (United States)

    2010-04-01

    ... determinations by self-regulatory organizations. 201.421 Section 201.421 Commodity and Securities Exchanges... Commission Review § 201.421 Commission consideration of determinations by self-regulatory organizations. (a..., order review of any determination by a self-regulatory organization that could be subject to an...

  8. Nuclear Regulatory Commission issuances, Volume 44, No. 4

    International Nuclear Information System (INIS)

    1996-10-01

    This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  9. Nuclear Regulatory Commission issuances. Volume 44, Number 2

    International Nuclear Information System (INIS)

    1996-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). The topics of this publication include the dismissal of a suit brought against Georgia Power Company in the transfer of Vogtle Electric Generating Plant, units 1 and 2 to Southern Nuclear; and denial of a petition to review the entire licensing process for Watts Bar Nuclear Plant, Unit 1 operated by the Tennessee Valley Authority

  10. Indexes to Nuclear Regulatory Commission Issuances, January--June 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This report indexes the issuances heard and ruled upon from January through June 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Information provided for each case includes the case name, full test reference, issuance number, issues raised by appellants, legal citations, facility name and docket number, subject matter of issues and/or rulings, type of hearing, and type of issuance. Each issuance is displayed in one or more of five separate formats: (1) case name index, (2) headers and digests, (3) legal citations index, (4) subject index, and (5) facility index.

  11. Indexes to Nuclear Regulatory Commission Issuances, January--June 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This report indexes the issuances heard and ruled upon from January through June 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. Information provided for each case includes the case name, full test reference, issuance number, issues raised by appellants, legal citations, facility name and docket number, subject matter of issues and/or rulings, type of hearing, and type of issuance. Each issuance is displayed in one or more of five separate formats: (1) case name index, (2) headers and digests, (3) legal citations index, (4) subject index, and (5) facility index

  12. Nuclear Regulatory Commission issuances, Volume 46, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This report includes the issuances received in October 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. Five issuances were received on the following subjects: (1) decontamination and decommissioning funding for Sequoyah Fuels Corporation and General Atomics; (2) involvement in NRC-licensed activities by Aharon Ben-Haim; (3) Barnett Industrial X-Ray, Inc.; (4) spent fuel storage installation at Northern States Power Company; and (5) Vermont Yankee Nuclear Power Station. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  13. Nuclear Regulatory Commission issuances, Volume 46, No. 4

    International Nuclear Information System (INIS)

    1997-10-01

    This report includes the issuances received in October 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Five issuances were received on the following subjects: (1) decontamination and decommissioning funding for Sequoyah Fuels Corporation and General Atomics; (2) involvement in NRC-licensed activities by Aharon Ben-Haim; (3) Barnett Industrial X-Ray, Inc.; (4) spent fuel storage installation at Northern States Power Company; and (5) Vermont Yankee Nuclear Power Station. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  14. Nuclear Regulatory Commission Issuances, Volume 44, No. 5

    International Nuclear Information System (INIS)

    1996-11-01

    This report includes the issuances received in November 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Seven issuances were received and are abstracted individually in the database: Emerick S. McDaniel, U.S. Enrichment Corporation, Sequoyah Fuels Corporation and General Atomics, all power reactor licensees, Florida Power and Light Company, Maine Yankee Atomic Power Company, and Northern States Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  15. Nuclear Regulatory Commission issuances, Volume 44, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  16. Regulatory Framework of Safety for HTGR

    International Nuclear Information System (INIS)

    Huh, Chang Wook; Suh, Nam Duk

    2011-01-01

    Recent accident in Fukushima Daiichi plant in Japan makes big impacts on the future of nuclear business. Many countries are changing their nuclear projects and increased safety of nuclear plants is asked for from the public. Without providing safety the society accepts, it might be almost impossible to build new plants further. In this sense high temperature gas-cooled reactor (HTGR) which is under development needs to be licensed reflecting this new expectation regarding safety. It means we should have higher level of safety goal and a systematic regulatory framework to assure the safety. In our previous paper, we evaluated the current safety goal and design practice in view of this new safety expectation after Fukushima accident. It was argued that a top-down approach starting from safety goal is necessary to develop safety requirements or to assure safety. Thus we need to propose an ultimate safety goal public accepts and then establish a systematic regulatory framework. In this paper we are going to provide a conceptual regulatory framework to guarantee the safety of HTGR. Section 2 discusses the recent trend of IAEA safety requirements and then summarize the HTGR design approach. Incorporating these discussions, we propose a conceptual framework of regulation for safety of HTGR

  17. 75 FR 54917 - Criteria for Nominating Materials Licensees for the U.S. Nuclear Regulatory Commission's Agency...

    Science.gov (United States)

    2010-09-09

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0294] Criteria for Nominating Materials Licensees for the U.S. Nuclear Regulatory Commission's Agency Action Review Meeting AGENCY: Nuclear Regulatory Commission. ACTION: Request for comment. SUMMARY: It is the policy of the U.S. Nuclear Regulatory Commission...

  18. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1980-02-01

    This first supplement to the second edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from April 1, 1978 to September 30, 1978 interpreting the NRC's Rules of Practice in 10 CFR Part 2. The supplement also includes additional material from adjudicatory decisions rendered prior to April 1, 1978 and, to a very limited degree, material from adjudicatory decisions and regulation changes after September 30, 1978. The supplement, which is intended to be used as a pocket-part supplement to the Digest itself, includes a number of new subsections and topics not covered in the Digest. The new subsections are noted in the index for the supplement

  19. Indexes to Nuclear Regulatory Commission Issuances, January-March 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors Denials (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owners of facility), Full text reference (volume and pagination), Issuance number, Issues raised by appellants, Legal citations (cases, regulations, and statutes), Name of facility, Docket number, Subject matter of issues and/or rulings, Type of hearing (for construction permit, operating license, etc.), and Type of issuance

  20. Nuclear Regulatory Commission issuances. Volume 17, No. 3

    International Nuclear Information System (INIS)

    1983-03-01

    This report contains the Issuances received during March 1983 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petition for Rulemaking (DPRM). The Issuances concerned the following facilities: Three Mile Island Nuclear Station, Unit No. 1; Comanche Peak Steam Electric Station, Units 1 and 2; Vallecitos Nuclear Center; Floating Nuclear Power Plants; San Onofre Nuclear Generating Station, Units 2 and 3; Point Beach Nuclear Plant, Unit 1; Perry Nuclear Power Plant, Units 1 and 2; Shoreham Nuclear Power Station, Unit 1; Western New York Nuclear Service Center; Limerick Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Black Fox Station, Units 1 and 2; WmH Zimmer Nuclear Power Station, Unit 1; WPPSS Nuclear Project No. 1; Zion Nuclear Plant, Units 1 and 2; and South Texas Project, Units 1 and 2

  1. Indexes to Nuclear Regulatory Commission issuances, January-March 1988

    International Nuclear Information System (INIS)

    1988-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owner(s) of facility); Full test reference (volume and pagination); Issuance number; Issues raised by appellants; Legal citations (cases, regulations, and statutes); Name of facility, Docket number; Subject matter of issues and/or rulings; Type of hearing (for construction permit, operating license, etc.); and Type of issuance (memorandum, order, decision, etc.)

  2. Indexes to Nuclear Regulatory Commission issuances, January--June 1988

    International Nuclear Information System (INIS)

    1988-09-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administration Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petition of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: case name (owner(s) of facility); full text reference (volume and pagination); issuance number; issues raised by appellants; legal citations (cases, regulations, and statutes); name of facility, docket number; subject matter of issues and/or rulings; type of hearing (for construction permit, operating license, etc.); and type of issuance (memorandum, order, decision, etc.)

  3. Indexes to Nuclear Regulatory Commission Issuances, January-June 1981

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owners of facility); Full text reference (volume and pagination); Issuance number; Issues raised by appellants; Legal citations (cases, regulations, and statutes); Name of facility, Docket number; Subject matter of issues and/or rulings; Type of hearing (for construction permit, operating license, etc.); and Type of issuance (memorandum, order, decision, etc.). These information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index, Digests and Headers, Legal Citations Index, Subject Index, and Facility Index

  4. Indexes to Nuclear Regulatory Commission Issuances, January--March 1990

    International Nuclear Information System (INIS)

    1990-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: case name (owner(s) of facility); full text reference (volume and pagination); issuance number; issues raised by appellants; legal citations (cases, regulations, and statutes); name of facility, Docket number; subject matter of issues and/or rulings; type of hearing (for construction permit, operating license, etc.); and type of issuance (memorandum, order, decision, etc.). These information elements are displayed in one or more of five separate formats arranged as follows: case name index; digests and headers; legal citations index; subject index; and facility index

  5. Regulatory Activities for Licensee's Safety Culture

    International Nuclear Information System (INIS)

    Choi, Young Sung; Choi, Kwang Sik

    2008-01-01

    Weaknesses in safety culture have contributed to a number of incidents/accidents in the nuclear and other high hazard sectors worldwide in the past. These events have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining regulatory oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. This paper presents the findings, conclusions and recommendations of international meetings and other countries' activities on safety culture and gives some suggestions for regulators to consider when planning regulatory oversight for licensee's safety culture

  6. The role of the Nuclear Regulatory Commission in the management of nuclear waste

    International Nuclear Information System (INIS)

    Thompson, H.L. Jr.

    1988-01-01

    In general, the US Nuclear Regulatory Commission (NRC) is responsible for reviewing and making licensing decisions to ensure that the US Department of Energy's (DOE's) high-level waste repository is designed, constructed, and operated without unreasonable risk to public health and safety. In implementing this responsibility, however, the commission's guidance to the staff is that, in the absence of unresolved safety concerns, the NRC regulatory program will not delay the executive branch's program as set forth in the DOE project decision schedule. The NRC role for the next several years will be to develop its licensing framework and to consult with DOE on its plans. An essential ingredient in the success of both NRC's and DOE's respective missions is the need for free and open exchange of information, which will assure us that the concerns of all parties are addressed. With regard to low-level radioactive waste, the states have the lead responsibility for disposal. The NRC also provides assistance to the states and compacts on such items as regulatory programs, site characterization, and mixed waste disposal. Another of the NRC's roles is in the management of uranium mill tailings. Currently, most of the NRC's attention is focused on ensuring adequate long-term stabilization of tailings

  7. Regulatory considerations for computational requirements for nuclear criticality safety

    International Nuclear Information System (INIS)

    Bidinger, G.H.

    1995-01-01

    As part of its safety mission, the U.S. Nuclear Regulatory Commission (NRC) approves the use of computational methods as part of the demonstration of nuclear criticality safety. While each NRC office has different criteria for accepting computational methods for nuclear criticality safety results, the Office of Nuclear Materials Safety and Safeguards (NMSS) approves the use of specific computational methods and methodologies for nuclear criticality safety analyses by specific companies (licensees or consultants). By contrast, the Office of Nuclear Reactor Regulation approves codes for general use. Historically, computational methods progressed from empirical methods to one-dimensional diffusion and discrete ordinates transport calculations and then to three-dimensional Monte Carlo transport calculations. With the advent of faster computational ability, three-dimensional diffusion and discrete ordinates transport calculations are gaining favor. With the proper user controls, NMSS has accepted any and all of these methods for demonstrations of nuclear criticality safety

  8. Nuclear Regulatory Commission Issuances, Volume 42, No. 2

    International Nuclear Information System (INIS)

    1995-08-01

    This report include the issuances received during the specificed period (August 1995) from the NRC, the Atomic Safety and Licensing Boards, the Administrative Law Judges, and the Decisions on Petitions for Rule Making. In these issuances, the following areas were addressed: (1) Emergency planning at the University of Missouri, (2) Transfer of operating license at Plant Vogtle, (3) Discriminatory action against a whistle-blower at Millstone Units 1 ampersand 2, (4) Regulatory issues related to embittlement and cracking at Oyster Creek, and (5) Age-related deterioration of reactor internals components at Pilgrim

  9. Nuclear Regulatory Commission probabilistic risk assessment implementation program: A status report

    International Nuclear Information System (INIS)

    Rubin, M.P.; Caruso, M.A.

    1996-01-01

    The US Nuclear Regulatory Commission (NRC) is undertaking a number of activities intended to increase the consideration of risk significance in its decision processes and the effective use of risk-based technologies in its regulatory activities. Although the NRC is moving toward risk-informed regulation throughout its areas of responsibilities, this paper focuses primarily on those issues associated with reactor regulation. As the NRC completed significant milestones in its development of probabilistic risk assessment (PRA) methodology and gained considerable experience in the limited application of risk assessment to selected regulatory activities, it became evident that a much broader use of risk informed approaches offered advantages to both the NRC and the US commercial nuclear industry. This desire to enhance the use of risk assessment is driven by the clear belief that application of PRA methods will result in direct improvements in nuclear power plant operational safety from the perspective of both the regulator and the plant operator. The NRC believed that an overall policy on the use of PRA methods in nuclear regulatory activities should be established so that the many potential applications of PRA could be implemented in a consistent and predictable manner that would promote regulatory stability and efficiency. This paper describes the key activities that the NRC has undertaken to implement the initial stages of an integrated risk-informed regulatory framework

  10. Action by the European Commission to promote nuclear safety outside the territory of the Union

    International Nuclear Information System (INIS)

    Joulia, J.P.

    2010-01-01

    The TACIS programme to improve nuclear safety in Central and Eastern Europe and the former USSR has now entered its final phase. A new programme 'the Instrument for Nuclear Safety Cooperation (INSC)' has been launched and its aim is to promote nuclear safety in all third-party countries. Support for improvement of the regulatory framework and the effectiveness of the bodies in charge of nuclear safety is a key element. Within the European Commission, the 'Europe, Southern Mediterranean, Middle East and Neighbourhood policy' Directorate, belonging to the AIDCO General Directorate, is tasked with implementation. (author)

  11. USNRC regulatory guidance for engineered safety feature air cleaning systems

    International Nuclear Information System (INIS)

    Bellamy, R.R.

    1991-01-01

    The need for clear, technically appropriate, and easily implementable guidance for the design, testing, and maintenance of nuclear air cleaning systems has long been recognized. Numerous industry consensus standards have been issued and revised over the last 30 years. Guidance has also been published by the US Nuclear Regulatory Commission in the form of regulations, regulatory guides, standard review plans, NUREG documents, and information notices. This paper will summarize the latest revisions to these documents and emphasize Regulatory Guide 1.52, Design, Testing, and Maintenance Criteria for Post-Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants, which was last revised in 1978. The USNRC has undertaken a project to revise this regulatory guide, and the status of that revision is highlighted

  12. The enforcement program of the nuclear regulatory commission in the United States

    International Nuclear Information System (INIS)

    Thornburg, H.D.

    1977-01-01

    The enforcement program of the United States Nuclear Regulatory Commission consists of a clearly spelled out, evenly applied program of deterrents which escalate according to the nature of the offense and the past history of the licensee's noncompliances. Ninety-eight percent of all enforcement actions are normally handled by the five Regional offices. Only one percent of noncompliances have been classed as violations where significant safety consequences occurred. A strong and timely enforcement program is essential to insure that licensees fulfill their obligations to protect the public and the environment. (Auth.) [fr

  13. Regulatory review of safety cases and safety assessments - associated challenges

    International Nuclear Information System (INIS)

    Bennett, D.G.; Ben Belfadhel, M.; Metcalf, P.E.

