WorldWideScience

Sample records for regulatory guide basis

  1. Design basis ground motion (Ss) required on new regulatory guide

    International Nuclear Information System (INIS)

    Kamae, Katsuhiro

    2013-01-01

    New regulatory guide is enforced on July 8. Here, it is introduced how the design basis ground motion (Ss) for seismic design of nuclear power reactor facilities was revised on the new guide. Ss is formulated as two types of earthquake ground motions, earthquake ground motions with site specific earthquake source and with no such specific source locations. The latter is going to be revised based on the recent observed near source ground motions. (author)

  2. A proposed Regulatory Guide basis for spent fuel decay heat

    International Nuclear Information System (INIS)

    Hermann, O.W.; Parks, C.V.; Renier, J.P.

    1991-01-01

    A proposed revision to Regulatory Guide 3.54, ''Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation'' has been developed for the US Nuclear Regulatory Commission. The proposed revision includes a data base of decay heat rates calculated as a function of burnup, specific power, cooling time, initial fuel 235 U enrichment and assembly type (i.e., PWR or BWR). Validation of the calculational method was done by comparison with existing measured decay heat rates. Procedures for proper use of the data base, adjustment formulae accounting for effects due to differences in operating history and initial enrichment, and a defensible safety factor were derived. 15 refs., 6 tabs

  3. Basis for revision 2 of the U.S. Nuclear Regulatory Commission's Regulatory Guide 1.99

    International Nuclear Information System (INIS)

    Randall, P.N.

    1986-01-01

    Regulatory Guide 1.99. ''Radiation Damage to Reactor Vessel Materials,'' is being updated to reflect recent studies of the physical basis for neutron radiation damage and efforts to correlate damage to chemical composition and fluence. Revision 2 of the Guide contains several significant changes. Welds and base metal are treated separately. Nickel content is added as a variable and phosphorus removed. The exponent in the fluence factor is reduced, especially at high fluences. And, guidance is given for calculating attenuation of damage through the vessel wall. This paper describes the basis for these changes in the Guide

  4. 77 FR 64564 - Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles

    Science.gov (United States)

    2012-10-22

    ...-Basis Hurricane and Hurricane Missiles AGENCY: Nuclear Regulatory Commission. ACTION: Proposed interim...-ISG-024, ``Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles....221, ``Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants.'' DATES: Submit...

  5. 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.

  6. 75 FR 7526 - Withdrawal of Regulatory Guide

    Science.gov (United States)

    2010-02-19

    ...'s Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections . Regulatory guides are... NUCLEAR REGULATORY COMMISSION [NRC-2010-0052] Withdrawal of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Withdrawal of Regulatory Guide 1.56, ``Maintenance of Water Purity in Boiling...

  7. Regulatory facility guide for Ohio

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

    1994-02-28

    The Regulatory Facility Guide (RFG) has been developed for the DOE and contractor facilities located in the state of Ohio. It provides detailed compilations of international, federal, and state transportation-related regulations applicable to shipments originating at destined to Ohio facilities. This RFG was developed as an additional resource tool for use both by traffic managers who must ensure that transportation operations are in full compliance with all applicable regulatory requirements and by oversight personnel who must verify compliance activities.

  8. 75 FR 22868 - Withdrawal of Regulatory Guide

    Science.gov (United States)

    2010-04-30

    ...'s public Web site under ``Regulatory Guides'' in the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections . Regulatory guides are also available for inspection at the NRC's... NUCLEAR REGULATORY COMMISSION [NRC-2010-0167] Withdrawal of Regulatory Guide AGENCY: Nuclear...

  9. 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.

  10. Conformance to Regulatory Guide 1.97, Arkansas Nuclear One, Unit No. 1

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-08-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit No. 1 of Arkansas Nuclear One and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  11. 75 FR 45173 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-08-02

    ... ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . In addition, regulatory guides are... NUCLEAR REGULATORY COMMISSION [NRC-2008-0638] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.151...

  12. 75 FR 16202 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-03-31

    ... Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . In addition, regulatory guides are available... NUCLEAR REGULATORY COMMISSION [NRC-2008-0644] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide (RG) 1.126...

  13. 75 FR 79049 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-12-17

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . The regulatory... NUCLEAR REGULATORY COMMISSION [NRC-2008-0427] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 3.12...

  14. 76 FR 18262 - Notice of issuance of Regulatory Guide

    Science.gov (United States)

    2011-04-01

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . The regulatory... NUCLEAR REGULATORY COMMISSION [NRC-2009-0277] Notice of issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.44...

  15. 76 FR 14107 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-03-15

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . The regulatory... NUCLEAR REGULATORY COMMISSION [NRC-2009-0276] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.43...

  16. 76 FR 14108 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-03-15

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . The regulatory... NUCLEAR REGULATORY COMMISSION [NRC-2009-0275] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.50...

  17. 75 FR 52999 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-08-30

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . In addition... NUCLEAR REGULATORY COMMISSION [NRC-2009-0556] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 8.35...

  18. 75 FR 12804 - Withdrawal of Regulatory Guide 8.6

    Science.gov (United States)

    2010-03-17

    ... ``Regulatory Guides'' in the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2010-0103] Withdrawal of Regulatory Guide 8.6 AGENCY: Nuclear Regulatory Commission. ACTION: Withdrawal of Regulatory Guide 8.6, ``Standard Test Procedure for Geiger-M...

  19. 75 FR 45171 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-08-02

    ... ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC's Agencywide... NUCLEAR REGULATORY COMMISSION [NRC-2010-0072] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 3.13...

  20. 75 FR 20868 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-04-21

    ... available through the NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2009-0351] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.68.2...

  1. 75 FR 42170 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-07-20

    ... NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2009-0425] Final Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide...

  2. 75 FR 81675 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-12-28

    ... through the NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2010-0031] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 4.16...

  3. 75 FR 48381 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-08-10

    ... NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2010-0274] Final Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance and availability of Regulatory Guide...

  4. 75 FR 37842 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-06-30

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . In addition... NUCLEAR REGULATORY COMMISSION [NRC-2009-0396] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 2.5...

  5. 75 FR 43207 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-07-23

    ... NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2009-0282] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.141...

  6. 75 FR 33361 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-06-11

    ....gov/reading-rm/doc-collections/ . In addition, regulatory guides are available for inspection at the... NUCLEAR REGULATORY COMMISSION [NRC-2009-0308] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.28...

  7. 75 FR 20399 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-04-19

    ... the NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2009-0418] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 6.9...

  8. 76 FR 31382 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-05-31

    ... the NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2010-0287] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 8.2...

  9. 76 FR 24539 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-05-02

    ... site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/ . Electronic copies... NUCLEAR REGULATORY COMMISSION [NRC-2010-0181] Final Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide...

  10. 75 FR 16525 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-04-01

    ... http://www.nrc.gov/reading-rm/doc-collections/ . In addition, regulatory guides are available for... NUCLEAR REGULATORY COMMISSION [NRC-2009-0413] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.11...

  11. 75 FR 27599 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2010-05-17

    ...'' at http://www.nrc.gov/reading-rm/doc-collections/ . In addition, regulatory guides are available for... NUCLEAR REGULATORY COMMISSION [NRC-2009-0492] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance and availability of Regulatory Guide 6.7...

  12. Regulatory Facility Guide for Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

    1994-02-28

    This guide provides detailed compilations of international, federal, and state transportation related regulations applicable to shipments originating at or destined to Tennessee facilities. Information on preferred routes is also given.

  13. Conformance to Regulatory Guide 1.97, Beaver Valley Power Station, Unit No. 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    Stoffel, J.W.; Udy, A.C.

    1985-11-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit No. 2 of the Beaver Valley Power Station and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  14. 75 FR 2894 - Withdrawal of Regulatory Guide 1.148

    Science.gov (United States)

    2010-01-19

    ... downloading through the NRC's public Web site under ``Regulatory Guides'' in the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections . Regulatory guides are also available for... NUCLEAR REGULATORY COMMISSION [NRC-2010-0013] Withdrawal of Regulatory Guide 1.148 AGENCY: Nuclear...

  15. 75 FR 70044 - Withdrawal of Regulatory Guide 1.39

    Science.gov (United States)

    2010-11-16

    ... downloading through the NRC's public Web site under ``Regulatory Guides'' in the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doollectionsc-c . Regulatory guides are also available for... NUCLEAR REGULATORY COMMISSION [NRC-2010-0354] Withdrawal of Regulatory Guide 1.39 AGENCY: Nuclear...

  16. 75 FR 5630 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-02-03

    ... ``Regulatory Guides'' collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2010-0031] Draft Regulatory Guide: Issuance, Availability... Guide, DG-4017. FOR FURTHER INFORMATION CONTACT: Gregory Chapman, U.S. Nuclear Regulatory Commission...

  17. 76 FR 35922 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-06-20

    .... Proposed Revision 1 of Regulatory Guide (RG) 8.4, ``Personnel Monitoring Device--Direct-Reading Pocket...'' at http://www.nrc.gov/reading-rm/doc-collections/ . In addition, regulatory guides are available for... NUCLEAR REGULATORY COMMISSION [NRC-2010-0148] Notice of Issuance of Regulatory Guide AGENCY...

  18. 75 FR 28073 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-05-19

    ... ``Regulatory Guides'' collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2010-0181] Draft Regulatory Guide: Issuance, Availability... Guide, DG-3039, ``Standard Format and Content for Emergency Plans for Fuel Cycle and Materials...

  19. 75 FR 45166 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-08-02

    ... ``Regulatory Guides'' collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2010-0265] Draft Regulatory Guide: Issuance, Availability... Guide, DG-3030, ``Nuclear Criticality Safety Standards for Fuels and Material Facilities.'' [[Page 45167...

  20. 75 FR 62893 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-10-13

    ... the ``Regulatory Guides'' collection of the NRC's Electronic Reading Room at http://www.nrc.gov... NUCLEAR REGULATORY COMMISSION [NRC-2010-0321] Draft Regulatory Guide: Issuance, Availability... Guide, DG-1196, ``Qualification for Cement Grouting for Prestressing Tendons in Containment Structures...

  1. 76 FR 20052 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-04-11

    ... the NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections... NUCLEAR REGULATORY COMMISSION [NRC-2010-0187] Notice of Issuance of Regulatory Guide AGENCY... Guide 1.149, ``Nuclear Power Plant Simulation Facilities for Use in Operator Training, License...

  2. 75 FR 58444 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-09-24

    ... ``Regulatory Guides'' collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2010-0305] Draft Regulatory Guide: Issuance, Availability... Guide, DG-1244, ``Availability of Electric Power Sources.'' FOR FURTHER INFORMATION CONTACT: Satish...

  3. 75 FR 29785 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-05-27

    ... ``Regulatory Guides'' collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc... NUCLEAR REGULATORY COMMISSION [NRC-2010-0187] Draft Regulatory Guide: Issuance, Availability... Guide, DG-1248, ``Nuclear Power Plant Simulation Facilities for Use in Operator Training, License...

  4. 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

  5. 76 FR 28102 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-05-13

    ..., Probabilistic Risk Assessment Branch, Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S... results of risk analyses are used to help justify regulatory action. As such, the principles, process, and... NUCLEAR REGULATORY COMMISSION [NRC-2009-0385] Notice of Issuance of Regulatory Guide AGENCY...

  6. Conformance to Regulatory Guide 1.97, Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (Docket No. 50-348 and 50-364)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-05-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit Nos. 1 and 2 of the Joseph M. Farley Nuclear Plant and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  7. Conformance to Regulatory Guide 1.97, Shearon Harris Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-400 and 50-401)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-09-01

    This EG and G Idaho, Inc. report reviews the submittals for Regulatory Guide 1.97, Revision 3, for Unit Nos. 1 and 2 of the Shearon Harris Nuclear Power Plant and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified. 7 refs

  8. Conformance to Regulatory Guide 1.97 Slurry Power Station, Unit Nos. 1 and 2 (Docket Nos. 50-280 and 50-281)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-09-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97, Revision 3, for Unit Nos. 1 and 2 of the Surry Power Station and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  9. 75 FR 18241 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-04-09

    ... Guide, DG-8036, ``Personnel Monitoring Device--Direct-Reading Pocket Dosimeters.'' FOR FURTHER.... The draft regulatory guide (DG), entitled, ``Personnel Monitoring Device--Direct-Reading Pocket... this guide included guidance on indirect-reading pocket dosimeters, this guide excludes such dosimeters...

  10. Conformance to Regulatory Guide 1.97, River Bend Station, Unit No. 1 (Docket No. 50-458)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-08-01

    This EG and G, Inc., report reviews the submittals for Regulatory Guide 1.97, Revision 3, for the River Bend Station, Unit No. 1. Any exception to Regulatory Guide 1.97 is evaluated and those areas where sufficient basis for acceptability is not provided are identified. 8 refs

  11. Regulatory Framework and Radiation Protection as Basis for Evaluation

    International Nuclear Information System (INIS)

    Elegba, S.B.

    2010-01-01

    Regulatory Framework for Nuclear Safety and Radiation Protection International Instruments: Conventions; Safety Fundamentals; Codes of Conduct; Safety Requirements and Guide, and National Instruments:-Legislation; Regulations; Guidance Documents. The Sustainable Development Principle recognizes a duty to prevent undue burden and degradation of the environment for future generations. The prime responsibility for safety must rest with the person or organization responsible for facilities…that give rise to radiation risks” (IAEA Safety Fundamentals – SF-1). Compliance with regulations and requirements imposed by the Regulatory Body shall not relieve the organization of its prime responsibility for safety. The regulatory body shall establish and implement appropriate arrangements for a systematic approach to quality management which extend throughout the range of responsibilities and functions undertaken.”. The IAEA self-assessment model for a Regulatory Body is based on a three tier approach. This model is modular and can be used and adopted for implementation by any regulator at any stage of maturity “Start up”, “On the way”, “Mature” Small, medium size, big. The IAEA is required by its Statute to promote international cooperation while regulating safety is a national responsibility. However, radiation risks may transcend national borders and international cooperation that serves to promote and enhance safety globally by exchanging experience and by improving capabilities to control hazards, to prevent accidents, to respond to emergencies and to mitigate any harmful consequences

  12. Technical Basis Document (TBD) and user guides

    International Nuclear Information System (INIS)

    Chiaro, P.J. Jr.

    1998-09-01

    A Technical Basis Document (TBD) should provide the background information for establishment of an instrument's operational requirements. Due to the amount and location of DOE facilities, no one set of requirements is possible. Operational requirements will vary based on the local environments and missions at each facility. Environmental conditions that can affect an instrument's operations are ambient temperature, humidity, and radio frequency, and to a lesser extent, magnetic fields, and interfering ionizing radiations. Consideration should also be made regarding how an instrument is to be used. If an instrument will be transported around the facility, vibration and shock can cause problems if they are not addressed in the TBD. This document provides guidance for the development of a TBD. This document applies to radiation instruments used for personnel and equipment contamination monitoring, dose rate monitoring, and air monitoring

  13. 75 FR 79049 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-12-17

    ... opened in transit. This guide also incorporates suggestions for ensuring that TIDs are properly applied..., Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2010-31729 Filed 12-16-10; 8:45 am...