    2006-01-01

    Regulatory reviews of safety cases and safety assessments are essential for credible decision making on the licensing or authorization of radioactive waste disposal facilities. Regulatory review also plays an important role in developing the safety case and in establishing stakeholders' confidence in the safety of the facility. Reviews of safety cases for radioactive waste disposal facilities need to be conducted by suitably qualified and experienced staff, following systematic and well planned review processes. Regulatory reviews should be sufficiently comprehensive in their coverage of issues potentially affecting the safety of the disposal system, and should assess the safety case against clearly established criteria. The conclusions drawn from a regulatory review, and the rationale for them should be reproducible and documented in a transparent and traceable way. Many challenges are faced when conducting regulatory reviews of safety cases. Some of these relate to issues of project and programme management, and resources, while others derive from the inherent difficulties of assessing the potential long term future behaviour of engineered and environmental systems. The paper describes approaches to the conduct of regulatory reviews and discusses some of the challenges faced. (author)

  14. Regulatory control of radiation sources. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

  15. Indexes to Nuclear Regulatory Commission issuances, January--June 1993

    International Nuclear Information System (INIS)

    1993-11-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owner(s) of facility); Full text reference (volume and pagination); Issuance number; Issues raised by appellants; Legal citations (cases, regulations, and statutes); Name of facility, Docket number; Subject matter of issues and/or rulings; Type of hearing (for construction permit, operating license, etc.); Type of issuance (memorandum, order, decision, etc.). These information elements are displayed in one or more of five separate formats arranged as follows: (1) Case Name Index; (2) Digests and Headers; (3) Legal Citations Index; (4) Subject Index; (5) Facility Index

  16. Indexes to Nuclear Regulatory Commission issuances, July-December 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owner(s) of facility); Full text reference (volume and pagination); Issuance number Issues raised by appellants; Legal citations (cases, regulations, and statutes); Name of facility, Docket number; Subject matter of issues and/or rulings; Type of hearing (operating license, operating license amendment, etc); Type of issuance (memorandum, order, decision, etc.). These information elements are displayed in one or more of five separate formats: Case Name Index, Headers and Digests, Legal Citations Index, Subject Index, and Facility Index.

  17. Indexes to Nuclear Regulatory Commission issuances, July-December 1997

    International Nuclear Information System (INIS)

    1998-01-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owner(s) of facility); Full text reference (volume and pagination); Issuance number Issues raised by appellants; Legal citations (cases, regulations, and statutes); Name of facility, Docket number; Subject matter of issues and/or rulings; Type of hearing (operating license, operating license amendment, etc); Type of issuance (memorandum, order, decision, etc.). These information elements are displayed in one or more of five separate formats: Case Name Index, Headers and Digests, Legal Citations Index, Subject Index, and Facility Index

  18. Indexes to Nuclear Regulatory Commission issuances, July--December 1992

    International Nuclear Information System (INIS)

    1993-06-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Digests and Legal Citations Index, Subject Index, and Facility Index. Subject words and/or phrases arranged alphabetically, indicate the issues and subjects covered in the issuances. The subject headings are followed by phrases that give specific information about the subject, as discussed in the issuances being indexed. These phrases are followed by the issuance number and the full text reference

  19. 76 FR 7853 - Patient Safety Organizations: Voluntary Delisting From Oregon Patient Safety Commission

    Science.gov (United States)

    2011-02-11

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety Organizations: Voluntary Delisting From Oregon Patient Safety Commission AGENCY: Agency for Healthcare Research and Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: Oregon Patient Safety Commission: AHRQ...

  20. Indexes to Nuclear Regulatory Commission issuances, July--September 1992

    International Nuclear Information System (INIS)

    1993-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: 1. Case Name Index: The case name index is an alphabetical arrangement of the case names of the issuances. Each case name is followed by the type of hearing, the type of issuance, docket number, issuance number, and full text reference. 2. Digests and Headers: The headers and digests are presented in issuance number order as follows: the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The header identifies the issuance by issuance number, case name, facility name, docket number, type of hearing, date of issuance, and type of issuance. 3. Legal Citations Index: This index is divided into four parts and consists of alphabetical or alpha-numerical arrangements of Cases, Regulations, Statutes, and Others. These citations are listed as given in the issuances. Changes in regulations and statutes may have occurred to cause changes in the number or name and/or applicability of the citation. It is therefore important to consider the date of the issuance. 4. Subject Index: Subject words and/or phrases, arranged alphabetically, indicate the issues and subjects covered in the issuances. 5. Facility Index: The index consists of an alphabetical arrangement of facility names from the issuance. The name is followed by docket number, type of hearing, data, type of issuance, issuance number, and full text reference

  1. The Canadian Nuclear Safety Commission's financial guarantee requirements

    International Nuclear Information System (INIS)

    Ferch, R.

    2006-01-01

    The Nuclear Safety and Control Act gives the Canadian Nuclear Safety Commission (CNSC) the legal authority to require licensees to provide financial guarantees in order to meet the purposes of the Act. CNSC policy and guidance with regard to financial guarantees is outlined, and the current status of financial guarantee requirements as applied to various CNSC licensees is described. (author)

  2. Safety system upgrades to a research reactor: A regulatory perspective

    International Nuclear Information System (INIS)

    Lamarre, G.B.; Martin, W.G.

    2003-01-01

    The NRU (National Research Universal) reactor, located at the Chalk River Laboratories of Atomic Energy of Canada Limited (AECL), first achieved criticality November 3, 1957. AECL continues to operate NRU for research to support safety and reliability studies for CANDU reactors and as a major supplier of medical radioisotopes. Following a detailed systematic review and assessment of NRU's design and the condition of its primary systems, AECL formally notified the Canadian Nuclear Safety Commission's (CNSC) predecessor - the Atomic Energy Control Board - in 1992 of its intention to upgrade NRU's safety systems. AECL proposed seven major upgrades to provide improvements in shutdown capability, heat removal, confinement, and reactor monitoring, particularly during and after a seismic event. From a CNSC perspective, these upgrades were necessary to meet modern safety standards. From the start of the upgrades project, the CNSC provided regulatory oversight aimed at ensuring that AECL maintained a structured approach to the upgrades. The elements of the approach include, but are not limited to, the determination of project milestones and target dates; the formalization of the design process and project quality assurance requirements; the requirements for updated documentation, including safety reports, safety notes and commissioning reports; and the approval and authorization process. This paper details, from a regulatory perspective, the structured approach used in approving the design, construction, commissioning and subsequent operation of safety system upgrades for an existing and operating research reactor, including the many challenges faced when attempting to balance the requirements of the upgrades project with AECL's need to keep NRU operating to meet its important research and production objectives. (author)

  3. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  4. Regulatory activities in reactor safety

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1987-01-01

    The safety phylosophy in designs and operation of nuclear power plants and, the steps for evaluating the safety and quality assurance, in the licensing procedure are described. The CNEN organization structure and the licensing procedure for nuclear power plants in Brazil are presented. (M.C.K.) [pt

  5. Indexes to Nuclear Regulatory Commission issuance, July-December 1980. Index of Volume 12, Number 4

    International Nuclear Information System (INIS)

    1980-01-01

    Issuances of the Atomic Safety and Licensing Board (ASLB), the Atomic Safety and Licensing Appeal Boards (ALAB), the Administrative Law Judge (ALJ), regulatory issuances of the Commission (CLI), the Directors Denial (DD), and the Denials of Petitions for Rulemaking for the period July through December 1980 appear in Nuclear Regulatory Commission Issuances, 12 NRC No. 1, Pages 1-136, through 12 NRC No. 6, Pages 607-742. Digests and indexes for these issuances are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owners of facility); Name of facility, docket number; Type of hearing (for construction permit, operating licenses, etc.); Issues raised by appellants; Issuance number; Type of issuance (memorandum, order, decision, etc.); Issuance pagination; Legal citations (cases, regulations, and statutes); and Subject matter of issues and/or rulings. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index; Digests and headers; Legal citation index; Subject index; and Facility index

  6. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  7. China's nuclear safety regulatory body: The national nuclear safety administration

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1991-04-01

    The establishment of an independent nuclear safety regulatory body is necessary for ensuring the safety of nuclear installations and nuclear fuel. Therefore the National Nuclear Safety Administration was established by the state. The aim, purpose, organization structure and main tasks of the Administration are presented. At the same time the practical examples, such as nuclear safety regulation on the Qinshan Nuclear Power Plant, safety review and inspections for the Daya Bay Nuclear Power Plant during the construction, and nuclear material accounting and management system in the nuclear fuel fabrication plant in China, are given in order to demonstrate the important roles having been played on nuclear safety by the Administration after its founding

  8. 77 FR 9273 - WORKSHOP Sponsored by the Nuclear Regulatory Commission and the Electric Power Research Institute...

    Science.gov (United States)

    2012-02-16

    ... Commission and the Electric Power Research Institute on the Treatment of Probabilistic Risk Assessment.... SUMMARY: The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research (RES), in cooperation with the Electric Power Research Institute (EPRI), will hold a joint workshop on the Treatment of...

  9. 76 FR 61402 - Draft Nuclear Regulatory Commission Fiscal Year 2012-2016 Strategic Plan

    Science.gov (United States)

    2011-10-04

    ...-2016 Strategic Plan AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment... comment on draft NUREG-1614, Volume 5. ``U.S. Nuclear Regulatory Commission, FY 2012-2016 Strategic Plan,'' dated September 2011. The NRC's draft FY 2012-2016 strategic plan describes the agency's mission and...

  10. 77 FR 15142 - Updated Nuclear Regulatory Commission Fiscal Years 2008-2013 Strategic Plan

    Science.gov (United States)

    2012-03-14

    ... 2008-2013 Strategic Plan AGENCY: Nuclear Regulatory Commission. ACTION: Strategic plan. SUMMARY: The U...-1614, Volume 5, ``U.S. Nuclear Regulatory Commission, Fiscal Years [FY] 2008-2013 Strategic Plan,'' dated February 2012. The updated FY 2008-2013 strategic plan describes the agency's mission and...

  11. Regional and International Networking to Support the Energy Regulatory Commission of Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Lavansiri, Direk; Bull, Trevor

    2010-09-15

    The Energy Regulatory Commission of Thailand is a new regulatory agency. The structure of the energy sector; the tradition of administration; and, the lack of access to experienced personnel in Thailand all pose particular challenges. The Commission is meeting these challenges through regional and international networking to assist in developing policies and procedures that allow it to meet international benchmarks.

  12. Regulatory safety aspects of nuclear waste management operations in India

    International Nuclear Information System (INIS)

    Sundararajan, A.R.

    2000-01-01

    The Department of Atomic Energy in India as part of its programme to harness the nuclear energy for generation of nuclear power has been operating a whole range of nuclear fuel cycle facilities including waste management plants for more than four decades. The waste management plants include three high level waste immobilisation plants, one in operation, one under commissioning and one more under construction. Atomic Energy Regulatory Board is mandated to review and authorise from the safety angle the siting, the design, the construction and the operation of the waste management plants. The regulatory procedures, which involve multi-tier review adopted for ensuring the safety of these facilities, are described in this paper. (author)

  13. The EU commission and national governments as partners: EC regulatory expansion in telecommunications 1979-2000

    OpenAIRE

    Mark Thatcher

    2001-01-01

    Explicitly or implicitly, general models of European integration claim that EC regulatory expansion involves a struggle for power between Commission and national governments. The Commission is seen as a policy entrepreneur, taking the initiative to drive forward integration (Sandholtz and Zysman 1989). It seeks regulatory expansion due to constraints on its expenditure (Majone 1996, ch4). Neo-functionalists emphasise the Commission's ability to expand its role against the wishes of government...

  14. Safety regulation: The lessons of workplace safety rule management for managing the regulatory burden

    OpenAIRE

    Hale, A.R.; Borys, D.; Adams, M.

    2012-01-01

    There is a strong political consensus in a number of countries that occupational safety and health regulation is stifling industrial innovation and development and is feeding a culture of damaging risk aversion and petty bureaucracy. In a number of countries this has led to proposals to repeal regulations and reduce the regulatory burden. The authors were commissioned to prepare a discussion paper on this issue by the Mercatus Center of George Mason University in Arlington, Virginia, aimed pa...

  15. Safety of Nuclear Power Plants: Commissioning and Operation

    International Nuclear Information System (INIS)

    2011-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  16. Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  17. Safety of Nuclear Power Plants: Commissioning and Operation. Arabic Edition

    International Nuclear Information System (INIS)

    2011-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  18. Safety of Nuclear Power Plants: Commissioning and Operation (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  19. Leak testing United States Nuclear Regulatory Commission type b packaging

    International Nuclear Information System (INIS)

    Lacy, K.A.

    1995-01-01

    The Waste Isolation Pilot Plant (WTPP) is a one of its kind research and development facility operated by the Department of Energy, Carlsbad Area Office. Located in southeastern New Mexico, the WTPP is designed to demonstrate the safe, permanent disposal of transuranic (TRU) radioactive nuclear waste, accumulated from 40 years of nuclear weapons production. Before the waste can be disposed of, it must first be safely transported from generator storage sites to the WIPP. To accomplish this, the TRUPACT-II was designed and fabricated. This double containment, non-vented waste packaging successfully completed a rigorous testing program, and in 1989 received a Certificate of Compliance (C of C) from the Nuclear Regulatory Commission (NRC). Currently, the TRUPACT-II is in use at Idaho National Engineering Laboratory to transport waste on site for characterization. The DOE/CAO is responsible for maintaining the TRUPACT-II C of C. The C of C requires performance of nondestructive examination (NDE), e.g., visual testing (VT), dimensional inspections, Liquid Dye Penetrant testing (PT), and Helium Leak Detection (HLD). The Waste Isolation Division (WID) uses HLD for verification of the containment integrity. The following HLD tests are performed on annual basis or when required, i.e. repairs or component replacement: (1) fabrication verification leak tests on both the outer containment vessel (OCV) and the inner containment vessel (ICV); (2) assembly verification leak tests on the OCV and ICV upper main o-rings; and (3) assembly verification leak tests on the OCV and the ICV vent port plugs. These tests are addressed in detail as part of this presentation

  20. Safety of Nuclear Power Plants: Commissioning and Operation

    International Nuclear Information System (INIS)

    2011-01-01

    The safety of a nuclear power plant is ensured by means of proper site selection, design, construction and commissioning, and the evaluation of these, followed by proper management, operation and maintenance of the plant. In a later phase, a proper transition to decommissioning is required. The organization and management of plant operations ensures that a high level of safety is achieved through the effective management and control of operational activities. This publication is a revision of the Safety Requirements publication Safety of Nuclear Power Plants: Operation, which was issued in 2000 as IAEA Safety Standards Series No. NS-R-2. The purpose of this revision was to restructure Safety Standards Series No. NS-R-2 in the light of new operating experience and new trends in the nuclear industry; to introduce new requirements that were not included in Safety Standards Series No. NS-R-2 on the operation of nuclear power plants; and to reflect current practices, new concepts and technical developments. This update also reflects feedback on the use of the standards, both from Member States and from the IAEA's safety related activities. The publication is presented in the new format for Safety Requirements publications. The present publication reflects the safety principles of the Fundamental Safety Principles. It has been harmonized with IAEA Safety Standards Series No. GS-R-3 on The Management System for Facilities and Activities. Guidance on the fulfilment of the safety requirements is provided in supporting Safety Guides. The terminology used in this publication is defined and explained in the IAEA Safety Glossary. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This

  1. Environment, safety, and health regulatory implementation plan

    International Nuclear Information System (INIS)

    1993-01-01

    To identify, document, and maintain the Uranium Mill Tailings Remedial Action (UMTRA) Project's environment, safety, and health (ES ampersand H) regulatory requirements, the US Department of Energy (DOE) UMTRA Project Office tasked the Technical Assistance Contractor (TAC) to develop a regulatory operating envelope for the UMTRA Project. The system selected for managing the UMTRA regulatory operating envelope data bass is based on the Integrated Project Control/Regulatory Compliance System (IPC/RCS) developed by WASTREN, Inc. (WASTREN, 1993). The IPC/RCS is a tool used for identifying regulatory and institutional requirements and indexing them to hardware, personnel, and program systems on a project. The IPC/RCS will be customized for the UMTRA Project surface remedial action and groundwater restoration programs. The purpose of this plan is to establish the process for implementing and maintaining the UMTRA Project's regulatory operating envelope, which involves identifying all applicable regulatory and institutional requirements and determining compliance status. The plan describes how the Project will identify ES ampersand H regulatory requirements, analyze applicability to the UMTRA Project, and evaluate UMTRA Project compliance status

  2. Regulatory Safety Requirements for Operating Nuclear Installations

    International Nuclear Information System (INIS)

    Gubela, W.

    2017-01-01

    The National Nuclear Regulator (NNR) is established in terms of the National Nuclear Regulator Act (Act No 47 of 1999) and its mandate and authority are conferred through sections 5 and 7 of this Act, setting out the NNR's objectives and functions, which include exercising regulatory control over siting, design, construction etc of nuclear installations through the granting of nuclear authorisations. The NNR's responsibilities embrace all those actions aimed at providing the public with confidence and assurance that the risks arising from the production of nuclear energy remain within acceptable safety limits -> Therefore: Set fundamental safety standards, conducting pro-active safety assessments, determining licence conditions and obtaining assurance of compliance. The promotional aspects of nuclear activities in South Africa are legislated by the Nuclear Energy Act (Act No 46 of 1999). The NNR approach to regulations of nuclear safety and security take into consideration, amongst others, the potential hazards associated with the facility or activity, safety related programmes, the importance of the authorisation holder's safety related processes as well as the need to exercise regulatory control over the technical aspects such as of the design and operation of a nuclear facility in ensuring nuclear safety and security. South Africa does not have national nuclear industry codes and standards. The NNR is therefore non-prescriptive as it comes to the use of industry codes and standards. Regulatory framework (current) provide for the protection of persons, property, and environment against nuclear damage, through Licensing Process: Safety standards; Safety assessment; Authorisation and conditions of authorisation; Public participation process; Compliance assurance; Enforcement

  3. Regulatory Activities on Civil Nuclear Safety Equipment in China

    International Nuclear Information System (INIS)

    Gaoshang, Lu; Choi, Kwang Sik

    2011-01-01

    It is stipulated in IAEA Fundamental Safety Principles (SF1) that the fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. The fundamental safety objective applies for all facilities and activities and for all stages over the lifetime of a facility or radiation source, including planning, sitting, design, manufacturing, construction, commissioning and operation, as well as decommissioning and closure. So, according to the requirement, the related activities such as design, manufacturing, installation and non-destructive test that conducted on civil nuclear equipment should be well controlled by the vendors, the owner of the nuclear power plants and the regulatory body. To insure the quality of those equipment, Chinese government had taken a series of measures to regulate the related activities on them

  4. US Nuclear Regulatory Commission organization charts and functional statements

    International Nuclear Information System (INIS)

    1996-01-01

    This document is the US NRC organizational structure and chart as of July 1, 1996. It contains the org charts for the Commission, ACRS, ASLAB, Commission staff offices, Executive Director for Operations, Office of the Inspector General, Program offices, and regional offices

  5. US Nuclear Regulatory Commission organization charts and functional statements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    This document is the US NRC organizational structure and chart as of July 1, 1996. It contains the org charts for the Commission, ACRS, ASLAB, Commission staff offices, Executive Director for Operations, Office of the Inspector General, Program offices, and regional offices.

  6. 39 CFR Appendix A to Part 3002 - Postal Regulatory Commission, Mission Statement of the Office of the Consumer Advocate

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Postal Regulatory Commission, Mission Statement of the Office of the Consumer Advocate A Appendix A to Part 3002 Postal Service POSTAL REGULATORY COMMISSION PERSONNEL ORGANIZATION Pt. 3002, App. A Appendix A to Part 3002—Postal Regulatory Commission, Mission Statement of the Office of the Consumer...

  7. Enhancement of Nuclear Safety in Korea: A Regulatory Perspective

    International Nuclear Information System (INIS)

    Chung, K.Y.

    2016-01-01

    In the aftermath of Fukushima Daiichi accident in 2011 Korean regulatory body immediately performed special inspections on nuclear power plants (NPPs) and a research reactor in Korea, and issued an enforcement order for the licensees to implement fifty Fukushima action items to address the safety issues identified by the inspections. Subsequently, the licensees have established the implementation plans for resolution of the action items. By the implementation of the action items, the possibility of severe accident due to the extreme hazards has been greatly reduced and the capabilities to mitigate the severe accident, should it occur, have been upgraded. To improve the consistency and predictability of the regulation on severe accidents, Nuclear Safety and Security Commission (NSSC) the regulatory body in Korea, is revising the regulatory framework for severe accidents. The new framework will require the licensee to enhance the capabilities for prevention and mitigation of severe accidents in view of the defence in depth principle, to assess the radiological effects from the severe accidents, and to improve current accident management procedures and guidelines necessary for the prevention and mitigation of severe accidents. This rulemaking also considers the safety principles provided by the IAEA Vienna Declaration in 2015, which require new NPPs to prevent large radioactive releases. (author)

  8. Report to the US Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data, 1986

    International Nuclear Information System (INIS)

    1987-05-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during calendar year 1986. Comments and observations are provided on operating experience at nuclear power plants and other NRC licensees, including results from selected AEOD studies; summaries of abnormal occurrences involving US nuclear plants; reviews of licensee event reports and their quality, reactor scram experience from 1984 to 1986, engineered safety features actuations, and the trends and patterns analysis program; and assessments of nonreactor and medical misadministration events. In addition, the report provides the year-end status of all recommendations included in AEOD studies, and listings of all AEOD reports issued from 1980 through 1986

  9. Reactor aging research. United States Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Vassilaros, M.G.

    1998-01-01

    The reactor ageing research activities in USA described, are focused on the research of reactor vessel integrity, including regulatory issues and technical aspects. Current emphasis are described for fracture analysis, embrittlement research, inspection capabilities, validation od annealing rule, revision of regulatory guide

  10. Quantitative safety goals for the regulatory process

    International Nuclear Information System (INIS)

    Joksimovic, V.; O'Donnell, L.F.

    1981-01-01

    The paper offers a brief summary of the current regulatory background in the USA, emphasizing nuclear, related to the establishment of quantitative safety goals as a way to respond to the key issue of 'how safe is safe enough'. General Atomic has taken a leading role in advocating the use of probabilistic risk assessment techniques in the regulatory process. This has led to understanding of the importance of quantitative safety goals. The approach developed by GA is discussed in the paper. It is centred around definition of quantitative safety regions. The regions were termed: design basis, safety margin or design capability and safety research. The design basis region is bounded by the frequency of 10 -4 /reactor-year and consequences of no identifiable public injury. 10 -4 /reactor-year is associated with the total projected lifetime of a commercial US nuclear power programme. Events which have a 50% chance of happening are included in the design basis region. In the safety margin region, which extends below the design basis region, protection is provided against some events whose probability of not happening during the expected course of the US nuclear power programme is within the range of 50 to 90%. Setting the lower mean frequency to this region of 10 -5 /reactor-year is equivalent to offering 90% assurance that an accident of given severity will not happen. Rare events with a mean frequency below 10 -5 can be predicted to occur. However, accidents predicted to have a probability of less than 10 -6 are 99% certain not to happen at all, and are thus not anticipated to affect public health and safety. The area between 10 -5 and 10 -6 defines the frequency portion of the safety research region. Safety goals associated with individual risk to a maximum-exposed member of public, general societal risk and property risk are proposed in the paper

  11. Nuclear Regulatory Commission staff approaches to improving the integration of regulatory guidance documents and prelicensing reviews

    International Nuclear Information System (INIS)

    Johnson, R.L.

    1994-01-01

    The Nuclear Regulatory Commission staff is conducting numerous activities to improve the integration of its regulatory guidance documents (i.e., License Application Review Plan (LARP) and open-quotes Format and Content for the License Application for the High-Level Waste repositoryclose quotes (FCRG)) and pre-license application (LA) reviews. Those activities related to the regulatory guidance documents consist of: (1) developing an hierarchy of example evaluation findings for LARP; (2) identifying LARP review plan interfaces; (3) conducting an integration review of LARP review strategies; (4) correlating LARP to the ongoing technical program; and (5) revising the FCRG. Some of the more important strategies the staff is using to improve the integration of pre-LA reviews with the LA review include: (1) use of the draft LARP to guide the staff's pre-LA reviews; (2) focus detailed pre-LA reviews on key technical uncertainties; (3) identify and track concerns with DOE's program; and (4) use results of pre-LA reviews in LA reviews. The purpose of this paper is to describe these ongoing activities and strategies and discuss some of the new work that is planned to be included in LARP Revision 1 and the final FCRG, which are scheduled to be issued in late 1994. These activities reflect both the importance the staff has placed on integration and the staff's approach to improving integration in these areas. The staff anticipates that the results of these activities, when incorporated in the FCRG, LARP, and pre-LA reviews, will improve its guidance for DOE's ongoing site characterization program and LA annotated outline development

  12. Study of the Nuclear Regulatory Commission's Appellate System

    International Nuclear Information System (INIS)

    Bickwit, L.; Malsch, M.; Ostrach, S.; Christenson, K.

    1979-12-01

    At the Chairman's request the Office of the General Counsel studied the Commission's appellate system. The study included examination of the development of the study, analysis of the current workload, investigation of the practices of other agencies, and consideration of alternatives to the present system. The study recommends retention of the present system with some limited modifications to enable the Commission to more effectively use its existing appellate powers

  13. Research program on regulatory safety research

    International Nuclear Information System (INIS)

    Mailaender, R.

    2010-02-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning regulatory nuclear safety research, as co-ordinated by the Swiss Nuclear Safety Inspectorate ENSI. Work carried out in various areas is reviewed, including that done on reactor safety, radiation protection and waste disposal as well as human aspects, organisation and safety culture. Work done concerning materials, pressure vessel integrity, transient analysis, the analysis of serious accidents in light-water reactors, fuel and material behaviour, melt cooling and concrete interaction is presented. OECD data bank topics are discussed. Transport and waste disposal research at the Mont Terri rock laboratory is looked at. Requirements placed on the personnel employed in nuclear power stations are examined and national and international co-operation is reviewed

  14. First update to the US Nuclear Regulatory Commission's regulatory strategy for the high-level waste repository program

    International Nuclear Information System (INIS)

    Johnson, R.L.; Linehan, J.J.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) staff has updated its initial regulatory strategy for the High-Level Waste Repository Licensing Program. The update describes changes to the initial strategy and summarizes progress and future activities. This paper summarizes the first update of the regulatory strategy. In general the overall strategy of identifying and reducing uncertainties is unchanged. Identifying regulatory and institutional uncertainties is essentially complete, and therefore, the current and future emphasis is on reducing those regulatory and institutional uncertainties identified to date. The NRC staff has improved the methods of reducing regulatory uncertainties by (1) enhancing the technical basis preparation process for potential rulemakings and guidance and (2) designing a new guidance document, called a staff position, for clarifying regulatory uncertainties. For guiding the US DOE's reduction of technical uncertainties, the NRC staff will give more emphasis to prelicense application reviews and less emphasis on preparing staff technical positions

  15. Regulatory Oversight of Safety Culture — Korea’s Experience

    International Nuclear Information System (INIS)

    Jung, S.J.; Choi, Y.S.; Kim, J.T.

    2016-01-01

    In Korea, a regulatory oversight program of safety culture was launched in 2012 to establish regulatory measures against several events caused by weak safety culture in the nuclear industry. This paper is intended to introduce the preliminary regulatory oversight framework, development and validation of safety culture components, pilot safety culture inspection results and lessons learned. The safety culture model should be based on a sound understanding of the national culture and industry characteristics where the model will be applied. The nuclear safety culture oversight model is being developed and built on the Korean regulatory system to independently assess the nuclear power operating organizations’ safety culture.

  16. Discussion on building safety culture inside a nuclear safety regulatory body

    International Nuclear Information System (INIS)

    Fan Yumao

    2013-01-01

    A strong internal safety culture plays a key role in improving the performance of a nuclear regulatory body. This paper discusses the definition of internal safety culture of nuclear regulatory bodies, and explains the functions that the safety culture to facilitate the nuclear safety regulation and finally puts forward some thoughts about building internal safety culture inside regulatory bodies. (author)

  17. Independent Commission for Radiological Protection and Nuclear Safety CIPRSN: Balance, obligations and future prospects

    International Nuclear Information System (INIS)

    Gieb, M.; Meruje, M. M; Sena Lino, A.

    2010-01-01

    This article summarizes the historical context of the regulatory situation in Portugal that led to the creation of the technical team of the Independent Commission for Radiological Protection and Nuclear Safety (CIPRSN), recalls its early works, and highlights the current work of some members of the team on the self-assessment of the national regulatory system of radiological protection and nuclear safety. The result of this self-assessment allows a detailed analysis of current problems and makes it possible to outline the future work plan of the technical team. It is hoped that this work may contribute to an improvement of the system, especially in view of new international and European legal instruments which are currently under implementation. (author)

  18. US Nuclear Regulatory Commission organization charts and functional statements

    International Nuclear Information System (INIS)

    1996-01-01

    This document is the organizational chart for the US NRC. It contains organizational structure and functional statements for the following: (1) the Commission, (2) committees and boards, (3) staff offices, (4) office of the Inspector General, (5) executive director for operations, (6) program offices, and (7) regional offices

  19. US Nuclear Regulatory Commission organization charts and functional statements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-19

    This document is the organizational chart for the US NRC. It contains organizational structure and functional statements for the following: (1) the Commission, (2) committees and boards, (3) staff offices, (4) office of the Inspector General, (5) executive director for operations, (6) program offices, and (7) regional offices.

  20. U.S. Nuclear Regulatory Commission, annual report, 1978

    International Nuclear Information System (INIS)

    1978-01-01

    The report contains the following chapters: (1) overview and summary, (2) reactor regulation, (3) materials regulation, (4) domestic safeguards, (5) waste management, (6) injection and enforcement, (7) operating experience, (8) state programs, (9) international activities, (10) standards development, (11) regulatory research, (12) informing and involving the public, (13) proceedings and litigation, and (14) administration and mangement

  1. Nuclear regulatory commission issuances. Volume 40, Number 1

    International Nuclear Information System (INIS)

    1994-07-01

    This report includes issuances concerning the following items. The Commission denies General Atomics' motion seeking to stay discovery in this proceeding until (1) the Commission determines whether it will grant General Atomics' Petition for Review of LBP-94-17 and/or Motion for Directed Certification; and (2) assuming that the commission grants the Petition/Motion, the Commission determines with finality the jurisdictional issues raised in General Atomics' previously filed Motion for Summary Disposition or for an Order of Dismissal. In this proceeding concerning an NRC Staff enforcement order issues in accordance with 10 C.F.R. section 2.202, the Licensing Board concludes that a Native American tribe wishing to participate in the proceeding to support the Staff's enforcement order has established its standing and presented two litigable contentions. This informal adjudicatory proceeding, convened under 10 C.F.R. Part 2, Subpart L, involves an application by the Chemetron Corporation (Licensee) for a license amendment. The proposed amendment concerns the decommissioning of the Licensee's Bert Avenue site in Newburgh Heights, Ohio, and its Harvard Avenue site and associated buildings at the McGean-Rohco property in Cuyahoga Heights, Ohio. In this license suspension and modification enforcement proceeding, the Licensing Board rules on prediscovery dispositive motions regarding ten issues specified by the parties for litigation. The Licensing Board determines that an Intervenor may move to admit into the proceeding a new basis for an already admitted contention. When it does so, the requirements for a late-filed contention are not applicable, but the Intervenor must show that it is timely to consider the new basis, in light of its seriousness and the timelines with which it has been raised. The Licensing Board also permitted Intervenor to file a reply to Applicant's response to his motion to add a new basis to his contention

  2. European Commission action aimed at constructing a European regulatory framework

    International Nuclear Information System (INIS)

    Ristori, D.

    2010-01-01

    The challenge of a low-carbon economy provides a new incentive for the development of renewable energies as well as of nuclear energy. The latter calls for a high level of safety and security. The EU has a role in providing a legal framework for this purpose as well as ensuring that these standards are respected internationally. For over 50 years the EURATOM Treaty has offered the legal basis for a wide range of initiatives supporting this policy. The EU has competences under chapter 3, 'Health and Safety', for the establishment of basic safety standards for the protection against ionizing radiation. These have extended beyond the scope of nuclear energy and now include medical exposures as well as natural radiation sources. The latest revision of the BSS-Directive, to be proposed in 2011, was an opportunity for the consolidation of all Community legislation. A ruling of the Court of Justice in 1999 paved the way for the establishment of standards on the safety of nuclear installations. A common vision on this matter was achieved through the creation of a body of European Safety Regulators (ENSREG) and the adoption of a specific Safety Directive in 2009. This new Directive translates internationally agreed safety standards into legally binding EU legislation and strengthens the position of national Regulators. (author)

  3. Regulatory risk control through mandatory occupational safety and health (OSH) certification and testing regimes (CTRs)

    NARCIS (Netherlands)

    Zwetsloot, G.I.J.M.; Hale, A.; Zwanikken, S.