  14. 75 FR 33853 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-06-15

    .... Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft guide in the... provides text and image files of NRC's public documents. If you do not have access to ADAMS or if there are... ADAMS Accession Number ML100760364. The regulatory analysis is available electronically under ADAMS...

  15. 75 FR 52996 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-08-30

    .... Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft guide in the... entry into ADAMS, which provides text and image files of NRC's public documents. If you do not have.../ . The regulatory analysis may be found in ADAMS under Accession No. ML102310331. Federal Rulemaking Web...

  16. 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

  17. Guiding College Students to Develop Academic Self-Regulatory Skills

    Science.gov (United States)

    Chen, Pin-Hwa

    2011-01-01

    This study aimed to explore the efficaciousness of a guiding model for Taiwanese college students employed to develop their academic self-regulatory skills. Twenty-eight undergraduates in a university in southern Taiwan were recruited as participants. The participants received training on the proposed guiding model and were asked to take their own…

  18. 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

  19. Regulatory guide in support of ECCS rule revision

    International Nuclear Information System (INIS)

    Tovmassian, H.S.

    1987-01-01

    The US Nuclear Regulatory Commission staff is proposing to amend 10 CFR 50.46 and Appendix K to allow licensees to use best estimate calculations to estimate emergency core cooling system performance. This estimate in conjunction with an estimate of the uncertainty in the calculation would then be used to assure that the licensing limits set forth in 10 CFR 50.46(b) are not exceeded. The NRC staff has prepared a draft regulatory guide to assist licensees and applicants in complying with these proposed amendments. This paper sets forth the objectives of this regulatory guide, the approach taken, the difficulties encountered, and the current status of this effort

  20. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2012-02-15

    ... Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide... draft regulatory guide (DG) DG-1271 ``Decommissioning of Nuclear Power Reactors.'' This guide describes... Regulatory Guide 1.184, ``Decommissioning of Nuclear Power Reactors,'' dated July 2000. This proposed...

  1. Conformance to Regulatory Guide 1.97 Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3 (Docket Nos. 50-259, 50-260, and 50-296)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-07-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97, Revision 3, for Unit Nos. 1, 2 and 3 of the Browns Ferry Nuclear Plant and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  2. 76 FR 11288 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-03-01

    ..., telephone: 301-492- 3303 or e-mail; [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The U..., the public can gain entry into ADAMS, which provides text and image files of NRC's public documents... analysis may be found in ADAMS under Accession No. ML102350573. Regulatory guides are not copyrighted, and...

  3. 75 FR 48382 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-08-10

    .... Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft guide in the... provides text and image files of NRC's public documents. If you do not have access to ADAMS or if there are... analysis may be found in ADAMS under Accession No. ML101740327. Federal Rulemaking Web site: Public...

  4. NRC [Nuclear Regulatory Commission] editorial style guide

    International Nuclear Information System (INIS)

    Beeson, J.F.; Calure, B.A.; Gable, D.; Lesar, M.T.; Mejac, M.F.; Sanders, R.F.

    1989-10-01

    Editorial style refers to the choices that writers, editors, and secretaries make to eliminate inconsistencies in their documents. These choices apply to the recurrent features of a document such as abbreviations, capitalization, compound words, numbers, symbols, and punctuation, as well as to references and footnotes. Making these choices is sometimes difficult because usage changes as the language evolves. Consider the use of hyphens, for example. Do we write non-power reactor or nonpower reactor? Is it on-site incident or onsite incident? Although usage is moving away from the use of hyphens with prefixes, the authorities who compile style guides do not always agree about which choice to use at a given time. Moreover, each discipline -- law, physics, mathematics -- has specific standards that apply to the publications for that discipline. Even in an area as seemingly certain as spelling, overlapping usage exists. Reputable dictionaries show both ''align'' and ''aline'' as correct spellings. Likewise, ''disc, disk, and diskette'' currently coexist as equally valid choices

  5. 77 FR 33253 - Regulatory Guide 8.33, Quality Management Program

    Science.gov (United States)

    2012-06-05

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0126] Regulatory Guide 8.33, Quality Management Program... Regulatory Commission (NRC or Commission) is withdrawing Regulatory Guide (RG) 8.33, ``Quality Management... Quality Management Program was deleted from the regulations as part of an overall revision in 2002 of the...

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

    International Nuclear Information System (INIS)

    Dials, G.E.

    1997-01-01

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

  7. Technical Basis for Electromagnetic Compatibility Regulatory Guidance Update

    Energy Technology Data Exchange (ETDEWEB)

    Ewing, Paul D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Korsah, Kofi [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard Thomas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mays, Gary T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-03-01

    The objective of this report is to serve as the technical basis document for the next, planned revision of this RG that highlights and provides the rationale for the recommended changes. The structure of this document follows and summarizes the several assessment activities undertaken during the course of this project to evaluate new and updated electromagnetic compatibility (EMC) standards, testing methods and limits, and relevant technology developments being incorporated into plant activities that may have EMI/RFI implications, as well as other specific issues, including impacts of electrostatic discharge (ESD) on safety equipment and impacts on increased usage of wireless devices in nuclear power plants.

  8. Regulatory basis for the Waste Isolation Pilot Plant performance assessment

    International Nuclear Information System (INIS)

    Howard, Bryan A.; Crawford, M.B.; Galson, D.A.; Marietta, Melvin G.

    2000-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191. and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996. the DOE submitted its Compliance Certification Application (CCA) to the EPA to demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP'S compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal

  9. Analysis of NRC Regulatory Guide 1.21 Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Il; Yook, Dae Sik; Lee, Byung Soo [KINS, Daejeon (Korea, Republic of)

    2015-05-15

    It is essential to have a degree of uniformity in the methods used for measuring, evaluating, recording, and reporting data on radioactive material in effluents and solid wastes. For this purpose, the U.S. Nuclear Regulatory Commission (NRC) released a revised version of the Regulatory Guide 1.21 'Measuring, evaluating, and reporting radioactive material in liquid and gaseous effluents and solid waste' (revision 2) in 2009, updating the revision 1 version released in 1974. This study compares the previous revision 1 (1974) version with the revision 2 (2009) version to elaborate on the application of the guidelines to Korea. This study consists of an analysis of the 2009 Revision 2 version of the U.S. NRC Regulatory Guidelines 1.21 and an exposition of methods for its application in the domestic environment. Major revisions were made to allow for the adoption of a risk informed approach. Radionuclides with lower than 1% contribution to emission or radiation levels can be selected as principal radionuclides. Requirements for analysis of leaks and spills have been reinforced, with additional groundwater monitoring and hydrological data analysis becoming necessary.

  10. AVS user's guide on the basis of practice

    International Nuclear Information System (INIS)

    Masuko, Kenji; Kato, Katsumi; Kume, Etsuo; Fujii, Minoru.

    1997-07-01

    The special guides for the use of visualization software AVS have been developed at Japan Atomic Energy Research Institute (JAERI). The purpose of these guides is to help the AVS users understand easily the use of the one, due to the fact that it is so difficult for beginners to understand the original manuals. In this report, 'Transportation Evacuation Simulation' is taken up as an object of visualization, and the procedure of visualization and images recording by using the AVS are described. By using the AVS according to this report, a series of the procedure which are necessary for use of the AVS can be acquired. (author)

  11. Radiation safety in educational, medical and research institutions. Regulatory guide G-121

    International Nuclear Information System (INIS)

    2000-05-01

    This regulatory guide is intended to help educational, medical and research institutions design and implement radiation protection programs that meed regulatory requirements. This guide applied to educational, medical or research institutions that require a licence from the CNSC to posses or use radioactive materials. It describes programs to assure that radioactive materials are used safely during licensed activities. (author)

  12. Combination of the deterministic and probabilistic approaches for risk-informed decision-making in US NRC regulatory guides

    International Nuclear Information System (INIS)

    Patrik, M.; Babic, P.

    2001-06-01

    The report responds to the trend where probabilistic safety analyses are attached, on a voluntary basis (as yet), to the mandatory deterministic assessment of modifications of NPP systems or operating procedures, resulting in risk-informed type documents. It contains a nearly complete Czech translation of US NRC Regulatory Guide 1.177 and presents some suggestions for improving a) PSA study applications; b) the development of NPP documents for the regulatory body; and c) the interconnection between PSA and traditional deterministic analyses as contained in the risk-informed approach. (P.A.)

  13. A guide to ventilation requirements for uranium mines and mills. Regulatory guide G-221

    International Nuclear Information System (INIS)

    2003-06-01

    The purpose of G-221 is to help persons address the requirements for the submission of ventilation-related information when applying for a Canadian Nuclear Safety Commission (CNSC) licence to site and construct, operate or decommission a uranium mine or mill. This guide is also intended to help applicants for a uranium mine or mill licence understand their operational and maintenance obligations with respect to ventilation systems, and to help CNSC staff evaluate the adequacy of applications for uranium mine and mill licences. This guide is relevant to any application for a CNSC licence to prepare a site for and construct, operate or decommission a uranium mine or mill. In addition to summarizing the ventilation-related obligations or uranium mine and mill licensee, the guide describes and discusses the ventilation-related information that licence applicants should typically submit to meet regulatory requirements. The guide pertains to any ventilation of uranium mines and mills for the purpose of assuring the radiation safety of workers and on-site personnel. This ventilation may be associated with any underground or surface area or premise that is licensable by the CNSC as part of a uranium mine or mill. These areas and premises typically include mine workings, mill buildings, and other areas or premises involving or potentially affected by radiation or radioactive materials. Some examples of the latter include offices, effluent treatment plants, cafeterias, lunch rooms and personnel change-rooms. (author)

  14. Regulatory compliance guide for DOT-7A type A packaging design

    International Nuclear Information System (INIS)

    Kelly, D.L.

    1996-01-01

    The purpose of this guide is to provide instruction for assuring that the regulatory design requirements for a DOT-7A Type A packaging are met. This guide also supports the testing and evaluation activities that are performed on new packaging designs by a DOE-approved test facility through the DOE's DOT-7A Test Program. This Guide was updated to incorporate regulatory changes implemented by HM-169A (49 CFR, 'Transportation')

  15. Preoperative imaging as the basis for image-guided neurosurgery

    International Nuclear Information System (INIS)

    Winkler, D.; Strauss, G.; Hesse, S.; Sabri, O.; Goldammer, A.; Meixensberger, J.; Hund-Georgiadis, M.; Richter, A.; Kahn, T.

    2004-01-01

    With the progressive development of soft- and hardware, the acceptance of image-guided neurosurgery has increased dramatically. Additional image data are required to analyze the nature and the dimensions of pathological processes and the surrounding tissue. In this context, fMRI, SPECT, PET, as well as special modalities of CT and MR imaging, are routinely used. Secondary post-processing options are used to detect intracerebral lesions as well as adjacent functional eloquent regions in the parenchymatous organ pre- and intraoperatively. The integration of different image information guarantees the precise planning and realization of surgical maneuvers. The segmentation of interesting structures and risk structures, as well as their implementation in the neuronavigation systems, help to avoid additional intraoperative traumatization and offer a higher level of safety and precision. In this article the value and limitations of presurgical imaging will be discussed. (orig.) [de

  16. An overview of the UK regulatory expectation for design basis accident analysis

    International Nuclear Information System (INIS)

    Trimble, Andy

    2013-01-01

    The UK Health and Safety Executive published its most recent regulatory expectations in the 2006 version of it's safety assessment principles (SAPs). This built on experience regulating the full range of facilities for which it is responsible. Thus the principles underpinning all regulatory safety case assessment are the same but the implementation differs depending on the application. This paper will describe the published design basis accident analysis (DBAA) logic in context with other technical aspects of the regulatory expectation for safety cases. It will further illustrate the DBAA methodology with practical examples from actual experience on reprocessing plant gained over the last 15 years or so. Among the examples will be the relevance of conventional safety fault initiators to nuclear safety assessment. It will further demonstrate the derivation of facility limits and conditions necessary for nuclear safety. (authors)

  17. Neural basis of decision making guided by emotional outcomes.

    Science.gov (United States)

    Katahira, Kentaro; Matsuda, Yoshi-Taka; Fujimura, Tomomi; Ueno, Kenichi; Asamizuya, Takeshi; Suzuki, Chisato; Cheng, Kang; Okanoya, Kazuo; Okada, Masato

    2015-05-01

    Emotional events resulting from a choice influence an individual's subsequent decision making. Although the relationship between emotion and decision making has been widely discussed, previous studies have mainly investigated decision outcomes that can easily be mapped to reward and punishment, including monetary gain/loss, gustatory stimuli, and pain. These studies regard emotion as a modulator of decision making that can be made rationally in the absence of emotions. In our daily lives, however, we often encounter various emotional events that affect decisions by themselves, and mapping the events to a reward or punishment is often not straightforward. In this study, we investigated the neural substrates of how such emotional decision outcomes affect subsequent decision making. By using functional magnetic resonance imaging (fMRI), we measured brain activities of humans during a stochastic decision-making task in which various emotional pictures were presented as decision outcomes. We found that pleasant pictures differentially activated the midbrain, fusiform gyrus, and parahippocampal gyrus, whereas unpleasant pictures differentially activated the ventral striatum, compared with neutral pictures. We assumed that the emotional decision outcomes affect the subsequent decision by updating the value of the options, a process modeled by reinforcement learning models, and that the brain regions representing the prediction error that drives the reinforcement learning are involved in guiding subsequent decisions. We found that some regions of the striatum and the insula were separately correlated with the prediction error for either pleasant pictures or unpleasant pictures, whereas the precuneus was correlated with prediction errors for both pleasant and unpleasant pictures. Copyright © 2015 the American Physiological Society.

  18. Neural basis of decision making guided by emotional outcomes

    Science.gov (United States)

    Matsuda, Yoshi-Taka; Fujimura, Tomomi; Ueno, Kenichi; Asamizuya, Takeshi; Suzuki, Chisato; Cheng, Kang; Okanoya, Kazuo; Okada, Masato

    2015-01-01

    Emotional events resulting from a choice influence an individual's subsequent decision making. Although the relationship between emotion and decision making has been widely discussed, previous studies have mainly investigated decision outcomes that can easily be mapped to reward and punishment, including monetary gain/loss, gustatory stimuli, and pain. These studies regard emotion as a modulator of decision making that can be made rationally in the absence of emotions. In our daily lives, however, we often encounter various emotional events that affect decisions by themselves, and mapping the events to a reward or punishment is often not straightforward. In this study, we investigated the neural substrates of how such emotional decision outcomes affect subsequent decision making. By using functional magnetic resonance imaging (fMRI), we measured brain activities of humans during a stochastic decision-making task in which various emotional pictures were presented as decision outcomes. We found that pleasant pictures differentially activated the midbrain, fusiform gyrus, and parahippocampal gyrus, whereas unpleasant pictures differentially activated the ventral striatum, compared with neutral pictures. We assumed that the emotional decision outcomes affect the subsequent decision by updating the value of the options, a process modeled by reinforcement learning models, and that the brain regions representing the prediction error that drives the reinforcement learning are involved in guiding subsequent decisions. We found that some regions of the striatum and the insula were separately correlated with the prediction error for either pleasant pictures or unpleasant pictures, whereas the precuneus was correlated with prediction errors for both pleasant and unpleasant pictures. PMID:25695644

  19. 77 FR 70846 - Regulatory Guide 1.182, “Assessing and Managing Risk Before Maintenance Activities at Nuclear...

    Science.gov (United States)

    2012-11-27

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0285] Regulatory Guide 1.182, ``Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants'' AGENCY: Nuclear Regulatory Commission... withdrawing Regulatory Guide (RG)1.182, Revision (Rev.) 0, ``Assessing and Managing Risk Before Maintenance...

  20. Regulatory guides for qualifying the calculation methodology of Furnas by CNEN

    International Nuclear Information System (INIS)

    1987-10-01

    Regulatory guides are presented which will be used for qualifying the calculation methodology of FURNAS by CNEN, in the areas of Neutronics, Thermohydraulics, Accident Analysis and Fuel Rod Performance, as applied to Angra 1 NPP. (Author) [pt

  1. Analysis of regulatory requirement for beyond design basis events of SMART

    International Nuclear Information System (INIS)

    Kim, W. S.; Seol, K. W.

    2000-01-01

    To enhance the safety of SMART reactor, safety and regulatory requirements associated with beyond design basis events (beyond BDE), which were developed and applied to advanced light water reactor designs, were analyzed along with a design status of passive reactor. And, based on these requirements, their applicability on the SMART design was evaluated. In the design aspect, severe accident prevention and mitigation features, containment performance, and accident management were analyzed. The evaluation results show that the requirement related to beyond DBE such as ATWS, loss of residual heat removal during shutdown operation, station blackout, fire, inter-system LOCA, and well-known events from severe accident phenomena is applicable to the SMART design. However, comprehensive approach against beyond DBE is not yet provided in the SMART design, and then it is required to designate and analyze the beyond DBE-related features. This study is expected to contribute to efforts to improve plant safety and to establish regulatory requirements for safety review

  2. Risk Informed Approach for Nuclear Security Measures for Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance to States for developing a risk informed approach and for conducting threat and risk assessments as the basis for the design and implementation of sustainable nuclear security systems and measures for prevention of, detection of, and response to criminal and intentional unauthorised acts involving nuclear and other radioactive material out of regulatory control. It describes concepts and methodologies for a risk informed approach, including identification and assessment of threats, targets, and potential consequences; threat and risk assessment methodologies, and the use of risk informed approaches as the basis for informing the development and implementation of nuclear security systems and measures. The publication is an Implementing Guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, law enforcement agencies and experts from competent authorities and other relevant organizations involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures related to nuclear and other radioactive material out of regulatory control

  3. 78 FR 55117 - Ultimate Heat Sink for Nuclear Power Plants; Draft Regulatory Guide

    Science.gov (United States)

    2013-09-09

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0203] Ultimate Heat Sink for Nuclear Power Plants; Draft... (DG), DG-1275, ``Ultimate Heat Sink for Nuclear Power Plants.'' This regulatory guide (RG) describes methods and procedures acceptable to the NRC staff that nuclear power plant facility licensees and...

  4. 76 FR 23845 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-04-28

    ... INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a... provides text and image files of the NRC's public documents. If you do not have access to ADAMS or if there...- 800-397-4209, 301-415-4737, or by e-mail to [email protected] . The Regulatory Analysis is...

  5. 76 FR 2425 - Draft Regulatory Guide: Reissuance and Availability

    Science.gov (United States)

    2011-01-13

    ... INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a..., the public can gain entry into ADAMS, which provides text and image files of NRC's public [email protected] . The Regulatory Analysis is available electronically under ADAMS Accession Number...

  6. 76 FR 32878 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-06-07

    ...: Mekonen [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory..., the public can gain entry into ADAMS, which provides text and image files of the NRC's [email protected] . The Regulatory Analysis is available electronically under ADAMS Accession Number...

  7. 76 FR 5215 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-01-28

    ... . SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public... . From this page, the public can gain entry into ADAMS, which provides text and image files of NRC's... [email protected] . The Regulatory Analysis is available electronically under ADAMS Accession...

  8. 76 FR 28102 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-05-13

    ... Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555... qualitative, traditional or probabilistic), data, and criteria for considering risk are appropriate for making... 10 CFR part 52, ``Licenses, Certifications, and Approvals for Nuclear Power Plants.'' Other types of...

  9. Communication and Consultation with Interested Parties by the Regulatory Body. General Safety Guide

    International Nuclear Information System (INIS)

    2017-01-01

    This Safety Guide provides recommendations on meeting the safety requirements concerning communication and consultation with the public and other interested parties by the regulatory body about the possible radiation risks associated with facilities and activities, and about processes and decisions of the regulatory body. The Safety Guide can be used by authorized parties in circumstances where there are regulatory requirements placed on them for communication and consultation. It may also be used by other organizations or individuals considering their responsibilities for communication and consultation with interested parties.

  10. Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

    International Nuclear Information System (INIS)

    Ichikawa, M.

    1994-01-01

    The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs

  11. Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

    Energy Technology Data Exchange (ETDEWEB)

    Ichikawa, M [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    1994-12-31

    The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs.

  12. Discussion of Regulatory Guide 7.10, emphasizing the graded approach for establishing QA programs

    International Nuclear Information System (INIS)

    Gordon, L.; Lake, W.H.

    1983-01-01

    To assist applicants in establishing an acceptable QA program to meet the programmatic elements of Appendix E to 10 CFR Part 71, Regulatory Guide 7.10 was developed. Regulatory Guide 7.10 is organized in three self-contained ANNEXES. Guidance applicable to designer/fabricators, to users, and users of radiographic devices are in separate annexes. QA programs for packaging to transport radioactive material are similar in regard to the various operations a licensee may be involved in. However, the appropriate QA/QC effort to verify the program elements may vary significantly. This is referred to as the graded approach. Appendix A in the guide addresses the graded approach

  13. Cyber Security in Nuclear Power Plants - U.S. NRC Regulatory Guide 5.71

    International Nuclear Information System (INIS)

    Pogacic, Goran

    2014-01-01

    We have already made a big step into new millennia and with it there is no more dilemma about presence of computers and internet in our lives. Almost all modern facilities struggle with this new dimension of information flow and how to use it to their best interest. But there is also the other side of the coin- the security threat. For nuclear power plants this threat poses even greater risk. In addition to protecting their trade secrets, personal data or other common targets of cyber attacks, nuclear power plants need to protect their digital computers, communication systems and networks up to and including the design basis threat (DBT). As stated in U.S. Nuclear Regulatory Commission (NRC) Regulatory Commission Regulations, Title 10, Code of Federal Regulations (CFR), section 73.1, 'Purpose and Scope' this includes protection against acts of radiological sabotage and prevention of the theft or diversion of special nuclear material. The main purpose of this paper is to explore the NRC Regulatory Guide (RG) 5.71 and its guidance in implementing cyber security requirements stated in NRC 10 CFR, section 73.54, 'Protection of Digital Computer and Communication Systems and Networks'. In particular, this section requires protection of digital computers, communication systems and networks associated with the following categories of functions: · safety-related and important-to-safety functions, · security functions, · emergency preparedness functions, including offsite communication, and · support systems and equipment which, if compromised, would adversely impact safety, security, or emergency preparedness functions. This section requires protection of such systems and networks from those cyber attacks that would act to modify, destroy, or compromise the integrity or confidentiality of data or software; deny access to systems, services or data; and impact the operation of systems, networks, and equipment. This paper will also present some of

  14. 75 FR 9002 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-02-26

    ... Guide, DG-3040, ``Design, Construction, and Inspection of Embankment Retention Systems at Fuel Cycle... October 1973. This guide describes some engineering practices and methods generally considered by the NRC to be satisfactory for the design, construction, and inspection of embankment retention systems used...

  15. 76 FR 24538 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-05-02

    ... with the motor starter for electric motors on motor-operated valves. This method would ensure that the..., Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2011-10561 Filed 4-29-11; 8:45 am...

  16. 77 FR 36017 - Regulatory Guide 7.3, Procedures for Picking Up and Receiving Packages of Radioactive Material

    Science.gov (United States)

    2012-06-15

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0139] Regulatory Guide 7.3, Procedures for Picking Up and... Guide (RG) 7.3, ``Procedures for Picking Up and Receiving Packages of Radioactive Material.'' The guide..., please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, or 301-415-4737...

  17. 75 FR 54921 - Withdrawal of Regulatory Guides 1.38, 1.94, and 1.116

    Science.gov (United States)

    2010-09-09

    ... Guide 1.38, ``Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling....116, ``Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical... Development Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory...

  18. Mechanistic Basis for Plant Responses to Drought Stress : Regulatory Mechanism of Abscisic Acid Signaling

    Science.gov (United States)

    Miyakawa, Takuya; Tanokura, Masaru

    The phytohormone abscisic acid (ABA) plays a key role in the rapid adaptation of plants to environmental stresses such as drought and high salinity. Accumulated ABA in plant cells promotes stomatal closure in guard cells and transcription of stress-tolerant genes. Our understanding of ABA responses dramatically improved by the discovery of both PYR/PYL/RCAR as a soluble ABA receptor and inhibitory complex of a protein phospatase PP2C and a protein kinase SnRK2. Moreover, several structural analyses of PYR/PYL/RCAR revealed the mechanistic basis for the regulatory mechanism of ABA signaling, which provides a rational framework for the design of alternative agonists in future.

  19. The Composite Regulatory Basis of the Large X-Effect in Mouse Speciation.

    Science.gov (United States)

    Larson, Erica L; Keeble, Sara; Vanderpool, Dan; Dean, Matthew D; Good, Jeffrey M

    2017-02-01

    The disruption of meiotic sex chromosome inactivation (MSCI) has been proposed to be a major developmental mechanism underlying the rapid evolution of hybrid male sterility. We tested this idea by analyzing cell-specific gene expression across spermatogenesis in two lineages of house mice and their sterile and fertile reciprocal hybrids. We found pervasive disruption of sex chromosome gene expression in sterile hybrids at every stage of spermatogenesis. Failure of MSCI was developmentally preceded by increased silencing of autosomal genes, supporting the hypothesis that divergence at the hybrid incompatibility gene, Prdm9, results in increased rates of autosomal asynapsis which in turn triggers widespread silencing of unsynapsed chromatin. We also detected opposite patterns of postmeiotic overexpression or hyper-repression of the sex chromosomes in reciprocal hybrids, supporting the hypothesis that genomic conflict has driven functional divergence that leads to deleterious X-Y dosage imbalances in hybrids. Our developmental timeline also exposed more subtle patterns of mitotic misregulation on the X chromosome, a previously undocumented stage of spermatogenic disruption in this cross. These results indicate that multiple hybrid incompatibilities have converged on a common regulatory phenotype, the disrupted expression of the sex chromosomes during spermatogenesis. Collectively, these data reveal a composite regulatory basis to hybrid male sterility in mice that helps resolve the mechanistic underpinnings of the well-documented large X-effect in mice speciation. We propose that the inherent sensitivity of spermatogenesis to X-linked regulatory disruption has the potential to be a major driver of reproductive isolation in species with chromosomal sex determination. © The Author 2016. Published by Oxford University Press on behalf of the Society for Molecular Biology and Evolution. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  20. 76 FR 40943 - Notice of Issuance of Regulatory Guide

    Science.gov (United States)

    2011-07-12

    ... Criterion III, ``Design Control,'' of Appendix B, ``Quality Assurance Criteria for Nuclear Power Plants and... high functional reliability, design quality, and a secure development and operational environment for... Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2011-17441 Filed...

  1. 76 FR 2725 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-01-14

    ...-0001, telephone: 301-415-7495 or e- mail [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction..., which provides text and image files of NRC's public documents. If you do not have access to ADAMS or if... 1-800-397-4209, 301-415-4737, or by e-mail to [email protected] . The Regulatory Analysis is...

  2. 75 FR 53352 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-08-31

    ..., telephone: (301) 251- 7483 or e-mail [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction... image files of NRC's public documents. If you do not have access to ADAMS or if there are problems in... Reading Room at http://www.nrc.gov/reading-rm/doc-collections/ . The regulatory analysis may be found in...

  3. 76 FR 10917 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-02-28

    ..., telephone: 301-251- 7627 or e-mail: [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The... . From this page, the public can gain entry into ADAMS, which provides text and image files of NRC's....nrc.gov/reading-rm/doc-collections/ . The regulatory analysis may be found in ADAMS under Accession No...

  4. 75 FR 1830 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-01-13

    ... (RG) 5.71, ``Cyber Security Programs for Nuclear Facilities.'' FOR FURTHER INFORMATION CONTACT: Karl J... review of applications for permits and licenses. RG 5.71, ``Cyber Security Programs for Nuclear... Nuclear Regulatory Research concerning cyber security program development and the collective body of...

  5. Development of regulatory requirements/guides for desalination unit coupled with nuclear plant

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik

    2005-10-01

    The basic design of System-integrated Modular Advanced Reactor (SMART), a small-to-medium sized integral type pressurized water reactor (PWR) with the capacity of 330MWth, has been developed in Korea. In order to demonstrate the safety and performance of the SMART design, 'Development Project of SMART-P (SMART-Pilot Plant)' has been being performed as one of the 'National Mid and Long-term Atomic Energy R and D Programs', which includes design, construction, and start-up operation of the SMART-P with the capacity of 65MWth, a 1/5 scaled-down design of the SMART. At the same time, a study on the development of regulatory requirements/guides for the desalination unit coupled with nuclear plant has been carried out by KINS in order to prepare for the forthcoming SMART-P licensing. The results of this study performed from August of 2002 to October of 2005 can be summarized as follows: (1) The general status of desalination technologies has been survey. (2) The design of the desalination plant coupled with the SMART-P has been investigated. (3) The regulatory requirements/guides relevant to a desalination unit coupled with a nuclear plant have been surveyed. (4) A direction on the development of domestic regulatory requirements/guides for a desalination unit has been established. (5) A draft of regulatory requirements/guides for a desalination unit has been developed. (6) Expert technical reviews have been performed for the draft regulatory requirements/guides for a desalination unit. The draft regulatory requirements/guides developed in this study will be finalized and can be applied directly to the licensing of the SMART-P and SMART. Furthermore, it will be also applied to the licensing of the desalination unit coupled with the nuclear plant

  6. 75 FR 13599 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-03-22

    ... Guide, DG-8040, ``Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication... it deal specifically with the following aspects of an acceptable occupational health physics program that are closely related to surveys: (1) The number and qualification of the health physics staff, (2...