    2011-01-01

    Governments make increasing use of private certification and testing infrastructures as an alternative for traditional regulatory arrangements in several areas including occupational safety and health (OSH).This research, commissioned by the Dutch Inspectorate for Work and Income (IWI), concerns an

  4. Regulatory system reform of occupational health and safety in China.

    Science.gov (United States)

    Wu, Fenghong; Chi, Yan

    2015-01-01

    With the explosive economic growth and social development, China's regulatory system of occupational health and safety now faces more and more challenges. This article reviews the history of regulatory system of occupational health and safety in China, as well as the current reform of this regulatory system in the country. Comprehensive, a range of laws, regulations and standards that promulgated by Chinese government, duties and responsibilities of the regulatory departments are described. Problems of current regulatory system, the ongoing adjustments and changes for modifying and improving regulatory system are discussed. The aim of reform and the incentives to drive forward more health and safety conditions in workplaces are also outlined.

  5. Nuclear Regulatory Commission issuances, July 1996: Volume 44, No. 1

    International Nuclear Information System (INIS)

    1996-07-01

    This report includes the issuances received during this period from NRC, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

  6. Regulatory Control of Radiation Sources. Safety Guide (Arabic Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This Safety Guide is intended to assist States in implementing the requirements established in Safety Standards Series No. GS-R-1, Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, for a national regulatory infrastructure to regulate any practice involving radiation sources in medicine, industry, research, agriculture and education. The Safety Guide provides advice on the legislative basis for establishing regulatory bodies, including the effective independence of the regulatory body. It also provides guidance on implementing the functions and activities of regulatory bodies: the development of regulations and guides on radiation safety; implementation of a system for notification and authorization; carrying out regulatory inspections; taking necessary enforcement actions; and investigating accidents and circumstances potentially giving rise to accidents. The various aspects relating to the regulatory control of consumer products are explained, including justification, optimization of exposure, safety assessment and authorization. Guidance is also provided on the organization and staffing of regulatory bodies. Contents: 1. Introduction; 2. Legal framework for a regulatory infrastructure; 3. Principal functions and activities of the regulatory body; 4. Regulatory control of the supply of consumer products; 5. Functions of the regulatory body shared with other governmental agencies; 6. Organization and staffing of the regulatory body; 7. Documentation of the functions and activities of the regulatory body; 8. Support services; 9. Quality management for the regulatory system.

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

    International Nuclear Information System (INIS)

    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

  8. Regulatory regime and its influence in the nuclear safety

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1999-01-01

    Main elements of nuclear regulatory regime in general is presented. These elements are: national rules and safety regulations, system of nuclear facility licensing, activities of regulatory body. Regulatory body is needed to specify the national safety regulations, review and assess the safety documentation presented to support license application, make inspections to verify fulfilment of safety regulations and license conditions, monitor the quality of work processes of user organization, and to assess whether these processes provide a high safety level, promote high safety culture, promote maintenance and development of national infrastructure relevant to nuclear safety, etc

  9. Safety evaluation report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission for U.S. Energy Research and Development Administration Light Water Breeder Reactor. Special project No. 561

    International Nuclear Information System (INIS)

    1976-07-01

    The Safety Evaluation Report is presented for the Light Water Breeder Reactor (LWBR). The LWBR core is to be installed in the Shippingport reactor at the Shippingport Atomic Power Station. The Safety Evaluation Report is the result of an NRC staff review of the LWBR Safety Analysis Report submitted by the Division of Naval Reactors, U. S. Energy Research and Development Administration. As a result of its review, the NRC staff has recommended that: (1) a diverse trip signal, such as containment high pressure, be included in a 2-out-of-3 logic for initiation of safety injection; (2) power be locked out from the pressurizer surge isolation valve during normal operation; and (3) a chlorine monitor be installed in the main control room

  10. Challenges and Enhancements to the Safety Culture of the Regulatory Body

    International Nuclear Information System (INIS)

    Niel, Jean-Christophe; Chevet, Pierre Franck; Sheron, Brian; Boyd, Michael; Carlsson, Lennart; Tiippana, Petteri; Burns, Stephen; Jamieson, Terry; Fuketa, Toyoshi; Rzentkowski, Greg; Weiss, Frank Peter; Le Guen, Bernard

    2015-06-01

    The workshop opened with presentations by both the NEA Director-General and the chair of the three committees directly involved with the safety culture of the regulatory body (SCRB). The opening session set the scene and gave an overview of the SCRB together with presentations and discussions on priorities and challenges. The main session focused on the principles of the SCRB, its implementation and the challenges and enhancements that are being raised and considered. The workshop concluded with a session that looked at findings and conclusions, the way forward and an agreed position on the SCRB. This document brings together the available presentations (slides) given at the workshop: 1 - Introduction: Challenges and Enhancements to the Safety Culture of the Regulatory Body (J-C. Niel); 2 - Thoughts on Safety Culture from a CSNI Perspective (B. Sheron); 3 - Radiological Protection Culture: CRPPH Work (M. Boyd); 4 - Challenges and Enhancements to Safety Culture of the Regulatory Body (L. Carlsson); 5 - Principles for the safety culture of the regulatory body (P. Tiippana); 6 - NRC's Internal Safety Culture: Successes, Challenges, and the Path Forward (S.G. Burns); 7 - Insights on the Canadian Nuclear Safety Commission's Safety Culture Journey (T. Jamieson); 8 - Lessons Learned from the Fukushima Dai-ichi Accident regarding Safety Culture of Regulatory Body (T. Fuketa); 9 - Challenges to Regulatory Bodies' safety culture (P-F. Chevet); 10 - Regulatory Safety Culture: International Perspective (G. Rzentkowski); 11 - Integration of Safety Research into Safety Culture Concepts (F-P. Weiss); 12 - Radiation Protection and Emergency Management Aspects: Culture drawn up by RP professionals (B. Le Guen); 13 - Closing session panel (L. Carlsson)

  11. Strengthening of the nuclear safety regulatory body. Field evaluation review

    International Nuclear Information System (INIS)

    1996-10-01

    As a result of a request from the Preparation Committee of the Nuclear Regulatory Authority (NRA) in 1992, and as recommended by the CEC/RAMG (Commission of European Communities/Regulatory Assistance Management Group) and the Agency mission in July 1993 to the Slovak Republic, the project SLR/9/005 was approved in 1993 as a model project for the period 1994-1996. Current budge is $401,340 and disbursements to date amount to $312,873. The project time schedule has been extended to 1997. The major conclusions of this evaluation are as follows: The project responded to an urgent national need, as well as to a statutory mandate of the Agency, and was adequately co-ordinated with other international assistance programmes to NRA. The project was designed as a structured programme of assistance by means of expert missions, scientific visits and a limited amount of equipment, acting upon several key areas of NRA regulatory responsibilities. Agency assistance was provided in a timely manner. A high concentration of expert missions was noticed at the initial stages of the project, which posed some managements problems. This was corrected to some extent in the course of implementation. Additionally, some overlapping of expert mission recommendations suggests that improvements are needed in the design of such missions. The exposure to international regulatory practice and expertise has resulted in substantial developments of NRA, both in organizational and operational terms. The project can claim to have contributed to NRA having gained governmental and international confidence. NRA's role in the safety assessment of Bohunice V1 reconstruction, as well as in Bohunice V2 safety review, Bohunice A1 decommissioning and in informing the public, also points at the success achieved by the project. The institutional and financial support of the Government contributed decisively to the project achievements. (author). Figs, tabs

  12. Outreach at the Canadian Nuclear Safety Commission - An Aboriginal Peoples' Perspective

    International Nuclear Information System (INIS)

    Lojk, R.; Ben Belfakhel, M.

    2006-01-01

    Established by the Nuclear Safety and Control Act (NSCA) that came into force in May 2000, the Canadian Nuclear Safety Commission (CNSC) is an independent federal agency that reports to Parliament through the Minister of Natural Resources. The CNSC regulates all uses of nuclear energy and nuclear materials from the production, to use, to the final disposition of any nuclear substances. Under the NSCA, the CNSC has the mandate to: - Regulate the development, production and use of nuclear energy and materials to protect the health, safety, security and environment; - Regulate production, possession and use of nuclear substances, prescribed equipment and prescribed information; - Implement measures respecting international commitments on the peaceful use of nuclear energy and substances; - Disseminate scientific, technical and regulatory information concerning CNSC activities. The main regulatory activities include setting regulatory standards, issuing licenses, verifying compliance and communicating with stakeholders and the public. These activities are accomplished by the work of two independent entities: a commission of up to seven members and a staff of about 500 employees. The Commission is an independent, quasi-judicial tribunal that provides licensing decisions on nuclear-related activities in a public forum. The President of the tribunal is the CEO of the CNSC staff organization. CNSC's regulatory philosophy is based on two principles: - Those persons and organizations subject to the NSCA and its Regulations are directly responsible for ensuring that the regulated activities that they engage in are managed so as to protect health, safety, security and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. - The CNSC is responsible to the public for regulating persons and organisations subject to the Nuclear Safety and Control Act and regulations to assure that they are properly discharging their obligations

  13. Battelle's human factors program for the US Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Shikiar, R.

    1983-10-01

    Battelle has been involved in a programmatic effort of technical assistance to the Division of Human Factors Safety of the NRC. This program involves the efforts of over 75 professionals engaged in over 20 projects. These projects span the areas of human factors engineering, procedures, examinations, training, staffing and qualifications, and utility management and organization. All of these bear, one way or another, on the role of operators in nuclear power plants. This programmatic effort can be viewed as part of an integrative approach to system safety

  14. Nuclear Regulatory Commission Issuances. Volume 42, No. 1, Pages 1--45

    International Nuclear Information System (INIS)

    1995-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation.

  16. Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1

    International Nuclear Information System (INIS)

    1995-01-01

    This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation

  17. The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

    2006-07-01

    The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

  18. Nuclear Regulatory Commission issuances. Volume 40, Number 5

    International Nuclear Information System (INIS)

    1994-11-01

    This book contains issuances of the Atomic Safety and Licensing Boards for November 1994. The issuances include Cameo Diagnostic Centre, Inc. byproduct material license; Georgia Power Company license amendment, transfer to Southern Nuclear for Vogtle Electric Generating Plant, units 1 and 2; Indiana Regional Cancer Center, order modifying and suspending byproduct material license; Louisiana Energy Services, special nuclear material license; Pacific Gas and Electric Company, construction period recovery, facility operating license, Diablo Canyon Nuclear Power plant; and Sequoyah Fuels Corporation, source materials license

  19. IAEA Mission Says Chile Committed to Enhancing Safety, Sees Regulatory Challenges

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said Chile is committed to strengthening its regulatory framework for nuclear and radiation safety. To help achieve this aim, the team said the country should address challenges in some areas, including the need to ensure effective independence in regulatory decision-making. The Integrated Regulatory Review Service (IRRS) team today concluded a 12-day mission to assess the regulatory safety framework in Chile. The mission was conducted at the request of the Government and hosted by the Chilean Nuclear Energy Commission (CCHEN), which is responsible for regulatory supervision together with the Ministry of Health (MINSAL). The review mission covered all civilian nuclear and radiation source facilities and activities regulated in Chile.

  20. U.S. Nuclear Regulatory Commission bases for control of solid materials

    International Nuclear Information System (INIS)

    Meck, R.A.; Cardille, F.P.; Feldman, C.; Gnugnoli, G.N.; Huffert, A.M.; Klementowicz, S.P.

    2002-01-01

    The U.S. Nuclear Regulatory Commission (NRC) is considering whether to proceed with rulemaking on the control of solid materials with very low levels of associated radioactivity. The current implementation of clearance by NRC licensees is the context for the decision. Inputs to the decision include information gathering efforts of the Commission in the areas of public workshops, dose assessments and inventories, the recommendations of the National Academies' National Research Council (NAs) on regulatory alternatives, and participation in international efforts by the International Atomic Energy Agency (IAEA). (author)

  1. Nuclear Regulatory Commission authorizations for Fiscal Years 1984 and 1985. House of Representatives, Ninety-Eighth Congress, First Session

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    H.R. 2510, as amended, authorizes $466.8 million to cover Nuclear Regulatory Commission salaries and expenses for fiscal year 1984 and $460 million for the following year in a two-year authorization. The bill substitutes certain expenditures for those recommended in the NRC request, while keeping the funding level the same. The committee report reviews and summarizes the two-year budget appropriation and the hearings before giving a section-by-section analysis. It notes that 46% is earmarked for waste management, and emphasizes the safety factors which have caused delays in construction and modifications in existing plants. 13 tables

  2. Regulatory oversight on nuclear safety in Taiwan

    Energy Technology Data Exchange (ETDEWEB)

    Huang, T-T. [Atomic Energy Council, New Taipei City, Taiwan (China)

    2014-07-01

    Taiwan is a densely populated island and over 98% of its energy is imported, 16.5% of which is nuclear, in the form of materials and services. Ensuring that the most stringent nuclear safety standards are met therefore remains a priority for the government and the operator, Taiwan power Company (Taipower). There are eight nuclear power reactors in Taiwan, six of which are in operation and two are under construction. The first began operating nearly 40 years ago. For the time being the issue of whether to decommission or extend life of the operating units is also being discussed and has no conclusion yet. Nuclear energy has been a hot issue in debate over the past decades in Taiwan. Construction of Lungmen nuclear power plant, site selection of a final low-level waste disposal facility, installation of spent fuel dry storage facilities and safety of the currently operating nuclear power reactors are the issues that all Taiwanese are concerned most. In order to ensure the safety of nuclear power plant, the Atomic Energy Council (AEC) has implemented rigorous regulatory work over the past decades. After the Fukushima accident, AEC has conducted a reassessment program to re-evaluate all nuclear power plants in Taiwan, and asked Taipower to follow the technical guidelines, which ENSREG has utilized to implement stress test over nuclear power plants in Europe. In addition, AEC has invited two expert teams from OECD/NEA and ENSREG to conduct peer reviews of Taiwan's stress test national report in 2013. My presentation will focus on activities regulating safety of nuclear power programs. These will cover (A) policy of nuclear power regulation in Taiwan, (B)challenges of the Lungmen Plant, (C) post-Fukushima safety re-assessment, and (D)radioactive waste management. (author)

  3. Report by USSR survey mission of Nuclear Safety Commission

    International Nuclear Information System (INIS)

    1990-01-01

    The USSR survey mission of Nuclear Safety Commission drew up and presents the report as follows. In relation to the accident in Chernobyl Nuclear Power Station in USSR, in order to investigate into the present status of the countermeasures for nuclear power safety in USSR and to exchange opinion, the USSR survey mission inspected nuclear power station facilities and visited the government organs, research institutes and others in USSR. The survey mission comprised 13 members, and went to Moscow, Kiev and two nuclear power station sites, from October 22 to November 1, 1989, for 11 days. At present in USSR, 49 nuclear power plants of about 35 GWe are in operation, and by 2000, the operation of more nuclear power plants of about 30 GWe is needed, but due to the change of social situation in USSR, its attainment seems to be difficult. The plan of nuclear power generation in USSR, the ensuring of safety in general, the recent countermeasures for improving safety, the effect of the accident in Chenobyl Nuclear Power Station on health and so on are reported. The detailed record of the visit to Zaporozhe and Chernobyl Nuclear Power Stations and 7 other research institutes and government organs is given. (K.I.)

  4. Indexes to Nuclear Regulatory Commission issuances, July--December 1995

    International Nuclear Information System (INIS)

    1996-01-01

    Digests and indexes for issuances of the NRC, the Atomic Safety and Licensing Board, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: (1) case name, (2) full text reference, (3) issuance number, (4) issued raised by appellants, (5) legal citations, (6) name of facility and Docket number, (7) subject matter, (8) type of hearing, and (9) type of issuance

  5. Respirator studies for the Nuclear Regulatory Commission (NRC)

    International Nuclear Information System (INIS)

    Skaggs, B.J.; Fairchild, C.I.; DeField, J.D.; Hack, A.L.