  7. Organization and staffing of the regulatory body for nuclear facilities. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    The purpose of this safety guide is to provide recommendations for national authorities on the appropriate management system, organization and staffing for the regulatory body responsible for the regulation of nuclear facilities in order to achieve compliance with the applicable safety requirements. This safety guide covers the organization and staffing 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 radioactive waste management facilities such as treatment, storage and disposal facilities. This safety guide also covers issues related to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation

  8. Unsolved problems in applying U.S. regulatory guides to control system equipment

    International Nuclear Information System (INIS)

    Stade, R.E.

    1978-01-01

    Two current problems encountered when designing control systems to the United States Regulatory Guide requirements are discussed. They are: 1) Level of surge voltages that should be specified when procuring solid state control and instrumentation systems and equipment. 2) The approach to be used qualifying equipment that must meet the aging requirements. (author)

  9. Regulatory Guide 1.79 safety injection recirculation test requirements, fact or fiction

    International Nuclear Information System (INIS)

    Roberts, J.K.

    1976-01-01

    The overwhelming concern of the general public in this day of state nuclear initiatives is the basic question, ''is nuclear power safe.'' Much of this concern has focused on the emergency core cooling systems. This public attention spotlights the testing organization's responsibility during startup of proving the operation and reliability of the emergency core cooling systems. The standard established by the Nuclear Regulatory Commission for testing emergency core cooling systems is Regulatory Guide 1.79 ''Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors''. The nuclear industry must satisfy the testing requirements of Regulatory Guide 1.79 to meet their responsibility to the public; and to prevent future embarrassment when questioned on the adequacy of emergency core cooling systems

  10. Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1996-01-01

    The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

  11. Structural Basis for Guide RNA Processing and Seed-Dependent DNA Targeting by CRISPR-Cas12a

    NARCIS (Netherlands)

    Swarts, Daan C.; Oost, van der John; Jinek, Martin

    2017-01-01

    The CRISPR-associated protein Cas12a (Cpf1), which has been repurposed for genome editing, possesses two distinct nuclease activities: endoribonuclease activity for processing its own guide RNAs and RNA-guided DNase activity for target DNA cleavage. To elucidate the molecular basis of both

  12. Critical considerations on the environmental protection. On the technical regulatory guide of air

    Energy Technology Data Exchange (ETDEWEB)

    Rasch, R

    1978-11-01

    The author critically examines the problem of environmental protection maintaining living conditions even with further development of technology. He deals in detail with the success-promising slogans put forth plastics and hydrochloric acid, nuclear energy, as well as keeping the air clean, sulfur dioxide as main topic from the viewpoint of environmental protection. Furthermore, the technical regulatory guides in maintaining clean air and flue gas purification are treated.

  13. Regulatory perspective on remaining challenges for utilization of pharmacogenomics-guided drug developments.

    Science.gov (United States)

    Otsubo, Yasuto; Ishiguro, Akihiro; Uyama, Yoshiaki

    2013-01-01

    Pharmacogenomics-guided drug development has been implemented in practice in the last decade, resulting in increased labeling of drugs with pharmacogenomic information. However, there are still many challenges remaining in utilizing this process. Here, we describe such remaining challenges from the regulatory perspective, specifically focusing on sample collection, biomarker qualification, ethnic factors, codevelopment of companion diagnostics and means to provide drugs for off-target patients. To improve the situation, it is important to strengthen international harmonization and collaboration among academia, industries and regulatory agencies, followed by the establishment of an international guideline on this topic. Communication with a regulatory agency from an early stage of drug development is also a key to success.

  14. Machine learning (ML)-guided OPC using basis functions of polar Fourier transform

    Science.gov (United States)

    Choi, Suhyeong; Shim, Seongbo; Shin, Youngsoo

    2016-03-01

    With shrinking feature size, runtime has become a limitation of model-based OPC (MB-OPC). A few machine learning-guided OPC (ML-OPC) have been studied as candidates for next-generation OPC, but they all employ too many parameters (e.g. local densities), which set their own limitations. We propose to use basis functions of polar Fourier transform (PFT) as parameters of ML-OPC. Since PFT functions are orthogonal each other and well reflect light phenomena, the number of parameters can significantly be reduced without loss of OPC accuracy. Experiments demonstrate that our new ML-OPC achieves 80% reduction in OPC time and 35% reduction in the error of predicted mask bias when compared to conventional ML-OPC.

  15. 77 FR 33253 - Regulatory Guide 8.24, Revision 2, Health Physics Surveys During Enriched Uranium-235 Processing...

    Science.gov (United States)

    2012-06-05

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0115] Regulatory Guide 8.24, Revision 2, Health Physics..., ``Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication'' was issued with a... specifically with the following aspects of an acceptable occupational health physics program that are closely...

  16. Regulatory requirements on accident management and emergency preparedness - concept of nuclear and radiation safety during beyond-design-basis accidents

    International Nuclear Information System (INIS)

    Yanke, R.

    2002-01-01

    Actual practice the and proposals for further activities in the field of Accident Management (AM) in the member countries of the Co-operation Forum of WWER regulators and in Western countries have been assessed. Further the results of the last working group on AM , the overview of interactions of severe accident research and the regulatory positions in various countries, IAEA reports, practice in Switzerland and Finland, were taken into consideration. From this information, the working group derived recommendations on Accident Management. The general proposals correspond to the present state of the art on AM. They do not describe the whole spectra of recommendations on AM for NPPs with WWER reactors. A basis for the implementation of an AM program is given, which could be extended in a follow-up working group. The developments and research concerning AM have to be continued. The positions of various countries with regard to the 'Interactions of severe accident research and the regulatory positions' are given. On the basis of the working group proposals, the WWER regulators could set regulatory requirements and support further developments of AM strategies, making use of the benefits of common features of NPPs with WWER reactors. Concerted actions in the field of AM between the WWER regulators would bundle the development of a unified concept of recommendations and speed up the implementation of AM measures in order to minimise the risks involved in nuclear power generation

  17. Regulatory and law framework of agricultural methanization and composting activities. User's guide

    International Nuclear Information System (INIS)

    2008-08-01

    After a presentation of the general context of organic waste management (its techniques, materials, legal and regulatory sources, i.e. European and French laws), this guide indicates the main regulatory and law aspects to those wishing to implement a project of methanization or composting of organic by-products in the agricultural sector. Several aspects are therefore discussed and presented in practical sheets. They concern the health and environment regulation, but not the professional risk prevention (explosion, fire, and so on). These aspects are the project setting up, input materials (animal by-products, organic materials coming from agricultural production or from out of it), waste collection and transport, process steps, organic product valorization, biogas valorization, solid and liquid release management

  18. Conflicts and misapplications of ANSI N509, N510, U.S. NRC Regulatory Guide 1.52 and 1.140

    International Nuclear Information System (INIS)

    Kovach, J.L.

    1987-01-01

    The nuclear industry in the early 1970's attempted to standardize air cleaning system design and testing by the development of ANSI N509, Nuclear Power Air Cleaning Units and Components and ANSI N510, Testing of Nuclear Air Cleaning Systems. Parallel to those and leaning somewhat on the same information, the USNRC has prepared first, Regulatory Guide 1.52, Design, Testing, and Maintenance Criteria for Atmosphere Clean Up of System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Reactor plants, and regulatory guide 1.140, Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Power Plants. These documents were a good starting point and should have been the basis for the evolution of sound engineering practices. Instead of that path, the subsequent revisions were narrow in scope, uncoordinated, rarely based on experience and became nearly unworkable. Starting with the scope statement (or equivalent for the regulatory guides) the problems began to occur. Ten recommendations are made for eliminating the troublesome aspects of the regulations

  19. Report of the working group 'Regulatory requirements on AM - Concept of nuclear and radiation safety during beyond-design-basis accidents'

    International Nuclear Information System (INIS)

    Bobaly, P.

    2001-01-01

    The developed working group report contains the following main paragraphs: legal basis and basis for regulatory requirements for on-site and off-site Accident Management (AM), regulatory requirements or recommendations for on-site AM and for emergency preparedness, background information concerning the implementation and review of an AM program as a basis for an AM guideline. Overview about AM/SAM implementation in member countries of the SAMINE project; measure and candidates for high level actions based upon US SAMG; interactions of severe accident research and the regulatory positions, relationship between different components of an accident management programme are also given

  20. Selection of terrestrial transfer factors for radioecological assessment models and regulatory guides

    International Nuclear Information System (INIS)

    Ng, Y.C.; Hoffman, F.O.

    1983-01-01

    A parameter value for a radioecological assessment model is not a single value but a distribution of values about a central value. The sources that contribute to the variability of transfer factors to predict foodchain transport of radionuclides are enumerated. Knowledge of these sources, judgement in interpreting the available data, consideration of collateral information, and established criteria that specify the desired level of conservatism in the resulting predictions are essential elements when selecting appropriate parameter values for radioecological assessment models and regulatory guides. 39 references, 4 figures, 5 tables

  1. Selection of terrestrial transfer factors for radioecological assessment models and regulatory guides

    Energy Technology Data Exchange (ETDEWEB)

    Ng, Y.C.; Hoffman, F.O.

    1983-01-01

    A parameter value for a radioecological assessment model is not a single value but a distribution of values about a central value. The sources that contribute to the variability of transfer factors to predict foodchain transport of radionuclides are enumerated. Knowledge of these sources, judgement in interpreting the available data, consideration of collateral information, and established criteria that specify the desired level of conservatism in the resulting predictions are essential elements when selecting appropriate parameter values for radioecological assessment models and regulatory guides. 39 references, 4 figures, 5 tables.

  2. Review of NRC Commission Papers on Regulatory Basis for Licensing and Regulating Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Yeong; Shin, Hyeong Ki [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    Spent nuclear fuel (SNF) accumulated in nuclear power plant has been a serious issue in most countries with operating nuclear power plants. Direct disposal of SNF could be a solution of the problem but many countries including the Republic of Korea have had a hard time selecting a site for high level waste repository because of low public acceptance. SNF recycling technologies consisting of reprocessing and transmutation have been developed so as to reduce the final volume of the disposed radioactive waste and to diminish the radiotoxicity of the waste. The Republic of Korea is now developing pyroprocessing and sodium-cooled fast reactor (SFR) technology to be used for the recycling of the wastes. KAERI has a plan to construct a pyroprocessing facility with a capacity of 30 tHM/y and a facility manufacturing TRU fuel for SFR by 2025. However, to license these facility and secure the safety, the current regulatory system related to SNF treatment needs to be improved and amended since the system has been developed focusing on facilities to examine irradiated nuclear materials. Status of reprocessing facility regulations developed by U.S.NRC was reviewed based on SECY papers. U.S.NRC has approved the development of a new rule referred to nationally as '10CFR Part 7x'. Existing 10CFR 50 and 70 has been evolved mainly for nuclear power plants and fuel cycle facilities whose radiological hazard is much lower than reprocessing plants respectively. U.S.NRC also derived many regulatory gaps including safety assessment methods, technical specification, general design criteria and waste classification and continue to develop the regulatory framework limited in scope to the resolution of Gap 5.

  3. The scientific and regulatory basis for the geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Savage, D.

    1995-01-01

    The disposal of radioactive waste is a central issue in the future of nuclear power and poses considerable technical, political and social issues. This book addresses these topics in an integrated fashion using performance assessment of the disposal concept as a unifying theme. Subjects addressed include: regulatory criteria; waste types, sources and characteristics; man-made or ''engineered'' barriers; the selection and evaluation of geological disposal media; the use of underground research laboratories; the movement of radionuclides in the biosphere; repository performance assessment tools approaches; addressing uncertainty and spatial variability; assessing information from natural systems; and looking at radioactive waste in relation to other wastes. (Author)

  4. Working draft regulatory guide on release criteria for decommissioning: NRC staff's draft for comment

    International Nuclear Information System (INIS)

    Daily, M.C.; Huffert, A.; Cardile, F.; Malaro, J.C.

    1994-08-01

    The Nuclear Regulatory Commission's (NRC) regulations in 10 CFR 20 are being amended to include radiological criteria for decommissioning of lands and structures at nuclear facilities. 10 CFR Part 20, Subpart E establishes criteria for the remediation of contaminated sites or facilities that will allow their release for future use with or without restrictions. The criteria include a Total Effective Dose Equivalent (TEDE) limit of 15 mrem/year (0.15 mSv/y) that should not be exceeded by an average individual among those who could potentially receive the greatest exposure from any residual activity within a facility or on a site. The criteria also require a licensee to reduce any residual radioactivity to as-low-as-reasonably-achievable (ALARA) levels. This staff draft guide describes acceptable procedures for determining the predicted dose level (PDL) from any residual radioactivity at the site. It describes the basic features of the calculational models and the associated default assumptions and parameter values the NRC staff would find acceptable in calculating PDLs. Appendices A, B, and C provide numerical values that can be used to estimate the dose from residual radioactivity remaining at a site. Since 10 CFR Part 20, Subpart E introduces several new concepts, definitions and discussions are included in a regulatory position concepts section of the guide to assist licensees in understanding some of the philosophy underlying the rule

  5. Inferring Gene Regulatory Networks Using Conditional Regulation Pattern to Guide Candidate Genes.

    Directory of Open Access Journals (Sweden)

    Fei Xiao

    Full Text Available Combining path consistency (PC algorithms with conditional mutual information (CMI are widely used in reconstruction of gene regulatory networks. CMI has many advantages over Pearson correlation coefficient in measuring non-linear dependence to infer gene regulatory networks. It can also discriminate the direct regulations from indirect ones. However, it is still a challenge to select the conditional genes in an optimal way, which affects the performance and computation complexity of the PC algorithm. In this study, we develop a novel conditional mutual information-based algorithm, namely RPNI (Regulation Pattern based Network Inference, to infer gene regulatory networks. For conditional gene selection, we define the co-regulation pattern, indirect-regulation pattern and mixture-regulation pattern as three candidate patterns to guide the selection of candidate genes. To demonstrate the potential of our algorithm, we apply it to gene expression data from DREAM challenge. Experimental results show that RPNI outperforms existing conditional mutual information-based methods in both accuracy and time complexity for different sizes of gene samples. Furthermore, the robustness of our algorithm is demonstrated by noisy interference analysis using different types of noise.