    1985-01-01

    A project of the Health, Safety and Environment Division is described. The project provides the NRC with information of respiratory protective devices and programs for their licensee personnel. The following activities were performed during FY 1983: selection of alternate test aerosols for quality assurance testing of high-efficiency particulate air respirator filters; evaluation of MAG-1 spectacles for use with positive and negative-pressure respirators; development of a Manual of Respiratory Protection in Emergencies Involving Airborne Radioactive Materials, and technical assistance to NRC licensees regarding respirator applications. 2 references, 1 figure

  6. Recommended revisions to nuclear regulatory commission seismic design criteria

    International Nuclear Information System (INIS)

    Coats, D.W.

    1981-01-01

    Task Action Plan (TAP) A-40 was developed by consolidating specific technical assistance studies initiated to identify and quantify the conservatism inherent in the seismic design sequence of current NRC criteria. Task 10 of TAP A-40 provided a technical review of the results of the other nine engineering and seismological tasks in TAP A-40 and recommended changes to the existing NRC criteria based on this review. We used the team approach to accomplish the objectives of Task 10 in an efficient manner and to provide the best technical product possible within the limited time available. The team consisted of a core group of Lawrence Livermore National Laboratory personnel and selected consultants. The recommendations summarized in this paper were not based solely on the results of the tasks in TAP A-40 but went far beyond that data base to encompass all available and appropriate literature. Some recommendations are based on the expertise of core members and consultants that stem from unpublished data, research, and experience. Copies of the pertinent sections of the Standard Review Plan (SRP) and Regulatory Guides as well as the reports developed under TAP A-40 were provided to the participants. These reports, other available engineering literature, and the experience of the consultants and core group provided technical basis for the recommendations. (orig./HP)

  7. Regulatory review of safety cases and safety assessments for near surface

    International Nuclear Information System (INIS)

    Nys, V.

    2003-01-01

    The activities of the ASAM Regulatory Review Working Group are presented. Regulatory review of the safety assessment is made. It includes the regulatory review of post-closure safety assessment; safety case development and confidence building. The ISAM methodology is reviewed and SA system description is presented. Recommendations on the review process management are given

  8. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  9. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  10. Nuclear safety and security culture - an integrated approach to regulatory oversight

    International Nuclear Information System (INIS)

    Tronea, M.; Ciurea Ercau, C.

    2013-01-01

    The paper presents the development and implementation of regulatory guidelines for the oversight of safety and security culture within licensees organizations. CNCAN (the National Commission for Nuclear Activities of Romania) has used the International Atomic Energy Agency (IAEA) attributes for a strong safety culture as the basis for its regulatory guidelines providing support to the reviewers and inspectors for recognizing and gathering information relevant to safety culture. These guidelines are in process of being extended to address also security culture, based on the IAEA Nuclear Security Series No. 7 document Nuclear Security Culture: Implementing Guide. Recognizing that safety and security cultures coexist and need to reinforce each other because they share the common objective of limiting risk and that similar regulatory review and inspection processes are in place for nuclear security oversight, an integrated approach is considered justified, moreover since the common elements of these cultures outweigh the differences. (authors)

  11. Safety culture as a matter of regulatory control and regulatory effectiveness

    International Nuclear Information System (INIS)

    Camargo, C.T.M.; Furieri, E.B.; Arrieta, L.A.I.; Almeida, C.U.C.

    2002-01-01

    More than 15 years have passed since the term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG), and although the concept now is widely accepted, practical applications and characteristics have been disseminated mainly for nuclear power plant operating organizations. There is still a lack of international guidance on the use of safety culture as a regulatory matter and on the application of the concept within regulatory organizations. This work explores the meaning of safety culture in two different fields: as an element of safety management systems it shall be a matter of regulatory control; as a complementary tool for quality management it should be used to enhance regulatory effectiveness. Brazilian recent experience on regulating nuclear power reactors provide some examples on how the concept of safety culture may influence regulatory strategies and regulatory management. (author)

  12. Legal principles of regulatory administration and nuclear safety regulation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyeong Hui; Cheong, Sang Kee [Hannam Univ., Taejon (Korea, Republic of)

    2000-12-15

    This research presents a critical analysis and evaluation of principles of administrative laws in order to provide framework of structural reform on the nuclear safety regulation system. The focus of this analysis and evaluation is centered around the area of origin of regulatory administrative laws; authorities of regulation; procedures of regulatory actions; regulatory enforcement; and administrative relief system. In chapter 2 the concept of regulatory administration is analysed. Chapter 3 identifies the origin of regulatory administration and the principles of administration laws. It also examines legal nature of the nuclear safety standard. In relation to regulatory authorities. Chapter 4 identifies role and responsibility of administration authorities and institutions. It also examines fundamental principles of delegation of power. Then the chapter discusses the nuclear safety regulation authorities and their roles and responsibilities. Chapter 5 classifies and examines regulatory administration actions. Chapter 6 evaluates enforcement measure for effectiveness of regulation. Finally, chapter 7 discusses the administrative relief system for reviewing unreasonable regulatory acts.

  13. Present activities of the Nuclear Energy Commission in the field of safety of radiation sources and security of radioactive materials in Mongolia

    International Nuclear Information System (INIS)

    Oyuntulkhuur, N.

    2001-01-01

    The Radiation Safety Department of the Nuclear Energy Commission (NEC) is a regulatory body in Mongolia established in 1997. The paper gives a general overview of the main activities of the NEC on regulatory control of radiation sources in Mongolia. Mongolia declared itself a nuclear-weapon-free zone in 1992. Legal framework and waste management issues are described. The regulatory authority's co-operation with other agencies in radiation protection is also presented in this paper. (author)

  14. US Nuclear Regulatory Commission human-factors program plan

    International Nuclear Information System (INIS)

    1983-08-01

    The purpose of the NRC Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This initial plan addresses nuclear power plants (NPP) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, The NRC Action Plan Developed as a Result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements, and (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-83 through FY-85 time frame

  15. Information system of the U.S. Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Farber, G.

    1982-09-01

    On the basis of legal regulations the U.S. NRC maintain a far-reaching information system by means of which their documents are easily made available to the interested public. The essential parts of the information system are - the central Public Document Room in Washington, D.C., - the National Technical Information Center in the Department of Commerce, - the co-operation with the Government Printing Office, - the Nuclear Safety Information Center in the Oak Ridge National Laboratory, and - the National Energy Software Center in the Argonne National Laboratory. Via these facilities the NRC provide all interested institutions with information on the activities in connection with their statutory tasks. Accordingly numerous documents concerning of approval and monitoring of nuclear facilities as well as the use, transport and storage of fissionable material, are granted for perusion. (orig.) [de

  16. Indexes to Nuclear Regulatory Commission issuances, July-September 1981. Index 1

    International Nuclear Information System (INIS)

    1981-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  17. Indexes to Nuclear Regulatory Commission issuances, January 1, 1980--December 31, 1985

    International Nuclear Information System (INIS)

    1989-11-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

  18. Indexes to Nuclear Regulatory Commission issuances, July-December 1985. Volume 22, Index 2

    International Nuclear Information System (INIS)

    1986-03-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

  19. Indexes to Nuclear Regulatory Commission issuances, July-September 1982. Vol. 16. Index 1

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  20. Regulatory framework and safety requirements for new (gen III) reactors

    International Nuclear Information System (INIS)

    Mourlon, Sophie

    2014-01-01

    Sophie Mourlon, ASN Deputy General Director, described the international process to enhance safety between local safety authorities through organizations such as WENRA. Then she explained to the participants the regulatory issues for the next generation of NPPs

  1. NRC [Nuclear Regulatory Commission] perspective of software QA [quality assurance] in the nuclear history

    International Nuclear Information System (INIS)

    Weiss, S.H.

    1988-01-01

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

  2. Nuclear Regulatory Commission's antitrust review process: an analysis of the impacts

    International Nuclear Information System (INIS)

    1981-06-01

    The Nuclear Regulatory Commission's (NRC) antitrust process is reviewed and its impacts to small systems and applicant systems are studied. This process takes the form of a description of the NRC's antitrust review process as implemented, a generic categorization of potential impacts and individual case-by-case studies of four different utilities

  3. The U.S. Nuclear Regulatory Commission's role in the management of radioactive wastes

    International Nuclear Information System (INIS)

    Bernero, R.M.; Kalman, K.L.

    1991-01-01

    This paper discusses the U.S. Nuclear Regulatory Commission's (NRC's) role in the management of radioactive waste. It provides an overview of the NRC's programs for the management of High-Level and Low-Level radioctive wastes and uranium mill tailings. (author) 7 refs

  4. US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

    International Nuclear Information System (INIS)

    1984-09-01

    The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

  5. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988.

  6. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J W; Boccio, J L; Diamond, D; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Higgins, J C; Weiss, A J [comp.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987.

  7. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    International Nuclear Information System (INIS)

    Baum, J.W.; Boccio, J.L.; Diamond, D.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987

  8. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J [comp.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs.

  9. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs

  10. The Energy Regulatory Commission (1). Law of the Comision Reguladora de Energia

    International Nuclear Information System (INIS)

    1995-01-01

    The Energy Regulatory Commission. Reforms to the Electric Energy Public Service Law (1992) and the Regulatory Law of Article 27 on Petroleum (1995) have brought about fundamental changes in the electric and natural gas industries. The legal reforms explicitly permit the private sector to construct, operate, and own, systems of electric generation and natural gas transportation, storage and distribution. The participation of the private sector in these areas required a redefinition in the government regulatory institutions. Accordingly the Federal Congress enacted the law of the Comision Reguladora de Energia (CRE) in 1995. The CRE law expands the scope of the CRE's authority and the breadth of its powers beyond those established when it was initially created in 1993. The CRE commenced operations in January 1994 as a decentralized technical and consultative body of the Energy Ministry. The decree that created the Commission limited the scope of its authority to an analysis and consultative role applicable only to the electric industry. (Author)

  11. United States Nuclear Regulatory Commission information digest: 1997 edition. Volume 9

    International Nuclear Information System (INIS)

    1997-05-01

    The Nuclear Regulatory Commission Information Digest (digest) provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, NRC licensed activities, and general information on domestic and world-wide nuclear energy. The digest, published annually, is a compilation of nuclear- and NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1996, 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

  12. Safety Culture Evaluation at Research Reactors of Pakistan Atomic Energy Commission

    International Nuclear Information System (INIS)

    Qamar, M.A.; Saeed, A.; Shah, J.H.

    2016-01-01

    The concept of safety culture was presented by IAEA in document INSAG-4 (1991), delineated as “assembly of characteristics and attitudes in organizations and individuals which establish that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance”. The purpose of this paper is to describe the evaluation of safety culture at research reactors of the Pakistan Atomic Energy Commission (PAEC). Evaluating the safety culture of a particular organization poses some challenges which can be resolved by using safety culture evaluation models like those of Sachein (1992) and Harber-Barrier(1998). In PAEC, safety culture is the integral part of management system which not only promotes safety culture throughout the organization but also enhances its significance. To strengthen the safety culture, PAEC is also participating in a number of international and regional meetings of IAEA regarding safety culture. PAEC and the national regulator Pakistan Nuclear Regulatory Authority (PNRA) are also arranging workshops, peer reviews, sharing operational experiences and interacting with IAEA missions to enhance its capabilities in the field of safety culture. The Directorate General of Safety (DOS) is a corporate office of PAEC for safety and regulatory matters. DOS is in the process of implementing a program to evaluate safety culture at nuclear installations of PAEC to ensure that safety culture is included as a vital segment of the Integral Management System of the establishment. In this regard, training sessions and lectures on safety culture evaluation are normally conducted in PAEC for awareness and enhancement of the safety culture program. Safety culture is also addressed in PNRA Regulations like PAK-909 and PAK-913. In this paper we will focus on the safety culture evaluation in our research reactors, i.e., PARR-1 and PARR-2. The evaluation results will be based on observations, interviews of employees, group discussions

  13. Safety culture competition - expectations of a regulatory authority

    International Nuclear Information System (INIS)

    Keil, D.; Gloeckle, W.

    2000-01-01

    The accident at the Chernobyl nuclear power station on April 26, 1986 influenced the development of reactor safety and promulgated two basic concepts especially in Germany. On the one hand, extensive measures of in-plant accident management have greatly reduced the so-called residual risk. On the other hand, a comprehensive safety approach has been initiated which comprises the nuclear power plant as a system together with people, technology, and organization and also includes safety culture. In a modern regulatory concept based on the dynamic development of safety, the authority's classical regulatory function of controlling is supplemented by the objective of promoting safety. While preserving the division of responsibilities between the regulatory authority and plant operators, the authority uses 'constructive critical dialog' as a tool to enhance safety. Besides the regulatory assessment of safety culture on the basis of indications or indicators, also the continuous promotion of safety culture in a dialog with plant operators is seen as one of the duties of a regulatory authority. Continued efforts are necessary to maintain the high level of safety culture in German nuclear power plants. Operators are expected to establish a safety management which assigns top priority to safety issues, and which pursues the goal of supervising and promoting safety culture. Developments on the deregulated electricity markets must not lead to safety aspects ranking second to economic aspects. Moreover, also under changed boundary conditions, only the safe operation of nuclear power plants ensures economic viability. (orig.) [de

  14. Development Perspective of Regulatory Audit Code System for SFR Nuclear Safety Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Moo Hoon; Lee, Gil Soo; Shin, An Dong; Suh, Nam Duk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2012-05-15

    A sodium-cooled fast reactor (SFR) in Korea is based on the KALIMER-600 concept developed by KAERI. Based on 'Long-term R and D Plan for Future Reactor Systems' which was approved by the Korea Atomic Energy Commission in 2008, the KAERI designer is scheduled to apply the design certification of the prototype SFR in 2017. In order to establish regulatory infrastructure for the licensing of a prototype SFR, KINS has develop the regulatory requirements for the demonstration SFR since 2010, and are scheduled to develop the regulatory audit code systems in regard to core, fuel, and system, etc. since 2012. In this study, the domestic code systems used for core design and safety evaluation of PWRs and the nuclear physics and code system for SFRs were briefly reviewed, and the development perspective of regulatory audit code system for SFR nuclear safety evaluation were derived

  15. 29 CFR 2200.108 - Official Seal of the Occupational Safety and Health Review Commission.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Official Seal of the Occupational Safety and Health Review... Occupational Safety and Health Review Commission. The seal of the Commission shall consist of: A gold eagle... background, encircled by a white band edged in black and inscribed “Occupational Safety and Health Review...

  16. Preparation of safety and regulatory document for BARC Facilities

    International Nuclear Information System (INIS)

    Prasad, S.S.; Jayarajan, K.

    2017-01-01

    In India, the necessary codes and safety guidelines for achieving the safety objectives are provided by the Atomic Energy Regulatory Board (AERB), which are in conformity with the principles of radiation protection as formulated by the International Council of Radiation Protection (ICRP) and International Atomic Energy Agency (IAEA). The same is followed by BARC Safety Council (BSC), which is the regulatory body for the BARC facilities. In addition to all types of fuel cycle facilities, BSC regulates safety of many types of conventional facilities. Many such types of facilities and projects are not under the regulatory purview of AERB. Therefore, the Council has also initiated a programme for development and publication of safety documents for installations in BARC in the fields/ topics yet not addressed by IAEA or AERB. This makes the task pioneering, as some of the areas taken up for defining the regulatory requirements are new, where standard regulatory documents are not available

  17. Ratemaking treatment of decommissioning costs by the Federal Energy Regulatory Commission

    International Nuclear Information System (INIS)

    Lenart, R.J.

    1985-01-01

    The Nuclear Regulatory Commission (NRC) has the responsibility for the assurance of funds at the time of decommissioning. The Federal Energy Regulatory Commission (FERC), in conjunction with the State Public Utility Commissions, have the responsibilty to ensure that utilities have just and reasonable rates and an opportunity to collect an appropriate amount of dollars to decommission a nuclear reactor at the conclusion of its service life. Therefore, the Federal Energy Regulatory Commission allows utilities to include nuclear power plant decommissioning costs in rates based on the following ratemaking concepts: (1) that the methodology used by a utility equitably allocates costs between present and future ratepayers who receive service from a nuclear unit; (2) that, given the uncertainty and imprecision that are included in cost estimates for events that will transpire 20-40 years in the future, the FERC chose to err on the low side rather than run the risk of overcharging current customers for future decommissioning expense; and (3) that, as decommissioning experience accumulates, as decommissioning technology improves, and as decommissioning estimates become more refined, utilities would continue to seek revised decommissioning expense allowances from FERC in order to ensure that actual decommissioning costs are recovered over the useful life in which the plant provides service

  18. Promoting and assessment of safety culture within regulatory body

    International Nuclear Information System (INIS)

    Awasthi, Sumit; Bhattacharya, D.; Koley, J.; Krishnamurthy, P.R.