  6. Review and assessment of nuclear facilities by the regulatory body. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of 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. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

  7. Review and assessment of nuclear facilities by the regulatory body. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of 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. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

  8. A structural basis for the regulatory inactivation of DnaA.

    Science.gov (United States)

    Xu, Qingping; McMullan, Daniel; Abdubek, Polat; Astakhova, Tamara; Carlton, Dennis; Chen, Connie; Chiu, Hsiu-Ju; Clayton, Thomas; Das, Debanu; Deller, Marc C; Duan, Lian; Elsliger, Marc-Andre; Feuerhelm, Julie; Hale, Joanna; Han, Gye Won; Jaroszewski, Lukasz; Jin, Kevin K; Johnson, Hope A; Klock, Heath E; Knuth, Mark W; Kozbial, Piotr; Sri Krishna, S; Kumar, Abhinav; Marciano, David; Miller, Mitchell D; Morse, Andrew T; Nigoghossian, Edward; Nopakun, Amanda; Okach, Linda; Oommachen, Silvya; Paulsen, Jessica; Puckett, Christina; Reyes, Ron; Rife, Christopher L; Sefcovic, Natasha; Trame, Christine; van den Bedem, Henry; Weekes, Dana; Hodgson, Keith O; Wooley, John; Deacon, Ashley M; Godzik, Adam; Lesley, Scott A; Wilson, Ian A

    2009-01-16

    Regulatory inactivation of DnaA is dependent on Hda (homologous to DnaA), a protein homologous to the AAA+ (ATPases associated with diverse cellular activities) ATPase region of the replication initiator DnaA. When bound to the sliding clamp loaded onto duplex DNA, Hda can stimulate the transformation of active DnaA-ATP into inactive DnaA-ADP. The crystal structure of Hda from Shewanella amazonensis SB2B at 1.75 A resolution reveals that Hda resembles typical AAA+ ATPases. The arrangement of the two subdomains in Hda (residues 1-174 and 175-241) differs dramatically from that of DnaA. A CDP molecule anchors the Hda domains in a conformation that promotes dimer formation. The Hda dimer adopts a novel oligomeric assembly for AAA+ proteins in which the arginine finger, crucial for ATP hydrolysis, is fully exposed and available to hydrolyze DnaA-ATP through a typical AAA+ type of mechanism. The sliding clamp binding motifs at the N-terminus of each Hda monomer are partially buried and combine to form an antiparallel beta-sheet at the dimer interface. The inaccessibility of the clamp binding motifs in the CDP-bound structure of Hda suggests that conformational changes are required for Hda to form a functional complex with the clamp. Thus, the CDP-bound Hda dimer likely represents an inactive form of Hda.

  9. Introduction of regulatory guide on cyber security of L and C systems in nuclear facilities

    International Nuclear Information System (INIS)

    Kang, Y.; Jeong, C. H.; Kim, D. I.

    2008-01-01

    In the case of unauthorized individuals, systems and entities or process threatening the instrumentation and control systems of nuclear facilities using the intrinsic vulnerabilities of digital based technologies, those systems may lose their own required functions. The loss of required functions of the systems can seriously affect the safety of nuclear facilities. Consequently, digital instrumentation and control systems, which perform functions important to safety, should be designed and operated to respond to cyber threats capitalizing on the vulnerabilities of digital based technologies. To make it possible, the developers and licensees of nuclear facilities should perform appropriate cyber security activities throughout the whole life cycle of digital instrumentation and control systems. Under the goal of securing the safety of nuclear facilities, this paper presents the regulatory on cyber security activities to remove the cyber threats that exploit the vulnerabilities of digital instrumentation and control systems and to mitigate the effect of such threats. Presented regulatory guide includes establishing the cyber security policy and plan, analyzing and classifying the cyber threats and cyber security assessment of digital instrumentation and control systems. (authors)

  10. Structural basis for CRISPR RNA-guided DNA recognition by Cascade

    NARCIS (Netherlands)

    Jore, M.M.; Lundgren, N.M.J.; Duijn, van E.; Bultema, J.B.; Westra, E.R.; Oost, van der J.; Brouns, S.J.J.; Beijer, M.R.

    2011-01-01

    The CRISPR (clustered regularly interspaced short palindromic repeats) immune system in prokaryotes uses small guide RNAs to neutralize invading viruses and plasmids. In Escherichia coli, immunity depends on a ribonucleoprotein complex called Cascade. Here we present the composition and

  11. Structural basis for CRISPR RNA-guided DNA recognition by Cascade

    NARCIS (Netherlands)

    Jore, Matthijs M.; Lundgren, Magnus; van Duijn, Esther; Bultema, Jelle B.; Westra, Edze R.; Waghmare, Sakharam P.; Wiedenheft, Blake; Pul, Uemit; Wurm, Reinhild; Wagner, Rolf; Beijer, Marieke R.; Barendregt, Arjan; Zhou, Kaihong; Snijders, Ambrosius P. L.; Dickman, Mark J.; Doudna, Jennifer A.; Boekema, Egbert J.; Heck, Albert J. R.; van der Oost, John; Brouns, Stan J. J.; Pul, Ümit

    The CRISPR (clustered regularly interspaced short palindromic repeats) immune system in prokaryotes uses small guide RNAs to neutralize invading viruses and plasmids. In Escherichia coli, immunity depends on a ribonucleoprotein complex called Cascade. Here we present the composition and

  12. Conformance to Regulatory Guide 1.97, Perry Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-440 and 50-441)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-03-01

    This EG and G Idaho, Inc., report provides a review of the submittals for Regulatory Guide 1.97, Revision 2, for the Perry Nuclear Power Plant, Unit Nos. 1 and 2. Any exception to the guidelines of Regulatory Guide 1.97 are evaluated

  13. A study for the establishment of regulatory requirement and evaluation guide for station blackout in nuclear power plants

    International Nuclear Information System (INIS)

    Lim, J. H.; Koo, C. S.; Joo, W. P.; Oh, S. H.; Shin, W. K.

    1999-01-01

    The consequence of SBO event could be a severe accident unless AC power was restored within a proper time, because many safety systems depend upon AC power. Based on the severity, the SBO has been extensively studied since it was identified as Unresolved Safety Issue at USNRC. The resolution of those studies is a rule-making such as 10 CFR 50.63 and Regulatory Guide 1.155. But there is no regulatory requirements of SBO for an operating domestic nuclear power plant up to the present time. This tudy has established SBO rule(regulatory requirements and evaluation guides) for an operating PWR type of the operating nuclear power plants in Korea

  14. Development of regulatory guide for review of aging management of the operating NPP

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Tae Myung; Lee, Jae Kyung [Cheongju Univ., Cheongju (Korea, Republic of); Kim, Young Ryul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2001-03-15

    This is the final report of the second year study. Based on the first year study, proposal of revised guidelines, analysis of revised or newly issued IAEA safety guides and reference guidelines of developed countries, and proposal of detailed guidelines of aging management in PSR have been performed in the second year study. The summary of results in the study so far can be summarized as below, overall view on PSR and idea of effective domestic application were leaded through additional investigation and comparison of legal basis, experiences and current status of PSR implementation among the countries having operating NPPs including Korea. Strategies of adequate application of PSR are roughly reevaluated and totally reestablished in summary from the analysis in factor by factor basis of PSR implementation experience in foreign countries and background of IAEA guidelines. Models and draft framework of PSR report in the first year study were summarized and reevaluated, and structure and outline options of PSR guidelines for judging the PSR report are newly proposed with comparison of their strengths and weaknesses based on the first year study. Among the opt ions, guidelines framework equivalent to the PSR report was picked up as the best. For the judgement of aging management, the most appropriate one was chosen for the detailed judgement of aging management review in our PSR being based on the Standard Review Plan for License Renewal (SRP-LR) in United States considering potential future usage in the judgement for continued operation of old NPP at the time of expiration of its design life. A draft PSR guidelines is prepared and attached by revision of basic guidelines issued in 2000, considering the issues discussed for the draft revision of IAEA PSR guide, the draft IAEA document about 'experience of PSR implementation of member states', and the characteristics of Hungarian PSR Guidelines.

  15. MR-guided dynamic PET reconstruction with the kernel method and spectral temporal basis functions

    Science.gov (United States)

    Novosad, Philip; Reader, Andrew J.

    2016-06-01

    Recent advances in dynamic positron emission tomography (PET) reconstruction have demonstrated that it is possible to achieve markedly improved end-point kinetic parameter maps by incorporating a temporal model of the radiotracer directly into the reconstruction algorithm. In this work we have developed a highly constrained, fully dynamic PET reconstruction algorithm incorporating both spectral analysis temporal basis functions and spatial basis functions derived from the kernel method applied to a co-registered T1-weighted magnetic resonance (MR) image. The dynamic PET image is modelled as a linear combination of spatial and temporal basis functions, and a maximum likelihood estimate for the coefficients can be found using the expectation-maximization (EM) algorithm. Following reconstruction, kinetic fitting using any temporal model of interest can be applied. Based on a BrainWeb T1-weighted MR phantom, we performed a realistic dynamic [18F]FDG simulation study with two noise levels, and investigated the quantitative performance of the proposed reconstruction algorithm, comparing it with reconstructions incorporating either spectral analysis temporal basis functions alone or kernel spatial basis functions alone, as well as with conventional frame-independent reconstruction. Compared to the other reconstruction algorithms, the proposed algorithm achieved superior performance, offering a decrease in spatially averaged pixel-level root-mean-square-error on post-reconstruction kinetic parametric maps in the grey/white matter, as well as in the tumours when they were present on the co-registered MR image. When the tumours were not visible in the MR image, reconstruction with the proposed algorithm performed similarly to reconstruction with spectral temporal basis functions and was superior to both conventional frame-independent reconstruction and frame-independent reconstruction with kernel spatial basis functions. Furthermore, we demonstrate that a joint spectral

  16. The revised version of the German Radiation Protection Regulatory Guide for Medical Applications (Richtlinie Strahlenschutz in der Medizin)

    International Nuclear Information System (INIS)

    Kemmer, W.

    1995-01-01

    The revised version of the regulatory guide, effective since 1 June 1993, is intended to enhance and effect in practice a harmonisation of approval and acceptance procedures and standardized testing processes for acceptance and approval, as well as to facilitate governmental supervisory functions relating to the application of radioactive substances and ionizing radiation in the medical field. The guide can furthermore serve as a useful source of reference and information for doctors or medical personnel being trained in applying the Radiation Protection Ordinance, or for acquisition of the required expert knowledge in medical radiological protection. (orig./HP) [de

  17. Molecular basis of calcium-sensitizing and desensitizing mutations of the human cardiac troponin C regulatory domain: a multi-scale simulation study.

    Directory of Open Access Journals (Sweden)

    Peter Michael Kekenes-Huskey

    Full Text Available Troponin C (TnC is implicated in the initiation of myocyte contraction via binding of cytosolic Ca²⁺ and subsequent recognition of the Troponin I switch peptide. Mutations of the cardiac TnC N-terminal regulatory domain have been shown to alter both calcium binding and myofilament force generation. We have performed molecular dynamics simulations of engineered TnC variants that increase or decrease Ca²⁺ sensitivity, in order to understand the structural basis of their impact on TnC function. We will use the distinction for mutants that are associated with increased Ca²⁺ affinity and for those mutants with reduced affinity. Our studies demonstrate that for GOF mutants V44Q and L48Q, the structure of the physiologically-active site II Ca²⁺ binding site in the Ca²⁺-free (apo state closely resembled the Ca²⁺-bound (holo state. In contrast, site II is very labile for LOF mutants E40A and V79Q in the apo form and bears little resemblance with the holo conformation. We hypothesize that these phenomena contribute to the increased association rate, k(on, for the GOF mutants relative to LOF. Furthermore, we observe significant positive and negative positional correlations between helices in the GOF holo mutants that are not found in the LOF mutants. We anticipate these correlations may contribute either directly to Ca²⁺ affinity or indirectly through TnI association. Our observations based on the structure and dynamics of mutant TnC provide rationale for binding trends observed in GOF and LOF mutants and will guide the development of inotropic drugs that target TnC.

  18. Best Basis Inventory Maintenance Tool (BBIM) Database Description and User Guide

    International Nuclear Information System (INIS)

    TRAN, T.T.

    2000-01-01

    The Best Basis Inventory Maintenance Tool (BBIM) is a computer database application with built-in calculations that model the chemical composition of the Hanford tank wastes in terms of three fundamental parameters: (1) Analyte concentration; (2) Waste density; and (3) Waste volume. Using these parameters, the BBIM is able to calculate for all of the Best-Basis constituents in each of the 177 tanks: (1) Total tank waste inventories; (2) Phase-based inventories; and (3) Phase-based concentrations. Calculations are handled differently depending upon the pedigree or type of the underlying data; for example, the input concentration could be in solid units, such as ''ug/g'' or in liquid units, such as ''ug/mL''. In each of these cases, there would be slight variations to the basic inventory calculation formula (Concentration - Density - Volume). In addition to calculating inventories, the BBIM also documents the source of the underlying data and how the calculations were performed. An enhancement is planned for 1Q00 to account for wastes transferred between tanks. When this is in place, the BBIM will be able to reflect ongoing Tank Farm operations, and will continuously (with a slight lag behind operational activities) maintain the documented best-basis inventory

  19. II-1 General regulatory guide for staff on duty; II-1 Opsti pravilnik za rad dezurnog osoblja

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    Personnel responsible for RA reactor operation is working in shifts. This regulatory guide describes in detail rights, tasks and responsibilities of each staff member in duty when operating the reactor under regular conditions, during start-up, during shutdown, during repair and maintenance shutdown periods. Rad reaktora odvija se po smenama. Ovaj pravilnik regulise prava, duznosti i odgovornost svakog od clanova tima u smeni pojedinacno u regularnim uslovima rada, prilikom remonta, u toku stajanja, dostizanja nominalne snage, zaustavljanja rada reaktora.

  20. Academe-Industry Partnership: Basis for Enhanced Learning Guide in the New Science General Education Course

    Directory of Open Access Journals (Sweden)

    Alma D. Agero

    2016-11-01

    Full Text Available This study explores the academe-industry partnership of Cebu Technological University Bachelor of Science in Hospitality Management and Bachelor of Science in Industrial Technology major in Food Preparation and Services courses, SY 2014-2015 to improve the quality of course offering. It takes on the feedback received from supervisors of 50 different hotels and restaurants of Cebu province, as well as the self-rating of 185 OJTs of the two courses as regard to OJTs' level of functional and science-based core competencies. This descriptive research utilizes Likert-type research-made survey questionnaire which was previously tested for validity and reliability. The findings revealed that industry supervisors evaluated the trainees as Competent in core competencies (Bartending, Bread and pastry products, Cookery, Customer services, Front office services, food and beverages as well as functional skills (Problem solving, Leadership, Communication, Independent work, Creativity, Negotiation, Teamwork, Time management and Initiative. However, they found the students need of strengthening their problem solving and communication skills. The researchers therefore developed an enhanced learning guide for the New Science GE course to address the gaps based on the industry feedback.