    2015-01-01

    Regulators have an important role to play in assisting organizations under their jurisdiction to develop positive safety cultures. It is therefore essential for the regulator to have a robust safety culture as an inherent strategy and communication of this strategy to the organizations it supervises. Atomic Energy Regulatory Board (AERB) emphasizes every utility to institute a good safety culture during various stages of a NPP. The regulatory requirement for establishing organisational safety culture within utility at different stages are delineated in the various AERB safety codes which are presented in the paper. Although the review and assessment of the safety culture is a part of AERB’s continual safety supervision through existing review mechanism, AERB do not use any specific indicators for safety culture assessment. However, establishing and nurturing a good safety culture within AERB helps in encouraging the utility to institute the same. At the induction level AERB provides training to its staffs for regulatory orientation which include a specific course on safety culture. Subsequently, the junior staffs are mentored by seniors while involving them in various regulatory processes and putting them as observers during regulatory decision making process. Further, AERB established a formal procedure for assessing and improving safety culture within its staff as a management system process. The paper describes as a case study the above safety culture assessment process established within AERB

  19. Recommendations of the Reactor Safety Commission, 1971--1974

    International Nuclear Information System (INIS)

    The Reactor Safety Commission (RSC) of the German Federal Republic was created in 1958 by the then Federal Minister for Atomic Energy and Hydroeconomy. Its task included the advising of the Federal Minister responsible for protection of the population from possible dangers occurring during peaceful utilization of nuclear energy and in all matters of the safety of nuclear oriented installations. The RSC consists of independent experts from differing specialty areas. The results of their consultations are passed on in recommendations to the appropriate Federal Minister. Since the reappointment and reorganization of the RSC in the year 1971 by the then Federal Minister for Education and Science, the recommendations have been published in the ''Federal Gazette.'' The report presented is divided into two parts with a three part appendix. All recommendations of the RSC made since the reorganization (68th Meeting on 3 November 1971) until expiration of the last appointment, (96th Meeting on 25 July 1974) are compiled in the first section. The second part contains all announcements of the RSC which have appeared in the ''Federal Gazette.'' These concern training, agenda, as well as current members. Appendix A includes the ''Guidelines for Pressurized Water Reactors'' approved in the 93rd Meeting on 24 April 1974. Two key word listings follow in Sections B and C of the Appendix. The report was prepared in behalf of the Federal Minister of the Interior through the Office of the RSC assigned to the Institute for Reactor Safety of the Technical Inspection Association (IRS). The report is continued at regular intervals following each meeting period

  20. System engineering in the Nuclear Regulatory Commission licensing process: Program architecture process and structure

    International Nuclear Information System (INIS)

    Romine, D.T.

    1989-01-01

    In October 1987, the U.S. Nuclear Regulatory Commission (NRC) established the Center for Nuclear Waste Regulatory Analyses at Southwest Research Institute in San Antonio, Texas. The overall mission of the center is to provide a sustained level of high-quality research and technical assistance in support of NRC regulatory responsibilities under the Nuclear Waste Policy Act (NWPA). A key part of that mission is to assist the NRC in the development of the program architecture - the systems approach to regulatory analysis for the NRC high-level waste repository licensing process - and the development and implementation of the computer-based Program Architecture Support System (PASS). This paper describes the concept of program architecture, summarizes the process and basic structure of the PASS relational data base, and describes the applications of the system

  1. Regulatory Regime and its influence in the nuclear safety

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1999-01-01

    A leading internationally agreed principle is that the prime responsibility for nuclear safety rests with each user of nuclear energy. A proper regulatory regime is needed to ensure that this responsibility is met. In the first place it provides a verification that all relevant safety issues are understood and taken into account in the practical measures by the users but it is equally important that the regulatory regime supports the users in their strive to achieve an adequate level of safety (author)

  2. Overall review strategy for the Nuclear Regulatory Commission's High-Level Waste Repository Program

    International Nuclear Information System (INIS)

    Johnson, R.L.

    1994-11-01

    The Overall Review Strategy gives general guidance to the Nuclear Regulatory Commission staff for conducting it's license application and pre-license application reviews. These reviews are in support of the Commission's construction authorization decision for a geologic repository for the disposal of high-level radioactive waste. Objectives and strategies are defined that focus the staff's reviews on determining compliance with requirements of 10 CFR Part 60. These strategies define how the staff prioritizes its reviews on those key technical uncertainties considered to be most important to repository performance. Strategies also give guidance for developing, in an integrated way, the License Application Review Plan together with supporting performance assessments, analyses, and research

  3. Regulatory system reform of occupational health and safety in China

    Science.gov (United States)

    WU, Fenghong; CHI, Yan

    2015-01-01

    With the explosive economic growth and social development, China’s regulatory system of occupational health and safety now faces more and more challenges. This article reviews the history of regulatory system of occupational health and safety in China, as well as the current reform of this regulatory system in the country. Comprehensive, a range of laws, regulations and standards that promulgated by Chinese government, duties and responsibilities of the regulatory departments are described. Problems of current regulatory system, the ongoing adjustments and changes for modifying and improving regulatory system are discussed. The aim of reform and the incentives to drive forward more health and safety conditions in workplaces are also outlined. PMID:25843565

  4. Safety Committees for Argentinean Research Reactor - Regulatory Issues

    International Nuclear Information System (INIS)

    Perrin, Carlos D.

    2009-01-01

    In the field of radiological and nuclear safety, the Nuclear Regulatory Authority (ARN) of Argentina controls three research reactors and three critical assemblies, by means of evaluations, audits and inspections, in order to ensure the fulfillment of the requirements established in the Licenses, in the Regulatory Standards and in the Mandatory Documentation in general. From the Nuclear Regulatory Authority's point of view, within the general process of research reactors safety management, the Operational Organization self verification of radiological and nuclear safety plays an outstanding role. In this aspect the ARN has established specific requirements in the Regulatory Standards, in the Operation Licenses and in the Operational Limits and Conditions. These requirements include the figure of different safety committees, which act as reviewers or advisers in diverse situations. This paper describes the main characteristics of the committees, their function, scope and the regulatory documents where the requirements are included. (author)

  5. Regulatory inspection of nuclear facilities and enforcement by the regulatory body. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    The purpose of this Safety Guide is to provide recommendations for regulatory bodies on the inspection of nuclear facilities, regulatory enforcement and related matters. The objective is to provide the regulatory body with a high level of confidence that operators have the processes in place to ensure compliance and that they do comply with legal requirements, including meeting the safety objectives and requirements of the regulatory body. However, in the event of non-compliance, the regulatory body should take appropriate enforcement action. This Safety Guide covers regulatory inspection and enforcement in relation to nuclear facilities such as: enrichment and fuel manufacturing plants; nuclear power plants; other reactors such as research reactors and critical assemblies; spent fuel reprocessing plants; and facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Section 2 sets out the objectives of regulatory inspection and enforcement. Section 3 covers the management of regulatory inspections. Section 4 covers the performance of regulatory inspections, including internal guidance, planning and preparation, methods of inspection and reports of inspections. Section 5 deals with regulatory enforcement actions. Section 6 covers the assessment of regulatory inspections and enforcement activities. The Appendix provides further details on inspection areas for nuclear facilities

  6. Industry perceptions of the impact of the U.S. Nuclear Regulatory Commission on nuclear power plant activities. Draft report

    Energy Technology Data Exchange (ETDEWEB)

    Davis, A Bert; Pederson, Cynthia D

    1990-03-01

    Teams of senior managers from the U.S. Nuclear Regulatory Commission (NRC) surveyed licensee staff members representing 13 nuclear power utilities from across the country to obtain their candid views of the effectiveness and impact of NRC regulatory activities. Licensee comments addressed the full scope of NRC activities and the impact of agency actions on licensee resources, staff performance, planning and scheduling, and organizational effectiveness. The principal themes of the survey respondents' comments are that (1) licensees acquiesce to NRC requests to avoid poor ratings on NRC Systematic Assessment of Licensee Performance (SALP) reports and the consequent financial and public perception problems that result, even if the requests require the expenditure of significant resources on matters of marginal safety significance, and (2) NRC so dominates licensee resources through its existing and changing formal and informal requirements that licensees believe that their plants, though not unsafe, would have better reliability, and may even achieve a higher degree of safety, if licensees were freer to manage their own resources. This draft report does not attempt to defend any NRC position; endorse or refute licensee perceptions; or explain any action taken by NRC in fulfilling its responsibilities to protect the health and safety of the public. Senior RC managers have made a preliminary evaluation of the information in this report and have made recommendations to address licensee concerns in some areas. The final evaluation and recommendations will be published at a later date as the final NUREG. (author)

  7. Indexes to Nuclear Regulatory Commission issuances, January-June 1984. Vol. 19, Index 2

    International Nuclear Information System (INIS)

    1984-11-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats: case name index, digests and headers, legal citations index, subject index, and facility index

  8. Indexes to Nuclear Regulatory Commission issuances, January-June 1986. Volume 23, Index 2

    International Nuclear Information System (INIS)

    1986-01-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats. These formats are case name index, digests and headers, legal citations index, subject index, and facility index

  9. Indexes to Nuclear Regulatory Commission issuances, July-December 1984. Volume 20, Index 2

    International Nuclear Information System (INIS)

    1985-03-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking for the period July-December 1984 are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  10. Indexes to Nuclear Regulatory Commission Issuances, July-September 1985. Volume 22, Index 1

    International Nuclear Information System (INIS)

    1985-12-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. The period from July through September 1985 is covered

  11. Indexes to Nuclear Regulatory Commission issuances, January-March 1984. Volume 19, Index 1

    International Nuclear Information System (INIS)

    1984-01-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements are displayed in one or more of five separate formats: Case Name Index, Digests and Headers, Legal Citations Index, Subject Index, and Facility Index

  12. Indexes to Nuclear Regulatory Commission issuances, January 1, 1986-- December 31, 1990

    International Nuclear Information System (INIS)

    1992-11-01

    Digests and indexes for issuances of the commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index

  13. Regulatory instrument review: Management of aging of LWR [light water reactor] major safety-related components

    International Nuclear Information System (INIS)

    Werry, E.V.

    1990-10-01

    This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging

  14. Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

    International Nuclear Information System (INIS)

    Sakenas, C.A.; McKenna, T.J.; Perkins, K.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

    1987-02-01

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. US Nuclear Regulatory Commission Response is the fifth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  15. Indexes to Nuclear Regulatory Commission issuances, January--March 1994. Volume 39, Index 1

    International Nuclear Information System (INIS)

    1994-07-01

    Digests and indexes for issuances of the Commission, Atomic Safety and Licensing Board Panel, Administrative Law Judges, Directors' Decisions, and Denials of Petitions for Rulemaking are presented in this document. They are intended to serve as a guide to the issuances

  16. Transforming public utility commissions in the new regulatory environment: Some issues and ideas for managing change

    Energy Technology Data Exchange (ETDEWEB)

    Wirick, D.W.; Davis, V.W.; Burns, R.E.; Jones, D.N.

    1996-07-01

    In the face of sweeping changes in utility markets and regulatory practices, public utility commissions are being forced to change in fundamental ways--to substantially transform themselves rather than to make only incremental changes in their operations. Managing this process of radical change is complicated by the fact that for the foreseeable future some portions of utility markets (e.g., water utilities) will function much as they have before. Some envision commissions in the future that are more externally focussed, that rely more on dispute resolution than adjudicatory proceedings, that concentrate on identifying and understanding competitive markets, that are more automated, and that are more likely to question old assumptions and definitions. This report identifies the considerations commissions might apply for identifying what mix of skills or fields of experise should compromise the technical staff. Factors are also identified which point towards a sectoral arrangement of staff and those factors which point toward a functional approach.

  17. Building Nuclear Safety and Security Culture Within Regulatory Body

    International Nuclear Information System (INIS)

    Huda, K.

    2016-01-01

    To achieve a higher level of nuclear safety and security, it needs to develop the safety and security culture not only in the facility but also in the regulatory body. The regulatory body, especially needs to develop the safety and security culture within the organization, because it has a function to promote and oversee the culture in the facilities. In this sense, the regulatory body should become a role model. Development of the nuclear safety and security culture should be started by properly understanding its concept and awakening the awareness of individual and organization on the importance of nuclear safety and security. For effectiveness of the culture development in the regulatory body, the following steps are suggested to be taken: setting up of the regulatory requirements, self-assessment, independent assessment review, communication with the licensee, oversight of management system implementation, and integration with regulatory activities. The paper discusses those steps in the framework of development of nuclear safety and security culture in the regulatory body, as well as some important elements in building of the culture in the nuclear facilities. (author)

  18. Basic elements of a regulatory programme for radiation safety

    International Nuclear Information System (INIS)

    Bilbao, A.A.

    2000-01-01

    In this lecture the objectives of IAEA TECDOC 1067: Organization and implementation of a national regulatory infrastructure governing protection against ionizing radiation and the safety of sources (1999) is presented

  19. Improvements of the Regulatory Framework for Nuclear Installations in the Areas of Human and Organizational Factors and Safety Culture

    International Nuclear Information System (INIS)

    Tronea, M.; Ciurea, C.

    2016-01-01

    The paper presents the development of regulatory requirements in the area of human and organizational factors taking account of the lessons learned from major accidents in the nuclear industry and in particular of the factors that contributed to the Fukushima Daiichi accident and the improvement of the regulatory oversight of nuclear safety culture. New requirements have been elaborated by the National Commission for Nuclear Activities Control (CNCAN) on the nuclear safety policy of licencees for nuclear installations, on independent nuclear safety oversight, on safety conscious work environment and on the assessment of nuclear safety culture. The regulatory process for the oversight of nuclear safety culture within licencees’ organizations operating nuclear installations and the associated procedure and guidelines, based on the IAEA Safety Standards, have been developed in 2010-2011. CNCAN has used the 37 IAEA attributes for a strong safety culture, grouped into five areas corresponding to safety culture characteristics, as the basis for its regulatory guidelines providing support to the reviewers and inspectors, in their routine activities, for recognising and gathering information relevant to safety culture. The safety culture oversight process, procedure and guidelines are in process of being reviewed and revised to improve their effectiveness and to align with the current international practices, using lessons learned from the Fukushima Daiichi accident. Starting with July 2014, Romania has a National Strategy for Nuclear Safety and Security, which includes strategic objectives, associated directions for action and concrete actions for promoting nuclear safety culture in all the organizations in the nuclear sector. The progress with the implementation of this strategy with regard to nuclear safety culture is described in the paper. CNCAN started to define its own organizational culture model and identifying the elements that promote and support safety

  20. Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

    International Nuclear Information System (INIS)

    Giraudel, B.; Langlois, G.

    1979-01-01

    From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

  1. ILK statement about the regulatory authorities' perception of operators' self-assessment of safety culture

    International Nuclear Information System (INIS)

    2005-01-01

    Over the past few years, German licensing and supervisory authorities have devoted increasing attention to safety management and safety culture issues. At present, German plant operators are introducing systems for self-assessment of the safety culture in their plants, such as the Safety Culture Assessment System developed by VGB Power Tech (VGB-SBS). In its statement, the International Committee on Nuclear Technology (ILK) addresses an effective approach of the authorities in evaluating the self-assessment of safety culture conducted by operators. ILK proposes a total of ten recommendations for evaluating the self-assessment system of the operators by the authority. The regulatory authorities should see to it that the operators establish a self-assessment system for aspects of organization and personnel, and use it continuously. The measures derived from this self-assessment by the operators, and the reasons underlying them, should be discussed with the authorities. In addition to the operators, also the regulatory authorities and the technical expert organizations commissioned by them should carry out self-assessments of their respective supervisory activities, taking into account also special events, such as changes in government, and develop appropriate programs of measures to be taken. In evaluating safety culture, the regulatory authorities should strive to support the activities of operators in improving their safety culture. A spirit of mutual confidence and cooperation should exist between operators and authorities. The recommendations expressed in the statement deliberately leave room for detailed implementation by the parties concerned. (orig.)