  1. Security programs for Category I or II nuclear material or certain nuclear facilities. Regulatory guide G-274

    International Nuclear Information System (INIS)

    2003-03-01

    The purpose of this regulatory guide is to help applicants for a Canadian Nuclear Safety Commission (CNSC) licence in respect of Category I or II nuclear material - other than a licence to transport - , or a nuclear facility consisting of a nuclear reactor that may exceed 10 MW thermal power during normal operation, prepare and submit the security information to be included with the application, pursuant to the Nuclear Safety and Control Act (NSCA). Category I and II nuclear material are defined in Appendix B to this guide. This guide describes: the security information that should typically be included with the application for any licence referred to above; how the security information may be organized and presented in a separate document (hereinafter 'the security program description'), in order to assist CNSC review and processing of the application; and, the administrative procedures to be followed when preparing, submitting or revising the security program description. (author)

  2. Federal guide for a radiological response: Supporting the Nuclear Regulatory Commission during the initial hours of a serious accident

    International Nuclear Information System (INIS)

    Hogan, R.T.

    1993-11-01

    This document is a planning guide for those Federal agencies that work with the Nuclear Regulatory commission (NRC) during the initial hours of response to a serious radiological emergency in which the NRC is the Lead Federal Agency (LFA). These Federal agencies are: DOE, EPA, USDA, HHS, NOAA, and FEMA. This guide is intended to help these agencies prepare for a prompt response. Instructions are provided on receiving the initial notification, the type of person to send to the scene, the facility at which people are needed, how to get them to that facility, and what they should do when they arrive. Federal agencies not specifically mentioned in this guide may also be asked to support the NRC

  3. Development, Use and Maintenance of the Design Basis Threat. Implementing Guide (French Edition); Elaboration, utilisation et actualisation de la menace de reference. Guide d'application

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    This publication provides guidance on how to develop, use and maintain a design basis threat (DBT). It is intended for decision makers from organizations with roles and responsibilities for the development, use and maintenance of the DBT. This implementing guide describes a DBT; identifies and recommends the roles and responsibilities of organizations that should be involved in the development, use and maintenance of a DBT; describes how to conduct a national threat assessment as a precursor to a DBT; explains how a DBT can be developed; explains how a DBT is incorporated into a State's nuclear security regime; and explains the conditions for a review of the DBT, and how the review and update are conducted.

  4. Guide line for operator in beyond design basis events for AHWR

    International Nuclear Information System (INIS)

    Kumar, Mithilesh; Mukhopadhyay, D.; Lele, H.G.; Vaze, K.K.

    2011-01-01

    Enhanced defence-in-depth is incorporated in the proposed Advanced Heavy Water Reactor (AHWR) as a part of their fundamental safety approach to ensure that the levels of protection in defence-in-depth shall be more independent from each other than in existing installation. Safety is enhanced by incorporating into their designs, increased emphasis on inherently safe characteristics and passive systems as a part of their fundamental safety approach. It is ensured that the risk from radiation exposures to workers, the public and the environment during construction/commissioning, operation, and decommissioning, shall be comparable to that of other industrial facilities used for similar purposes. This implies that there will be no need for relocation or evacuation measures outside the plant site, apart from those generic emergency measures developed for any industrial facility. It has been demonstrated by analyses that there is no core damage for PIEs with frequencies more than 10- 10 /year. However some scenarios in residual risk domain are considered to demonstrate that dose at plant boundary is within prescribed acceptable limit. It is also possible to arrest core damage progression at various stages of event progression, by incorporating certain operating procedures, without any release. This paper discusses analyses of such low frequency event with multiple failure under the category of 'Decrease in MHT inventory' where plant related symptoms like channel exit temperature, channel component temperatures, moderator level etc. with respect to time are quantified. The operator guide line has been given for case like Loss of coolant without Emergency core coolant system (ECCS) and loss moderator heat sink. It has been observed that 3.0 kg/s mass flow rate is adequate to capture the rising trend of clad surface temperature. (author)

  5. Development, Use and Maintenance of the Design Basis Threat. Implementing Guide (Arabic Edition)

    International Nuclear Information System (INIS)

    2009-01-01

    threat to those assets. As described in this publication, an understanding of the threat can lead to a detailed description of potential adversaries (the design basis threat), which, in turn, is the basis of an appropriately designed physical protection system. This direct link gives confidence that protection would be effective against an adversary attack. International experience in using a design basis threat to protect assets of high consequence is largely based on the protection of nuclear material and facilities. Furthermore, the nuclear security documents defining and recommending that physical protection be based upon the threat. The Physical Protection Objectives and Fundamental Principles, the Recommendations on the Physical Protection of Nuclear Facilities and Nuclear Material, and the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended - do so exclusively for the protection of nuclear material and facilities. Given the historical background, and its continuing contemporary relevance, it has been necessary to draw on that nuclear protection experience in developing this publication. However, the general approach can also be applied to protecting other assets that require a high degree of confidence in the effectiveness of their protection, such as high-activity radioactive material. Specialists from France, Germany, Japan, the Russian Federation, Spain, the United Kingdom, and the United States of America assisted the IAEA in preparing this publication. A draft was presented to an open-ended technical meeting in December 2006, and subsequently circulated for comment to all Member States. This publication is consistent with The Physical Protection Objectives and Fundamental Principles; the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended; and the Recommendations on the Physical Protection of Nuclear Facilities and Nuclear Material.

  6. Development, use and maintenance of the design basis threat. Implementing guide

    International Nuclear Information System (INIS)

    2009-01-01

    threat to those assets. As described in this publication, an understanding of the threat can lead to a detailed description of potential adversaries (the design basis threat), which, in turn, is the basis of an appropriately designed physical protection system. This direct link gives confidence that protection would be effective against an adversary attack. International experience in using a design basis threat to protect assets of high consequence is largely based on the protection of nuclear material and facilities. Furthermore, the nuclear security documents defining and recommending that physical protection be based upon the threat - The Physical Protection Objectives and Fundamental Principles (GOV/2001/41/ Attachment), the Recommendations on the Physical Protection of Nuclear Facilities and Nuclear Material (INFCIRC/225/Rev. 4 (corrected)), and the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended (INFCIRC/274) (adopted on 8 July 2005; (GOV/2005/57)) - do so exclusively for the protection of nuclear material and facilities. Given the historical background, and its continuing contemporary relevance, it has been necessary to draw on that nuclear protection experience in developing this publication. However, the general approach can also be applied to protecting other assets that require a high degree of confidence in the effectiveness of their protection, such as high-activity radioactive material. Specialists from France, Germany, Japan, the Russian Federation, Spain, the United Kingdom, and the United States of America assisted the IAEA in preparing this publication. A draft was presented to an open-ended technical meeting in December 2006, and subsequently circulated for comment to all Member States. This publication is consistent with The Physical Protection Objectives and Fundamental Principles; the Convention on Physical Protection of Nuclear Facilities and Nuclear Material as Amended; and the Recommendations on the

  7. Guide relative to the regulatory requirements applicable to the radioactive materials transport in airport area

    International Nuclear Information System (INIS)

    2006-02-01

    This guide makes an inventory of all the points necessary for the correct functioning of the transport of radioactive materials in airport zone. Stowage of the parcels, program of radiological protection (P.R.P.), operation of transport, quality assurance, radiation dose evaluation, radiation monitoring, dose optimization, storage management, are the principal points of this guide. (N.C.)

  8. A call for action: Improve reporting of research studies to increase the scientific basis for regulatory decision-making

    DEFF Research Database (Denmark)

    Ågerstrand, Marlene; Christiansen, Sofie; Hanberg, Annika

    2018-01-01

    This is a call for action to scientific journals to introduce reporting requirements for toxicity and ecotoxicity studies. Such reporting requirements will support the use of peer-reviewed research studies in regulatory decision-making. Moreover, this could improve the reliability...... and reproducibility of published studies in general and make better use of the resources spent in research....

  9. A call for action: Improve reporting of research studies to increase the scientific basis for regulatory decision-making

    DEFF Research Database (Denmark)

    Ågerstrand, Marlene; Christiansen, Sofie; Hanberg, Annika

    2018-01-01

    This is a call for action to scientific journals to introduce reporting requirements for toxicity and ecotoxicity studies. Such reporting requirements will support the use of peer-reviewed research studies in regulatory decision-making. Moreover, this could improve the reliability and reproducibi...

  10. The radon issue: Considerations on regulatory approaches and exposure evaluations on the basis of recent epidemiological results

    International Nuclear Information System (INIS)

    Bochicchio, Francesco

    2008-01-01

    Recent epidemiological results have shown consistent statistically significant increases of lung cancer risk due to exposure to radon in dwellings at moderate levels of exposure, and a strong synergism with cigarette smoking. These results are summarized and discussed in relation to their possible implications for the regulatory control of radon and for future policies for the control of radon risk

  11. Structural basis for regulation of rhizobial nodulation and symbiosis gene expression by the regulatory NolR

    Science.gov (United States)

    The symbiosis between rhizobial microbes and host plants involves the coordinated expression of multiple genes, which leads to nodule formation and nitrogen fixation. As part of the transcriptional machinery for nodulation and symbiosis across a range of Rhizobium, NolR serves as a global regulatory...

  12. Regulatory standpoints on the design-basis capability of safety-related motor-operated valves(MOVs) and power-operated gate valves(POGVs)

    International Nuclear Information System (INIS)

    Kim, W. T.; Kum, O. H.

    1999-01-01

    The weakness in the design-basis capability of Motor-Operated Valves(MOVs) and the susceptibility to Pressure Locking and Thermal Binding phenomena of Power-Operated Gate Valves(POGVs) have been major concerns to be resolved in the nuclear society in and abroad since Three Mile Island accident occurred in the USA in 1979. Through detailed analysis of operating experience and regulatory activities, some MOVs and POGVs have been found to be unreliable in performing their safety functions when they are required to do so under certain conditions, especially under design-basis accident conditions. Further, it is well understood that these safety problems may not be identified by the typical valve in-service testing(IST). USNRC has published three Generic Letters, GL 89-10, GL 95-07, and GL 96-05, requiring nuclear plant licensees to take appropriate actions to resolve the problems mentioned above. Korean nuclear regulatory body has made public an administration measure called 'Regulatory recommendation to verify safety functions of the safety-related MOVs and POGVs' on June 13, 1997, and in this administration measure Korean utility is asked to submit written documents to show how it assure design-basis capability of these valves. The following are among the major concerns being considered from a regulation standpoint. Program scope and implementation priority, dynamic tests under differential pressure conditions, accuracy of diagnostic equipment, torque switch setting and torque bypass percentage, weak link analysis, motor actuator sizing, corrective actions taken to resolve pressure locking and thermal binding susceptibility, and a periodic verification program for the valves once design-basis capability has been verified

  13. Development of Draft Regulatory Guide on Accident Analysis for Nuclear Power Plants with New Safety Design Features

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Seok; Woo, Sweng Woong; Hwang, Tae Suk [KINS, Daejeon (Korea, Republic of); Sim, Suk K; Hwang, Min Jeong [Environment and Energy Technology, Daejeon (Korea, Republic of)

    2016-05-15

    The present paper discusses the development process of the draft version of regulatory guide (DRG) on accident analysis of the NPP having the NSFD and its result. Based on the consideration on the lesson learned from the previous licensing review, a draft regulatory guide (DRG) on accident analysis for NPP with new safety design features (NSDF) was developed. New safety design features (NSDF) have been introduced to the new constructing nuclear power plants (NPP) since the early 2000 and the issuance of construction permit of SKN Units 3 and 4. Typical examples of the new safety features includes Fluidic Device (FD) within Safety Injection Tanks (SIT), Passive Auxiliary Feedwater System (PAFS), ECCS Core Barrel Duct (ECBD) which were adopted in APR1400 design and/or APR+ design to improve the safety margin of the plants for the postulated accidents of interest. Also several studies of new concept of the safety system such as Hybrid ECCS design have been reported. General and/or specific guideline of accident analysis considering the NSDF has been requested. Realistic evaluation of the impact of NSDF on accident with uncertainty and separated accident analysis accounting the NSDF impact were specified in the DRG. Per the developmental process, identification of key issues, demonstration of the DRG with specific accident with specific NSDF, and improvement of DGR for the key issues and their resolution will be conducted.

  14. A guide to approaching regulatory considerations for lentiviral-mediated gene therapies.

    Science.gov (United States)

    White, Michael; Whittaker, Roger; Stoll, Elizabeth Ann

    2017-06-12

    Lentiviral vectors are increasingly the gene transfer tool of choice for gene or cell therapies, with multiple clinical investigations showing promise for this viral vector in terms of both safety and efficacy. The third-generation vector system is well-characterized, effectively delivers genetic material and maintains long-term stable expression in target cells, delivers larger amounts of genetic material than other methods, is non-pathogenic and does not cause an inflammatory response in the recipient. This report aims to help academic scientists and regulatory managers negotiate the governance framework to achieve successful translation of a lentiviral vector-based gene therapy. The focus is on European regulations, and how they are administered in the United Kingdom, although many of the principles will be similar for other regions including the United States. The report justifies the rationale for using third-generation lentiviral vectors to achieve gene delivery for in vivo and ex vivo applications; briefly summarises the extant regulatory guidance for gene therapies, categorised as advanced therapeutic medicinal products (ATMPs); provides guidance on specific regulatory issues regarding gene therapies; presents an overview of the key stakeholders to be approached when pursuing clinical trials authorization for an ATMP; and includes a brief catalogue of the documentation required to submit an application for regulatory approval of a new gene therapy.

  15. Survey of materials and other problems of relevance in safety engineering, and an assessment of their reflection in regulatory guides for conventional and nuclear engineering (1. technical report)

    International Nuclear Information System (INIS)

    Trunk, M.; Herter, K.H.

    1984-01-01

    Survey and assessment of nuclear engineering specifications and regulatory guides (ASME-BPVC Section III, division 1,2 and KTA, BS 5500) with regard to materials, dimensioning and testing for the purpose of showing to what extent available technical codes, regulatory guides and safety codes are useful in preventing failures and defining the safe limit. The other question examined is that of how these codes ought to be brought up to date in order to reflect the latest state of the art in science and technology. (orig./HP) [de

  16. 75 FR 54918 - Draft Regulatory Guide, DG-1247, “Design-Basis Hurricane and Hurricane Missiles for Nuclear Power...

    Science.gov (United States)

    2010-09-09

    .... This series was developed to describe and make available to the public such information as methods that... maximum hurricane windspeeds for hurricanes that originate in the Atlantic and make landfall along the... connected and provides an aerodynamic sail area on which the wind can act. An automobile hurricane missile...

  17. 78 FR 31614 - Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles

    Science.gov (United States)

    2013-05-24

    ... applicants. Issuance of this final ISG may be viewed as constituting backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and may be considered to be inconsistent with the issue finality provisions in 10...: LWR Edition.'' This ISG applies to reviews of ESP, DC and COL applications where the resolution of the...

  18. Technical bases for regulatory review; comparison of practices, standards and guides

    International Nuclear Information System (INIS)

    Vinck, W.; Naurer, H.; Van Reijen, G.

    1979-01-01

    In first place, national licensing and regulatory scenes are presentd, as well as correlations between: a) Correlations and industrial standards; b) national and international developments. The purpose of harmonisation efforts and ongoing activities, especially within the EC, are highlighted. For the purpose of being sufficiently specific, three specific areas are dealt with as examples, explaining how actual application of practices and criteria in EC Member States correlate (or not) to one another including the points of convergence and divergences: protection against aircraft crash, seismic effects, protection against fuel handling accidents. Conclusive remarks deal with the origin in and relative importance of discrepancies in safety practices and criteria. (author)

  19. Guidelines on how to meet the requirement to keep all exposures as low as reasonably achievable. Regulatory guide

    International Nuclear Information System (INIS)

    1997-01-01

    The purpose of Regulatory Guide G-129 (E) is to provide Atomic Energy Control Board (AECB) licensees with guidelines on how to meet the forthcoming AECB regulatory requirement to keep doses received by workers and members of the public As Low As Reasonably Achievable (ALARA), social and economic factors taken into account. it is realized that the scope for realistic dose reductions will vary depending on the nature of the licensed activity. Therefore, criteria are given in section D for determining if doses can be deemed to be as low as reasonably achievable without further evaluation. The elements that the AECB considers to be essential in the approach to ALARA are described in section E and are summarized as follows: a demonstrated management commitment to the ALARA principle; the implementation of ALARA through a licensee's organization and management, provision of resources, training, establishment of action levels, documentation and other measures; and regular operational reviews. The above elements will be the focus of any AECB assessment to verify compliance with the requirement to keep radiation exposures as low as reasonably achievable. (author)

  20. Structural basis for regulation of rhizobial nodulation and symbiosis gene expression by the regulatory protein NolR.

    Science.gov (United States)

    Lee, Soon Goo; Krishnan, Hari B; Jez, Joseph M

    2014-04-29

    The symbiosis between rhizobial microbes and host plants involves the coordinated expression of multiple genes, which leads to nodule formation and nitrogen fixation. As part of the transcriptional machinery for nodulation and symbiosis across a range of Rhizobium, NolR serves as a global regulatory protein. Here, we present the X-ray crystal structures of NolR in the unliganded form and complexed with two different 22-base pair (bp) double-stranded operator sequences (oligos AT and AA). Structural and biochemical analysis of NolR reveals protein-DNA interactions with an asymmetric operator site and defines a mechanism for conformational switching of a key residue (Gln56) to accommodate variation in target DNA sequences from diverse rhizobial genes for nodulation and symbiosis. This conformational switching alters the energetic contributions to DNA binding without changes in affinity for the target sequence. Two possible models for the role of NolR in the regulation of different nodulation and symbiosis genes are proposed. To our knowledge, these studies provide the first structural insight on the regulation of genes involved in the agriculturally and ecologically important symbiosis of microbes and plants that leads to nodule formation and nitrogen fixation.

  1. Hydropower : A Regulatory Guide to Permitting and Licensing in Idaho, Montana, Oregon, and Washington.

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Gilbert A.

    1992-12-01

    The design, construction and operation of a hydropower project can result in many potential impacts. These potential impacts are of concern to a host of federal, state, and local authorities. Early consultation with land and water management, fish and wildlife resource protection, and health and human safety-oriented agencies should occur to determine specific concerns and study requirements for each proposed project. This Guide to Permitting and Licensing outlines the characteristic features of attractive hydropower sites; summarizes an array of developmental constraints; illustrates potential environmental impacts and concerns; and summarizes all federal, state, and local permitting and licensing requirements.

  2. Hydropower: A Regulatory Guide to Permitting and Licensing in Idaho, Montana, Oregon, and Washington.

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Gilbert A.

    1992-12-01

    The design, construction and operation of a hydropower project can result in many potential impacts. These potential impacts are of concern to a host of federal, state, and local authorities. Early consultation with land and water management, fish and wildlife resource protection, and health and human safety-oriented agencies should occur to determine specific concerns and study requirements for each proposed project. This Guide to Permitting and Licensing outlines the characteristic features of attractive hydropower sites; summarizes an array of developmental constraints; illustrates potential environmental impacts and concerns; and summarizes all federal, state, and local permitting and licensing requirements.

  3. Geothermal : A Regulatory Guide to Leasing, Permitting, and Licensing in Idaho, Montana, Oregon, and Washington.

    Energy Technology Data Exchange (ETDEWEB)

    Bloomquist, R.Gordon

    1991-10-01

    The actual geothermal exploration and development may appear to be a simple and straightforward process in comparison to the legal and institutional maze which the developer must navigate in order to obtain all of the federal, state, and local leases, permits, licenses, and approvals necessary at each step in the process. Finally, and often most difficult, is obtaining a contract for the sale of thermal energy, brine, steam, or electricity. This guide is designed to help developers interested in developing geothermal resource sites in the Bonneville Power Administration Service Territory in the state of Idaho, Montana, Oregon, and Washington better understand the federal, state, and local institutional process, the roles and responsibilities of each agency, and how and when to make contact in order to obtain the necessary documents.

  4. Genomic regions, cellular components and gene regulatory basis underlying pod length variations in cowpea (V. unguiculata L. Walp).

    Science.gov (United States)

    Xu, Pei; Wu, Xinyi; Muñoz-Amatriaín, María; Wang, Baogen; Wu, Xiaohua; Hu, Yaowen; Huynh, Bao-Lam; Close, Timothy J; Roberts, Philip A; Zhou, Wen; Lu, Zhongfu; Li, Guojing

    2017-05-01

    Cowpea (V. unguiculata L. Walp) is a climate resilient legume crop important for food security. Cultivated cowpea (V. unguiculata L) generally comprises the bushy, short-podded grain cowpea dominant in Africa and the climbing, long-podded vegetable cowpea popular in Asia. How selection has contributed to the diversification of the two types of cowpea remains largely unknown. In the current study, a novel genotyping assay for over 50 000 SNPs was employed to delineate genomic regions governing pod length. Major, minor and epistatic QTLs were identified through QTL mapping. Seventy-two SNPs associated with pod length were detected by genome-wide association studies (GWAS). Population stratification analysis revealed subdivision among a cowpea germplasm collection consisting of 299 accessions, which is consistent with pod length groups. Genomic scan for selective signals suggested that domestication of vegetable cowpea was accompanied by selection of multiple traits including pod length, while the further improvement process was featured by selection of pod length primarily. Pod growth kinetics assay demonstrated that more durable cell proliferation rather than cell elongation or enlargement was the main reason for longer pods. Transcriptomic analysis suggested the involvement of sugar, gibberellin and nutritional signalling in regulation of pod length. This study establishes the basis for map-based cloning of pod length genes in cowpea and for marker-assisted selection of this trait in breeding programmes. © 2016 The Authors. Plant Biotechnology Journal published by Society for Experimental Biology and The Association of Applied Biologists and John Wiley & Sons Ltd.

  5. Radiation dose to the embryo/fetus: Draft Regulatory Guide DG-8011

    International Nuclear Information System (INIS)

    1992-02-01

    Section 20.1208 of 10 CFR Part 20, ''Standards for Protection Against Radiation,'' requires that each licensee ensure that the dose to an embryo/fetus during the entire pregnancy, from occupational exposure of a declared pregnant woman, does not exceed 0.5 rem (5 mSv). Paragraph 20.1208(b) requires the licensee to make efforts to avoid substantial variation above a uniform monthly exposure rate to a declared pregnant woman that would satisfy the 0.5 rem limit. The dose to the embryo/fetus is to be the sum of (1) the deep-dose equivalent to the declared pregnant woman (10 CFR 10.1208(c)(1)) and (2) the dose to the embryo/fetus from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman (10 CFR 20.1208(c)(2)). This guide is being developed to provide guidance on calculating the radiation dose to the embryo/fetus

  6. Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2013-01-01

    Nuclear terrorism and the illicit trafficking of nuclear and other radioactive material threaten the security of all States. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The possibility that nuclear and other radioactive material may be used for terrorist acts cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material, and to establish capabilities for detection and response to nuclear and other radioactive material out of regulatory control. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This approach recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in nuclear and other radioactive material; national response plans; and contingency measures. Within its nuclear security programme, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking; and to detect and respond to nuclear security events. This is an Implementing Guide on nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control. The objective of the publication is to provide guidance to Member States for the

  7. Development of the regulatory guide on the management of aging for the operating NPP

    International Nuclear Information System (INIS)

    Shin, Tae Myung; Lee, Jae Kyung; Byeon, Chang Soo; Kim, Hyo Soo; Kim, Young Ryul; Eun, Hui Kwang

    2000-03-01

    this is the first final report, and it includes the analysis of PSR regulation status for the operating NPP of foreign countries and thus established scope and method of Korean PSR. The detailed requirements of aging management, as one of the most important factors, is planned to be dealt in the second final report, The result of study so far can be summarized as below, The necessity and feasibility of domestic PSR application is confirmed through the investigation, comparison and review of PSR implementation and regulation status in foreign countries, And, detailed analysis of vaseline guidelines of IAEA performed to establish a skeleton of desirable safety review guideline for Korean NPP. Our own objectives, scope and strategy of review for PWR are roughly set up form factor by factor analysis of PSR implementation experience in foreign countries and background of IAEA guidelines. The essential elements of review for each PSR safety factors are classified and proposed. For efficient review of proposed safety factors and elements, three different option of framework for PSR guidelines are proposed and compared. Through analysis of strength safety factors and elements, three different options of framework for PSR guidelines are proposed and compared. Through analysis of strength and weakness of the three optional frameworks proposed for Korean PSR guideline, the third one is recommended as the best for both owner and regulator. By maintaining the current framework of SAR at maximum and, at the same time, referring the basic concept of IAEA PSR guide, the detailed contents and its review elements are chosen. The standards on the aging was proposed preliminarily for the application of aging evaluation in PSR

  8. Development of the regulatory guide on the management of aging for the operating NPP

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Tae Myung; Lee, Jae Kyung; Byeon, Chang Soo; Kim, Hyo Soo [Chungju Univ., Cheongju (Korea, Republic of); Kim, Young Ryul; Eun, Hui Kwang [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-03-15

    this is the first final report, and it includes the analysis of PSR regulation status for the operating NPP of foreign countries and thus established scope and method of Korean PSR. The detailed requirements of aging management, as one of the most important factors, is planned to be dealt in the second final report, The result of study so far can be summarized as below, The necessity and feasibility of domestic PSR application is confirmed through the investigation, comparison and review of PSR implementation and regulation status in foreign countries, And, detailed analysis of vaseline guidelines of IAEA performed to establish a skeleton of desirable safety review guideline for Korean NPP. Our own objectives, scope and strategy of review for PWR are roughly set up form factor by factor analysis of PSR implementation experience in foreign countries and background of IAEA guidelines. The essential elements of review for each PSR safety factors are classified and proposed. For efficient review of proposed safety factors and elements, three different option of framework for PSR guidelines are proposed and compared. Through analysis of strength safety factors and elements, three different options of framework for PSR guidelines are proposed and compared. Through analysis of strength and weakness of the three optional frameworks proposed for Korean PSR guideline, the third one is recommended as the best for both owner and regulator. By maintaining the current framework of SAR at maximum and, at the same time, referring the basic concept of IAEA PSR guide, the detailed contents and its review elements are chosen. The standards on the aging was proposed preliminarily for the application of aging evaluation in PSR.

  9. General Fit-Basis Functions and Specialized Coordinates in an Adaptive Density-Guided Approach to Potential Energy Surfaces

    DEFF Research Database (Denmark)

    Klinting, Emil Lund; Thomsen, Bo; Godtliebsen, Ian Heide

    . This results in a decreased number of single point calculations required during the potential construction. Especially the Morse-like fit-basis functions are of interest, when combined with rectilinear hybrid optimized and localized coordinates (HOLCs), which can be generated as orthogonal transformations......The overall shape of a molecular energy surface can be very different for different molecules and different vibrational coordinates. This means that the fit-basis functions used to generate an analytic representation of a potential will be met with different requirements. It is therefore worthwhile...... single point calculations when constructing the molecular potential. We therefore present a uniform framework that can handle general fit-basis functions of any type which are specified on input. This framework is implemented to suit the black-box nature of the ADGA in order to avoid arbitrary choices...

  10. Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide (Arabic Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance to Member States for the development, or improvement of nuclear security systems and measures for the detection of criminal or unauthorized acts with nuclear security implications involving nuclear and other radioactive material out of regulatory control. It describes the elements of an effective nuclear security detection architecture which is composed of an integrated set of nuclear security systems and measures, and is based on an appropriate legal and regulatory framework for the implementation of the national detection strategy. The publication is an implementing guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, legislative bodies, competent authorities, institutions, and individuals involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control

  11. Anatomical basis for simultaneous block of greater and third occipital nerves, with an ultrasound-guided technique.

    Science.gov (United States)

    Kariya, Ken; Usui, Yosuke; Higashi, Naoko; Nakamoto, Tatsuo; Shimbori, Hironobu; Terada, Satoshi; Takahashi, Hideo; Ueta, Hisashi; Kitazawa, Yusuke; Sawanobori, Yasushi; Okuda, Yasuhisa; Matsuno, Kenjiro

    2017-11-13

    In some headache disorders, for which the greater occipital nerve block is partly effective, the third occipital nerve is also suggested to be involved. We aimed to establish a simple technique for simultaneously blocking the greater and third occipital nerves. We performed a detailed examination of dorsal neck anatomy in 33 formalin-fixed cadavers, and deduced two candidate target points for blocking both the greater and third occipital nerves. These target points were tested on three Thiel-fixed cadavers. We performed ultrasound-guided dye injections into these points, examined the results by dissection, and selected the most suitable injection point. Finally, this target point was tested in three healthy volunteers. We injected 4 ml of local anesthetic and 1 ml of radiopaque material at the selected point, guided with a standard ultrasound system. Then, the pattern of local anesthetic distribution was imaged with computed tomography. We deduced that the most suitable injection point was the medial head of the semispinalis capitis muscle at the C1 level of the cervical vertebra. Both nerves entered this muscle, in close proximity, with little individual variation. In healthy volunteers, an anesthetic injected was confined to the muscle and induced anesthesia in the skin areas innervated by both nerves. The medial head of the semispinalis capitis muscle is a suitable landmark for blocking the greater and third occipital nerves simultaneously, by which occipital nerve involvement in various headache disorders may be rapidly examined and treated.