  2. 10 CFR Appendix A to Part 73 - U.S. Nuclear Regulatory Commission Offices and Classified Mailing Addresses

    Science.gov (United States)

    2010-01-01

    ... PROTECTION OF PLANTS AND MATERIALS Pt. 73, App. A Appendix A to Part 73—U.S. Nuclear Regulatory Commission..., Louisiana, Montana, Nebraska, Nevada, New Mexico, North Dakota, Oklahoma, Oregon, South Dakota, Texas, Utah...

  3. Policy for setting and assessing regulatory safety goals. Peer discussions on regulatory practices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This publication pertains to future planning for enhancement of good practices and it describes the experience to date in developing and implementing the policy for setting and assessing regulatory safety goals for nuclear facilities in 22 Member States. Senior regulators from these 22 Member States participated in four Peer Group discussions in 1993/94 which considered the policy used for setting and assessing regulatory safety goals. This publication presents the consensus views reached by the majority of these senior regulators.

  4. Policy for setting and assessing regulatory safety goals. Peer discussions on regulatory practices

    International Nuclear Information System (INIS)

    1995-10-01

    This publication pertains to future planning for enhancement of good practices and it describes the experience to date in developing and implementing the policy for setting and assessing regulatory safety goals for nuclear facilities in 22 Member States. Senior regulators from these 22 Member States participated in four Peer Group discussions in 1993/94 which considered the policy used for setting and assessing regulatory safety goals. This publication presents the consensus views reached by the majority of these senior regulators

  5. Risk Assessment Review Group report to the U.S. Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Lewis, H.W.; Budnitz, R.J.; Kouts, H.J.C.; Loewenstein, W.B.; Rowe, W.D.; von Hippel, F.; Zachariasen, F.

    1978-09-01

    The Risk Assessment Review Group was organized by the U.S. Nuclear Regulatory Commission on July 1, 1977, with four elements to its charter: clarify the achievements and limitations of WASH-1400, the ''Rasmussen Report''; assess the peer comments thereon, and responses to those comments; study the present state of such risk assessment methodology; and recommend to the Commission how (and whether) such methodology can be used in the regulatory and licensing process. Areas of study include: risk assessment methodologies; statistical issues; completeness; the data base; and the WASH-1400 assessment of the damage to human health from radiation after a postulated accident. Specific items discussed include: Browns Ferry; common cause failure; human factors; format and scrutability; the peer review process; earthquakes; risk perception; allegations by UCS concerning WASH-1400 treatment of quality assurance and quality control; current role of probabilistic methods in the regulatory process; acts of violence; ATWS; influence of design defects in quality assurance failures; and calculation of population doses from given releases of radionuclides

  6. The Canadian Nuclear Safety Commission Compliance Program for Uranium Mines and Mills

    Energy Technology Data Exchange (ETDEWEB)

    Schryer, D., E-mail: denis.schryer@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Saskatoon, Saskatchewan (Canada)

    2014-05-15

    The Canadian Nuclear Safety Commission (CNSC) is the principal nuclear regulator in Canada. The CNSC is empowered through the Nuclear Safety and Control Act (NSCA) and its associated regulations, to regulate the entire nuclear cycle which includes: uranium mining and milling, uranium refining and processing, fuel fabrication, power generation and nuclear waste management. A CNSC uranium mine licence is required by a proponent to site, prepare, construct, operate, decommission and abandon this nuclear facility. The CNSC licence is the legal instrument that authorizes the regulated activities and incorporates conditions and regulatory controls. Following a favourable Commission Tribunal decision to issue a licence to authorize the licensed activities, CNSC develops and executes a compliance plan of the licensee’s programs and procedures. The CNSC compliance plan is risk-informed and applies its resources to the identified higher risk areas. The compliance program is designed to encourage compliance by integrating three components: promotion, verification and enforcement and articulates the CNSC expectations to attain and maintain compliance with its regulatory requirements. The licensee performance is assessed through compliance activities and reported to the Commission to inform the licensing process during licence renewal. The application of the ongoing compliance assessment and risk management model ensures that deviations from impact predictions are addressed in a timely manner. The Uranium Mines and Mills Division of the CNSC are preparing to meet the challenges of the planned expansion of their Canadian uranium mining industry. The presentation will discuss these challenges and the measures required to address them. The Uranium Mines and Mills Division (UMMD) have adopted a structured compliance framework which includes formal procedures to conduct site inspections. New UMMD staff are trained to apply the regulations to licensed sites and to manage non

  7. International Nuclear Safety Experts Conclude IAEA Peer Review of Korea's Regulatory System

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: An international team of senior nuclear safety experts concluded today a two-week mission to review the regulatory framework for nuclear safety in the Republic of Korea. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Korea, while the final report will be submitted by the end of summer 2011. At the request of the Korean Government, the IAEA assembled a team of 16 senior regulatory experts from 14 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Korean Ministry for Education, Science and Technology (MEST) and the Korean Institute for Nuclear Safety (KINS). The mission is a peer-review based on the IAEA Safety Standards. ''This was the first IRRS mission organized after Japan's Fukushima Daiichi nuclear accident and it included a review of the regulatory implications of that event,' explains Denis Flory, IAEA Deputy Director General and Head of the Department of Nuclear Safety and Security. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission and Team Leader of this mission commended the Korean authorities for their openness and commitment to sharing their experience with the world's nuclear safety community. ''IRRS missions such as the one that was just concluded here in the Republic of Korea are crucial to the enhancement of nuclear safety worldwide,'' he said. The IRRS team reviewed Korea's current regulatory framework while acknowledging the fact that the country's Government has already decided to establish, as of October 2011, a new independent regulatory body to be called Nuclear Safety Commission (NSC). As a consequence, KINS role will be as a regulatory expert organization reporting to the NSC, while MEST's role will be restricted to promoting the utilization of nuclear energy. The IRRS team identified particular strengths in the Korean regulatory system

  8. Safety analysis in support of regulatory decision marking

    International Nuclear Information System (INIS)

    Pomier Baez, L.; Troncoso Fleitas, M.; Valhuerdi Debesa, C.; Valle Cepero, R.; Hernandez, J.L.

    1996-01-01

    Features of different safety analysis techniques by means of calculation thermohydraulic a probabilistic and severe accidents used in the safety assessment, as well as the development of these techniques in Cuba and their use in support of regulatory decision making are presented

  9. Improvement of the regulatory system by implementation new safety demands

    International Nuclear Information System (INIS)

    Iglesias, R.; Alfonso, C.

    1996-01-01

    The work describes in broad terms, the analysis that is being performed aiming at the adoption of a regulatory system that could meet the current safety demands, but which, at the same time, could be a general system that might allow different safety assessments to be done by making use of more specific technical standards of the technology supplier

  10. 75 FR 62153 - Notice of the Nuclear Regulatory Commission Issuance of Materials License SUA-1596 for Uranium...

    Science.gov (United States)

    2010-10-07

    ... Commission Issuance of Materials License SUA-1596 for Uranium One Americas, Inc. Moore Ranch In Situ Recovery.... SUPPLEMENTARY INFORMATION: The Nuclear Regulatory Commission (NRC) has issued a license to Uranium One Americas, Inc. (Uranium One) for its Moore Ranch uranium in situ recovery (ISR) facility in Campbell County...

  11. The Safety Culture of an Effective Nuclear Regulatory Body

    International Nuclear Information System (INIS)

    Carlsson, Lennart; Bernard, Benoit; Lojk, Robert; Koskinen, Kaisa; Rigail, Anne-Cecile; Stoppa, Gisela; Lorand, Ferenc; Aoki, Masahiro; Fujita, Kenichi; Takada, Hiroko; Kurasaki, Takaaki; Choi, Young Sung; Smit, Martin; Bogdanova, Tatiana; Sapozhnikov, Alexander; Smetnik, Alexander; Cid Campo, Rafael; Axelsson, Lars; Carlsson, Lennart; Edland, Anne; Ryser, Cornelia; Cohen, Miriam; Ficks, Ben; Valentin, Andrea; Nicic, Adriana; Lorin, Aurelie; Nezuka, Takayoshi; Creswell, Len

    2016-01-01

    The fundamental objective of all nuclear safety regulatory bodies is to ensure that activities related to the peaceful use of nuclear energy are carried out in a safe manner within their respective countries. In order to effectively achieve this objective, the nuclear regulatory body requires specific characteristics, one of which is a healthy safety culture. This regulatory guidance report describes five principles that support the safety culture of an effective nuclear regulatory body. These principles concern leadership for safety, individual responsibility and accountability, co-operation and open communication, a holistic approach, and continuous improvement, learning and self-assessment. The report also addresses some of the challenges to a regulatory body's safety culture that must be recognised, understood and overcome. It provides a unique resource to countries with existing, mature regulators and can be used for benchmarking as well as for training and developing staff. It will also be useful for new entrant countries in the process of developing and maintaining an effective nuclear safety regulator. (authors)

  12. PNRA: Practically Improving Safety Culture within the Regulatory Body

    International Nuclear Information System (INIS)

    Bhatti, S.A.N.; Habib, M.A.

    2016-01-01

    The prevalence of a good safety culture is equally important for all kind of organizations involved in nuclear business including operating organizations, designers, regulator, etc., and this should be reflected through the processes and activities of these organizations. The need for inculcating safety culture into regulatory processes and practices is gradually increasing since the major nuclear accident of Fukushima, Japan. Accordingly, several international fora in last few years repeatedly highlighted the importance of prevalence of safety culture in regulatory bodies as well. The utilisation of concept of safety culture remained applicable in regulatory activities of PNRA in the form of core values. After the Fukushima accident, PNRA considered it important to check the extent of utilisation of safety culture concept in organizational activities and decided to conduct its “Safety Culture Self-Assessment (SCSA)” for presenting itself as role model in-order to endorse the fact that safety culture at regulatory authority plays an important role to influence safety culture at licenced facilities. Considering the complexity of cultural assessment starting from visual manifestations to the basic assumptions at the deeper level, PNRA decided to utilise IAEA emerging methodology for assessment of culture and then used modified IAEA normative framework (made it applicable for regulatory body) for assessing safety culture at a regulatory body. PNRA SCSA team utilised safety culture assessment tools (observations, focus groups, surveys, interviews and document analysis) for collecting cultural facts by including all level of personnel involved in different activities and functions in the organization. Different challenges were encountered during implementation of these tools which were tackled with the background of training on SCSA and with the help of experts during support missions arranged by IAEA. Before formally starting the SCSA process, pre-launch activities

  13. Indexes to Nuclear Regulatory Commission issuances, January--June 1995. Volume 41, Index 2

    International Nuclear Information System (INIS)

    1995-09-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the directors' Decisions (DD), and the Denials of Petitions for rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. The information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index

  14. Indexes to Nuclear Regulatory Commission Issuances, July--December 1993. Volume 38, Index 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Digests and Headers; Legal Citations Index; Subject Index, and Facility Index.

  15. Indexes to Nuclear Regulatory Commission issuances, January--June 1995. Volume 41, Index 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the directors` Decisions (DD), and the Denials of Petitions for rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. The information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index.

  16. A compilation of reports of the Advisory Committee on Reactor Safeguards, 1997 annual, U.S. Nuclear Regulatory Commission. Volume 19

    International Nuclear Information System (INIS)

    1998-04-01

    This compilation contains 67 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1997. It also includes a report to the Congress on the NRC Safety Research Program. Specific topics include: (1) advanced reactor designs, (2) emergency core cooling systems, (3) fire protection, (4) generic letters and issues, (5) human factors, (6) instrumentation, control and protection systems, (7) materials engineering, (8) probabilistic risk assessment, (9) regulatory guides and procedures, rules, regulations, and (10) safety research, philosophy, technology and criteria

  17. A compilation of reports of the Advisory Committee on Reactor Safeguards, 1997 annual, U.S. Nuclear Regulatory Commission. Volume 19

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This compilation contains 67 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1997. It also includes a report to the Congress on the NRC Safety Research Program. Specific topics include: (1) advanced reactor designs, (2) emergency core cooling systems, (3) fire protection, (4) generic letters and issues, (5) human factors, (6) instrumentation, control and protection systems, (7) materials engineering, (8) probabilistic risk assessment, (9) regulatory guides and procedures, rules, regulations, and (10) safety research, philosophy, technology and criteria.

  18. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest. Digest No. 2

    International Nuclear Information System (INIS)

    1978-08-01

    This second edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to March 31, 1978 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This second edition replaces the first edition and its supplements and includes appropriate changes reflecting the recent amendments to the Rules of Practice which became effective on May 26, 1978

  19. Implementing 'Continuous Improvement' in the U.S. Nuclear Regulatory Commission's Decommissioning Program

    International Nuclear Information System (INIS)

    Orlando, D. A.; Buckley, J. T.; Johnson, R. L.; Gillen, D. M.

    2006-01-01

    The United States Nuclear Regulatory Commission's (US NRC's) comprehensive decommissioning program encompasses the decommissioning of all US NRC licensed facilities, ranging from the termination of routine licenses for sealed sources, to the closure of complex materials sites and nuclear power reactor facilities. Of the approximately 200 materials licenses that are terminated each year, most are routine and require little, if any, remediation to meet the US NRC unrestricted release criteria. However, some present technical and policy challenges that require large expenditures of resources, including a few complex materials sites that have requested license termination under the restricted-use provisions of 10 CFR 20.1403. Fiscal constraints to reduce budgeted resources in the decommissioning program, as well as concerns over the time to complete the decommissioning process have led to actions to improve the program and use resources more efficiently. In addition, the US NRC's Strategic Plan requires efforts to identify and implement improvements to US NRC programs in order to improve efficiency, effectiveness, timeliness, and openness, of the US NRC's activities, while maintaining the necessary focus on safety. Decommissioning regulations, and more recently the analysis of several issues associated with implementing those regulations, also have been significant catalysts for improvements in the decommissioning program. Actions in response to these catalysts have resulted in a program focused on the management of complex sites in a comprehensive, consistent, and risk-informed manner, as opposed to the past practice of focusing on sites deemed to be problematic. This paper describes the current status of the decommissioning of US NRC-licensed nuclear facilities, including an overview of recent decommissioning project completion efforts. It provides a detailed summary of past, current, and future improvements in the US NRC decommissioning program including the

  20. Safety culture from a regulatory perspective

    International Nuclear Information System (INIS)

    Dahlgren, K.

    1996-01-01

    The Swedish Nuclear Power Inspectorate, SKI, has in its regulatory approach to the area of management and organization focussed on the process of continuous improvement and have in collaboration with Battelle Human Affairs Research Center, Seattle, developed a conceptual model of the important characteristics of a continuous improvement organization and how to assess it. In this work SKI has also recognized the importance of the regulatory goals and strategies adopted by SKI for promoting an improvement process on the part of the utilities, which will be further discussed below. 15 refs

  1. Safety culture from a regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Dahlgren, K [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    1997-12-31

    The Swedish Nuclear Power Inspectorate, SKI, has in its regulatory approach to the area of management and organization focussed on the process of continuous improvement and have in collaboration with Battelle Human Affairs Research Center, Seattle, developed a conceptual model of the important characteristics of a continuous improvement organization and how to assess it. In this work SKI has also recognized the importance of the regulatory goals and strategies adopted by SKI for promoting an improvement process on the part of the utilities, which will be further discussed below. 15 refs.

  2. Recommended revisions to Nuclear Regulatory Commission seismic design criteria. Technical report

    International Nuclear Information System (INIS)

    Coats, D.W.

    1980-05-01

    This report recommends changes in the Nuclear Regulatory Commission's (NRC's) criteria now used in the seismic design of nuclear power plants. Areas covered include ground motion, soil-structure interaction, structures, and equipment and components. Members of the Engineering Mechanics Section of the Nuclear Test Engineering Division at Lawrence Livermore Laboratory (LLL) generally agreed upon the recommendations, which are based on (1) reports developed under the NRC's Task Action Plan A-40, (2) other available engineering literature, and (3) recommendations of nationally recognized experts retained by LLL specifically for this task

  3. Technical support to the Nuclear Regulatory Commission for the boiling water reactor blowdown heat transfer program

    International Nuclear Information System (INIS)

    Rice, R.E.

    1976-09-01

    Results are presented of studies conducted by Aerojet Nuclear Company (ANC) in FY 1975 to support the Nuclear Regulatory Commission (NRC) on the boiling water reactor blowdown heat transfer (BWR-BDHT) program. The support provided by ANC is that of an independent assessor of the program to ensure that the data obtained are adequate for verification of analytical models used for predicting reactor response to a postulated loss-of-coolant accident. The support included reviews of program plans, objectives, measurements, and actual data. Additional activity included analysis of experimental system performance and evaluation of the RELAP4 computer code as applied to the experiments

  4. Review of decision methodologies for evaluating regulatory actions affecting public health and safety

    International Nuclear Information System (INIS)

    Hendrickson, P.L.; McDonald, C.L.; Schilling, A.H.

    1976-12-01

    This report examines several aspects of the problems and choices facing the governmental decision maker who must take regulatory actions with multiple decision objectives and attributes. Particular attention is given to the problems facing the U.S. Nuclear Regulatory Commission (NRC) and to the decision attribute of chief concern to NRC, the protection of human health and safety, with emphasis on nuclear power plants. The study was undertaken to provide background information for NRC to use in refining its process of value/impact assessment of proposed regulatory actions. The principal conclusion is that approaches to rationally consider the value and impact of proposed regulatory actions are available. These approaches can potentially improve the decision-making process and enable the agency to better explain and defend its decisions. They also permit consistent examination of the impacts, effects of uncertainty and sensitivity to various assumptions of the alternatives being considered. Finally, these approaches can help to assure that affected parties are heard and that technical information is used appropriately and to the extent possible. The principal aspects of the regulatory decision problem covered in the report are: the legal setting for regulatory decisions which affect human health and safety, elements of the decision-making process, conceptual approaches to decision making, current approaches to decision making in several Federal agencies, and the determination of acceptable risk levels

  5. Improved cost-benefit techniques in the US Nuclear Regulatory Commission

    Energy Technology Data Exchange (ETDEWEB)

    Cronin, F.J.; Nesse, R.J.; Vaeth, M.; Wusterbarth, A.R.; Currie, J.W.

    1983-06-01

    The major objective of this report is to help the US Nuclear Regulatory Commission (NRC) in its regulatory mission, particularly with respect to improving the use of cost-benefit analysis and the economic evaluation of resources within the NRC. The objectives of this effort are: (1) to identify current and future NRC requirements (e.g., licensing) for valuing nonmarket goods; (2) to identify, highlight, and present the relevant efforts of selected federal agencies, some with over two decades of experience in valuing nonmarket goods, in this area; and (3) to review methods for valuing nonmarket impacts and to provide estimats of their magnitudes. Recently proposed legislation may result in a requirement for not only more sophisticated valuation analyses, but more extensive applications of these techniques to issues of concern to the NRC. This paper is intended to provide the NRC with information to more efficiently meet such requirements.

  6. U.S. Nuclear Regulatory Commission fiscal year 1980 supplemental budget request

    International Nuclear Information System (INIS)

    1979-01-01

    The proposed supplemental will enable the Nuclear Regulatory Commission to implement necessary additional effort arising from the agency's assessment of the accident at the Three Mile Island Unit 2 facility on March 28, 1979. The TMI accident has had a major impact on all NRC program areas, in particular on research activities and reactor operations. In addition, funds are requested to enhance the agency's Waste Management program to reflect the recommendations of the President's Interagency Review Group on Waste Management. Specific activities involved in this effort will include developing regulatory guidance, developing a licensing review capability and completing a plan for the site characterization review, all in support of the preparation of NRC guidelines necessary to conduct a construction authorization review. FY 1980 appropriations did not include funds to cover these requirements. A detailed analysis across program lines of the supplemental request is contained in this report

  7. Safety culture in Ignalina NPP, regulatory view

    Energy Technology Data Exchange (ETDEWEB)

    Maksimovas, G [VATESI (Lithuania)

    1997-09-01

    The presentation describes how success on the way to a high level Safety Culture in Ignalina NPP may be achieved by daily, well motivated activities with good attitude and proper management participation, ensuring the development and proper implementation of Safety Culture principles within the activities of Operational organization of Ignalina NPP.

  8. Safety culture in Ignalina NPP, regulatory view

    International Nuclear Information System (INIS)

    Maksimovas, G.

    1997-01-01

    The presentation describes how success on the way to a high level Safety Culture in Ignalina NPP may be achieved by daily, well motivated activities with good attitude and proper management participation, ensuring the development and proper implementation of Safety Culture principles within the activities of Operational organization of Ignalina NPP

  9. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1995--December 31, 1995. Volume 42, Pages 1-258

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    This is the 42nd volume of issuances of the U.S. Nuclear Regulatory Commission (NRC) and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. This book is a reprinting, containing corrections of numerous printing errors in a previously distributed book. It covers the period from July 1, 1995 to December 31, 1995. Atomic Safety and Licensing Boards conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities, and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a 6-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly editions and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition.

  10. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1995--December 31, 1995. Volume 42, Pages 1-258

    International Nuclear Information System (INIS)

    1996-01-01

    This is the 42nd volume of issuances of the U.S. Nuclear Regulatory Commission (NRC) and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. This book is a reprinting, containing corrections of numerous printing errors in a previously distributed book. It covers the period from July 1, 1995 to December 31, 1995. Atomic Safety and Licensing Boards conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities, and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a 6-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly editions and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition

  11. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal Board and Licensing Board decisions, July 1972--March 1992

    International Nuclear Information System (INIS)

    1993-02-01

    This 5th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to March 31, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  12. United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--December 1991

    International Nuclear Information System (INIS)

    1992-11-01

    This 4th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to December 31, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  13. Safety Culture Implementation in Indonesian Nuclear Energy Regulatory Agency (BAPETEN)

    International Nuclear Information System (INIS)

    Nurwidi Astuti, Y.H.; Dewanto, P.

    2016-01-01

    The Indonesia Nuclear Energy Act no. 10 of 1997 clearly stated that Nuclear Energy Regulatory Agency (BAPETEN) is the Nuclear Regulatory Body. This is the legal basis of BAPETEN to perform regulatory functions on the use of nuclear energy in Indonesia, including regulation, authorisation, inspection and enforcement. The Independent regulatory functions are stipulated in Article 4 and Article 14 of the Nuclear Energy Act no. 10 (1997) which require the government to establish regulatory body that is reporting directly to the president and has responsibility to control of the use of nuclear energy. BAPETEN has been start fully its functioning on January 4, 1999. In it roles as a regulatory body, the main aspect that continues and always to be developed is the safety culture. One of the objectives of regulatory functions is “to increase legal awareness of nuclear energy of the user to develop safety culture” (Article 15, point d), while in the elucidation of article 15 it is stipulated that “safety culture is that of characteristics and attitudes in organizations and individual that emphasise the importance of safety”.

  14. Regulatory practices of radiation safety of SNF transportation in Russia

    International Nuclear Information System (INIS)

    Kuryndina, Lidia; Kuryndin, Anton; Stroganov, Anatoly

    2008-01-01

    This paper overviews current regulatory practices for the assurance of nuclear and radiation safety during railway transportation of SNF on the territory of Russian Federation from NPPs to longterm-storage of reprocessing sites. The legal and regulatory requirements (mostly compliant with IAEA ST-1), licensing procedure for NM transportation are discussed. The current procedure does not require a regulatory approval for each particular shipment if the SNF fully comply with the Rosatom's branch standard and is transported in approved casks. It has been demonstrated that SNF packages compliant with the branch standard, which is knowingly provide sufficient safety margin, will conform to the federal level regulations. The regulatory approval is required if a particular shipment does not comply with the branch standard. In this case, the shipment can be approved only after regulatory review of Applicant's documents to demonstrate that the shipment still conformant to the higher level (federal) regulations. The regulatory review frequently needs a full calculation test of the radiation safety assurance. This test can take a lot of time. That's why the special calculation tools were created in SEC NRS. These tools aimed for precision calculation of the radiation safety parameters by SNF transportation use preliminary calculated Green's functions. Such approach allows quickly simulate any source distribution and optimize spent fuel assemblies placement in cask due to the transport equation property of linearity relatively the source. The short description of calculation tools are presented. Also, the paper discusses foreseen implications related to transportation of mixed-oxide SNF. (author)

  15. Organizational behavior of regulatory agencies: a case study of the Bureau of Consumer Services in the Pennsylvania Public Utility Commission

    Energy Technology Data Exchange (ETDEWEB)

    Silver, J.H.

    1981-01-01

    Regulatory agencies operate in a complex field of organizations and interest groups. The variety of behaviors that occur in the regulatory field are not satisfactorily explained by current interpretative frameworks. Regulatory agencies are at once criticized and praised. They flourish as organizational entities, yet they exhibit behavior that is often inexplicable. Notions like clientele capture, the politics of regulation, exchange theory, and institutionalized organizations do not singly explain the vagaries of regulatory behavior. A merger of these viewpoints, however, provides a foundation for a comprehensive interpretative framework. A bureau of consumer services within a state public utility commission is viewed as an institutionalized organization. From this perspective, a variety of ritual behaviors, based upon symbolic and tangible interorganizational exchanges are observed and characterized. The outcome of these exchanges is the establishment of the Bureau of Consumer Services as a legitimate regulatory agent with significant impact upon the formulation of regulatory policy in the formal proceedings of the Pennsylvania Public Utility Commission.

  16. International nuclear safety experts complete IAEA peer review of German regulatory system

    International Nuclear Information System (INIS)

    2008-01-01

    policies, the regulatory framework and activities identified by the IRRS team were: Both BMU and UM BW have high quality and experienced staff, which are supported by experienced and competent technical support organizations. Both organizations have a high commitment to learning and self improvement; The team has also made recommendations and suggestions related to areas where the regulatory system as a whole could be improved. Examples include: There is room for improving information exchange and communication between the Federal and State regulatory bodies. Such enhanced communication would also lead to increased mutual trust and public confidence. In order to fulfill their regulatory responsibilities, BMU and UM BW should be staffed appropriately and develop a plan for a succession planning strategy. It could be very beneficial for the regulatory system, and helpful for worldwide learning, if all German 'Laender' (states) with nuclear power plants also took the opportunity to benefit from the experience of an IRRS mission, including making self- assessments against international best practice. The peer review consisted of an analysis of technical regulatory information, interviews, and discussions with key personnel at BMU and UM BW, as well as with regulatory inspectors at Neckarwestheim-1 Nuclear Power Plant to witness a regulatory inspection. Regulatory aspects were also discussed with Federal Minister Sigmar Gabriel and Minister Tanja Goenner of Baden-Wuerttemberg. Other organisations such as the Federal Office for Radiation Protection (BFS), the Reactor Safety Commission (RSK), the technical support organisation Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS), and the Nuclear Safety Standards Commission (ILK) were also involved. (author)

  17. Contemporary Approaches to Safety Culture: Lessons from Developing a Regulatory Oversight Approach

    International Nuclear Information System (INIS)

    Goebel, V.; Heppell-Masys, K.

    2016-01-01

    The Canadian Nuclear Safety Commission (CNSC) regulates the use of nuclear energy and materials to protect health, safety, security and the environment, and to implement Canada’s international commitments on the peaceful use of nuclear energy; and to disseminate objective scientific, technical and regulatory information to the public. In the late 1990s, the CNSC conducted research into an Organization and Management (O&M) assessment method. Based on this research the CNSC conducted O&M assessments at all Canadian nuclear power plants and conducted additional assessments of nuclear research and uranium mine and mill operations. The results of these assessments were presented to licencees and used to inform their ongoing actions related to safety culture. Additional safety culture outreach and oversight activities provided licencees with opportunities to develop effective safety culture assessment methods, to share best practices across industry, and to strive for continual improvement of their organizations. Recent changes to the Canadian Standards Association (CSA) management system standard have resulted in the inclusion of requirements associated to safety culture and human performance. Representatives from several sectors of Canada’s nuclear industry, as well as participation from regulators such as the CNSC took part to the development of this consensus standard. Specifically, these requirements focus on monitoring and understanding safety culture, integrating safety into all of the requirements of the management system, committing workers to adhere to the management system and supporting excellence in workers’ performance. The CNSC is currently developing a regulatory document on safety culture which includes key concepts applicable to all licencees and specific requirements related to self-assessment, and additional guidance for nuclear power plants. Developing a regulatory document on safety culture requires consultation and fact finding initiatives at

  18. Plant safety and performance indicators for regulatory use

    International Nuclear Information System (INIS)

    Ferjancic, M.; Nemec, T.; Cimesa, S.

    2004-01-01

    Slovenian Nuclear Safety Administration (SNSA) supervises nuclear and radiological safety of Krsko NPP. This SNSA supervision is performed through inspections, safety evaluations of plant modifications and event analyses as well as with the safety and performance indicators (SPI) which are a valuable data source for plant safety monitoring. In the past SNSA relied on the SPI provided by Krsko NPP and did not have a set of SPI which would be more appropriate for regulatory use. In 2003 SNSA started with preparation of a new set of SPI which would be more suitable for performing the regulatory oversight of the plant. New internal SNSA procedure which is under preparation will define use and evaluation of SPI and will include definitions for the proposed set of SPI. According to the evaluation of SPI values in comparison with the limiting values and/or trending, the procedure will define SNSA response and actions. (author)

  19. Uranium recovery research sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory. Annual progress report, May 1982-May 1983

    International Nuclear Information System (INIS)

    Foley, M.G.; Opitz, B.E.; Deutsch, W.J.

    1983-06-01

    Pacific Northwest Laboratory (PNL) is currently conducting research for the US Nuclear Regulatory Commission (NRC) on uranium recovery process wastes for both active and inactive operations. NRC-sponsored uranium recovery research at PNL is focused on NRC regulatory responsibilities for uranium-recovery operations: license active milling and in situ extraction operations; concur on the acceptability of DOE remedial-action plans for inactive sites; and license DOE to maintain inactive sites following remedial actions. PNL's program consists of four coordinated projects comprised of a program management task and nine research tasks that address the critical technical and safety issues for uranium recovery. Specifically, the projects endeavor to find and evaluate methods to: prevent erosion of tailings piles and prevent radon release from tailings piles; evaluate the effectiveness of interim stabilization techniques to prevent wind erosion and transport of dry tailings from active piles; estimate the dewatering and consolidation behavior of slurried tailings to promote early cover placement; design a cover-protection system to prevent erosion of the cover by expected environmental stresses; reduce seepage into ground water and prevent ground-water degradation; control solution movement and reaction with ground water in in-situ extraction operations; evaluate natural and induced restoration of ground water in in-situ extraction operations; and monitor releases to the environment from uranium recovery facilities

  20. Uranium recovery research sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory. Annual progress report, May 1982-May 1983

    Energy Technology Data Exchange (ETDEWEB)

    Foley, M.G.; Opitz, B.E.; Deutsch, W.J.; Peterson, S.R.; Gee, G.W.; Serne, R.J.; Hartley, J.N.; Thomas, V.W.; Kalkwarf, D.R.; Walters, W.H.

    1983-06-01

    Pacific Northwest Laboratory (PNL) is currently conducting research for the US Nuclear Regulatory Commission (NRC) on uranium recovery process wastes for both active and inactive operations. NRC-sponsored uranium recovery research at PNL is focused on NRC regulatory responsibilities for uranium-recovery operations: license active milling and in situ extraction operations; concur on the acceptability of DOE remedial-action plans for inactive sites; and license DOE to maintain inactive sites following remedial actions. PNL's program consists of four coordinated projects comprised of a program management task and nine research tasks that address the critical technical and safety issues for uranium recovery. Specifically, the projects endeavor to find and evaluate methods to: prevent erosion of tailings piles and prevent radon release from tailings piles; evaluate the effectiveness of interim stabilization techniques to prevent wind erosion and transport of dry tailings from active piles; estimate the dewatering and consolidation behavior of slurried tailings to promote early cover placement; design a cover-protection system to prevent erosion of the cover by expected environmental stresses; reduce seepage into ground water and prevent ground-water degradation; control solution movement and reaction with ground water in in-situ extraction operations; evaluate natural and induced restoration of ground water in in-situ extraction operations; and monitor releases to the environment from uranium recovery facilities.