  12. Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

    Energy Technology Data Exchange (ETDEWEB)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01

    The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk – as a function of different configurations – in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

  13. 77 FR 40385 - Withdrawal of Regulatory Guide 7.3; Procedures for Picking Up and Receiving Packages of...

    Science.gov (United States)

    2012-07-09

    ... Picking Up and Receiving Packages of Radioactive Material AGENCY: Nuclear Regulatory Commission. ACTION.... Nuclear Regulatory Commission (NRC or Commission) is withdrawing RG 7.3, ``Procedures for Picking Up and... Public Document Room (PDR) reference staff at 1-800-397-4209, or 301-415-4737, or by email at PDR...

  14. WHO informal consultation on scientific basis for regulatory evaluation of candidate human vaccines from plants, Geneva, Switzerland, 24-25 January 2005.

    NARCIS (Netherlands)

    Laan, Jan Willem van der; Minor, Philip; Mahoney, Richard; Arntzen, Charles; Shin, Jinho; Wood, David

    2006-01-01

    In January 2005, WHO convened a meeting of leading experts in plant-derived vaccines and experts from regulatory authorities for an informal discussion on the state-of-the-art and to analyse whether specific guidance might be needed for plant-derived vaccines that is not yet provided by regulatory

  15. Development approach on usage of radiation and inspection of QA according to the change of approval procedure of safety regulatory guides

    International Nuclear Information System (INIS)

    Oh, B. J.; Ahn, H. Z.; Kim, S. W.; Yoo, S. O.; Kang, S. C.; Yang, S. H.; Han, S. J.; Kim, H. S.; Kim, H. J.

    2002-01-01

    In accordance with 2001 amendment of the Atomic Energy Act(AEA), KINS also amended its internal 'Regulation on Implementation of Entrusted AEA-related Work'. Up to now the nuclear safety-specialized institute has used its internally developed guidelines in the safety regulation. From now on, however, the institute will enhance the objectivity and transparency by having the instruments approved by the Ministry of Science ad Technology. In this paper, we introduced the major points and directions to be considered to the development of the safety regulatory guides on Inspection for the quality assurance of the nuclear reactor facilities and the use of radioisotopes, and review and inspection for dosimeter reading

  16. Regulatory and law framework of agricultural methanization and composting activities. User's guide; Le cadre reglementaire et juridique des activites agricoles de methanisation et de compostage. Guide Pratique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-08-15

    After a presentation of the general context of organic waste management (its techniques, materials, legal and regulatory sources, i.e. European and French laws), this guide indicates the main regulatory and law aspects to those wishing to implement a project of methanization or composting of organic by-products in the agricultural sector. Several aspects are therefore discussed and presented in practical sheets. They concern the health and environment regulation, but not the professional risk prevention (explosion, fire, and so on). These aspects are the project setting up, input materials (animal by-products, organic materials coming from agricultural production or from out of it), waste collection and transport, process steps, organic product valorization, biogas valorization, solid and liquid release management

  17. Regulatory Guide 1.131: Qualification tests of electric cables, field splices, and connections for light-water-cooled nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Criterion III, ''Design Control,'' of Appendix B, ''Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plant,'' to 10 CFR Part 50, ''Licensing of Production and Utilization Facilities,'' requires that, where a test program is used to verify the adequacy of a specific design feature, it include suitable qualification testing of a prototype unit under the most adverse design conditions. This regulatory guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification testing of electric cables, field splices, and connections for service in light-water-cooled nuclear power plants to ensure that the cables, field splices, and connections can perform their safety-related functions. The fire test provisions of this guide do not apply to qualification for an installed configuration

  18. 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

  19. Implementation to the guide and regulatory procedures elaborated in mark the ARCAL XX project for the teletherapy practices

    International Nuclear Information System (INIS)

    Peres Reyes, Y.; Betancourt Hernandez, L.A.; De la Fuente Punch, A.

    1998-01-01

    From the beginning of ARCAL XX, the activities have been guided to homogenize the conditions the radiological security in the different ones you practice associated to the ionizing radiations uses, on the fundamental base to the adoption that the International Basic Standards on Radiation Protection for the ionizing radiation and the Security to the Radiation sources

  20. Regulatory viewpoint on nuclear fuel quality assurance

    International Nuclear Information System (INIS)

    Tripp, L.E.

    1976-01-01

    Considerations of the importance of fuel quality and performance to nuclear safety, ''as low reasonably achievable'' release of radioactive materials in reactor effluents, and past fuel performance problems demonstrate the need for strong regulatory input, review and inspection of nuclear fuel quality assurance programs at all levels. Such a regulatory program is being applied in the United States of America by the US Nuclear Regulatory Commission. Quality assurance requirements are contained within government regulations. Guidance on acceptable methods of implementing portions of the quality assurance program is contained within Regulatory Guides and other NRC documents. Fuel supplier quality assurance program descriptions are reviewed as a part of the reactor licensing process. Inspections of reactor licensee control of their fuel vendors as well as direct inspections of fuel vendor quality assurance programs are conducted on a regularly scheduled basis. (author)

  1. Official publication of the regulatory guide concerning control of LAW and MAW with negligible heat release, which are not delivered to the waste collection station of the Land

    International Nuclear Information System (INIS)

    1989-01-01

    Control of the LAW and MAW from nuclear installations is to be made so as to ensure that amounts, residence and status of conditioning of the wastes can be determined any time in order to provide for a safe interim storage or ultimate disposal by supervision and control of all waste management steps (waste treatment, conditioning, interim storage, transport). The checks have to determine the radionuclide inventory, and, independent of aforesaid measurements, the nuclear fuel content (e.g. Pu) has to be declared if the limit of 74 Bq/g is exceeded. The provisions of the regulatory guide are intended to be valid for a period of three years, and shall then be replaced by a statutory instrument (an ordinance to be prepared by the joint Committee of the Laender for Nuclear Energy - Executive Committee). (orig./HP) [de

  2. Two standards - CSA-N288.1 and USNRC regulatory guides 1.109, 1.111 for chronic atmospheric releases from nuclear facilities - compared

    International Nuclear Information System (INIS)

    Peterson, S-R.

    1997-05-01

    Although the Canadian Standards Association's 'Guidelines for Calculating Derived Release Limits for Radioactive Material in Airborne and Liquid Effluents for Normal Operation of Nuclear Facilities', CSA-N288.1-M87 (CSA 1987) can be used to license CANDU (CANadian Deuterium Uranium) reactors sold off-shore, in practice purchasers may wish to use the United States Regulatory Guides (RG) 1.109 (United States Nuclear Regulatory Commission 1977a) and 1.111 (USNRC 1977b) to calculate doses from routine atmospheric releases to members of a critical group. When differences in dose predictions are found between the two standards, CSA-N288.1 comes under attack. This paper explains the differences between the two models. The two atmospheric dispersion models were compared for a ground level release and an elevated release such as from CANDU 6. For a ground level release, CSA's dilution factors were slightly more than half of RG's. For the elevated release, following recommendations in each guide, CSA's dilution coefficient is higher than RG's within 1000 m of the stack and only slightly lower farther away. All differences can be accounted for by different mathematical formulations and assumptions about height at which wind speed is measured. Ingestion, inhalation, immersion and external doses predicted by the two models were compared for unit release (Bq s -1 ) and for realistic source terms of a suite of 33 radionuclides commonly released from both CANDUs and Pressurized Water Reactors (PWRs). To demonstrate real differences in the models, ingestion doses for the two models were compared using the CSA diet in both models and CSA predictions were recalculated to account for decay which occurs between harvest and ingestion in RG. Once all assumptions are equalized, there is very little difference in dose predictions of the two models that cannot be explained by different parameter values. Both models have outdated dose conversion factors, and the use of improved numbers will

  3. A genome-wide analysis of the RNA-guided silencing pathway in coffee reveals insights into its regulatory mechanisms.

    Directory of Open Access Journals (Sweden)

    Christiane Noronha Fernandes-Brum

    Full Text Available microRNAs (miRNAs are derived from self-complementary hairpin structures, while small-interfering RNAs (siRNAs are derived from double-stranded RNA (dsRNA or hairpin precursors. The core mechanism of sRNA production involves DICER-like (DCL in processing the smallRNAs (sRNAs and ARGONAUTE (AGO as effectors of silencing, and siRNA biogenesis also involves action of RNA-Dependent RNA Polymerase (RDR, Pol IV and Pol V in biogenesis. Several other proteins interact with the core proteins to guide sRNA biogenesis, action, and turnover. We aimed to unravel the components and functions of the RNA-guided silencing pathway in a non-model plant species of worldwide economic relevance. The sRNA-guided silencing complex members have been identified in the Coffea canephora genome, and they have been characterized at the structural, functional, and evolutionary levels by computational analyses. Eleven AGO proteins, nine DCL proteins (which include a DCL1-like protein that was not previously annotated, and eight RDR proteins were identified. Another 48 proteins implicated in smallRNA (sRNA pathways were also identified. Furthermore, we identified 235 miRNA precursors and 317 mature miRNAs from 113 MIR families, and we characterized ccp-MIR156, ccp-MIR172, and ccp-MIR390. Target prediction and gene ontology analyses of 2239 putative targets showed that significant pathways in coffee are targeted by miRNAs. We provide evidence of the expansion of the loci related to sRNA pathways, insights into the activities of these proteins by domain and catalytic site analyses, and gene expression analysis. The number of MIR loci and their targeted pathways highlight the importance of miRNAs in coffee. We identified several roles of sRNAs in C. canephora, which offers substantial insight into better understanding the transcriptional and post-transcriptional regulation of this major crop.

  4. Regulatory Guidance for Lightning Protection in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kisner, Roger A.; Wilgen, John B.; Ewing, Paul D.; Korsah, Kofi; Antonescu, Christina E.

    2006-01-01

    Oak Ridge National Laboratory (ORNL) was engaged by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) to develop the technical basis for regulatory guidance to address design and implementation practices for lightning protection systems in nuclear power plants (NPPs). Lightning protection is becoming increasingly important with the advent of digital and low-voltage analog systems in NPPs. These systems have the potential to be more vulnerable than older analog systems to the resulting power surges and electromagnetic interference (EMI) when lightning strikes facilities or power lines. This paper discusses the technical basis for guidance to licensees and applicants covered in Regulatory Guide (RG) 1.204, Guidelines for Lightning Protection of Nuclear Power Plants, issued August 2005. RG 1.204 describes guidance for practices that are acceptable to the NRC staff for protecting nuclear power structures and systems from direct lightning strikes and the resulting secondary effects.

  5. U.S. Nuclear Regulatory Commission Extremely Low Probability of Rupture pilot study: xLPR framework model user's guide

    International Nuclear Information System (INIS)

    Kalinich, Donald A.; Sallaberry, Cedric M.; Mattie, Patrick D.

    2010-01-01

    For the U.S. Nuclear Regulatory Commission (NRC) Extremely Low Probability of Rupture (xLPR) pilot study, Sandia National Laboratories (SNL) was tasked to develop and evaluate a probabilistic framework using a commercial software package for Version 1.0 of the xLPR Code. Version 1.0 of the xLPR code is focused assessing the probability of rupture due to primary water stress corrosion cracking in dissimilar metal welds in pressurizer surge nozzles. Future versions of this framework will expand the capabilities to other cracking mechanisms, and other piping systems for both pressurized water reactors and boiling water reactors. The goal of the pilot study project is to plan the xLPR framework transition from Version 1.0 to Version 2.0; hence the initial Version 1.0 framework and code development will be used to define the requirements for Version 2.0. The software documented in this report has been developed and tested solely for this purpose. This framework and demonstration problem will be used to evaluate the commercial software's capabilities and applicability for use in creating the final version of the xLPR framework. This report details the design, system requirements, and the steps necessary to use the commercial-code based xLPR framework developed by SNL.

  6. Good Manufacturing Practice-Compliant Production and Lot-Release of Ex Vivo Expanded Regulatory T Cells As Basis for Treatment of Patients with Autoimmune and Inflammatory Disorders

    Directory of Open Access Journals (Sweden)

    Manuel Wiesinger

    2017-10-01

    Full Text Available In recent years, the exploration of regulatory T cell (Treg-based cellular therapy has become an attractive strategy to ameliorate inflammation and autoimmunity in various clinical settings. The main obstacle to the clinical application of Treg in human is their low number circulating in peripheral blood. Therefore, ex vivo expansion is inevitable. Moreover, isolation of Treg bears the risk of concurrent isolation of unwanted effector cells, which may trigger or deteriorate inflammation upon adoptive Treg transfer. Here, we present a protocol for the GMP-compliant production, lot-release and validation of ex vivo expanded Tregs for treatment of patients with autoimmune and inflammatory disorders. In the presented production protocol, large numbers of Treg, previously enriched from a leukapheresis product by using the CliniMACS® system, are ex vivo expanded in the presence of anti-CD3/anti-CD28 expander beads, exogenous IL-2 and rapamycin during 21 days. The expanded Treg drug product passed predefined lot-release criteria. These criteria include (i sterility testing, (ii assessment of Treg phenotype, (iii assessment of non-Treg cellular impurities, (iv confirmation of successful anti-CD3/anti-CD28 expander bead removal after expansion, and (v confirmation of the biological function of the Treg product. Furthermore, the Treg drug product was shown to retain its stability and suppressive function for at least 1 year after freezing and thawing. Also, dilution of the Treg drug product in 0.9% physiological saline did not affect Treg phenotype and Treg function for up to 90 min. These data indicate that these cells are ready to use in a clinical setting in which a cell infusion time of up to 90 min can be expected. The presented production process has recently undergone on site GMP-conform evaluation and received GMP certification from the Bavarian authorities in Germany. This protocol can now be used for Treg-based therapy of various

  7. Guide for 3D WARP simulations of hollow electron beam lenses. Practical explanation on basis of Tevatron electron lens test stand

    Energy Technology Data Exchange (ETDEWEB)

    Moens, Vince [Ecole Polytechnique Federale de Lausanne (EPFL) (Switzerland)

    2014-06-08

    The purpose of this guide is to help successive students handle WARP. It outlines the installation of WARP on personal computers as well as super-computers and clusters. It furthermore teaches the reader how to handle the WARP environment and run basic scripts. Lastly it outlines how to execute the current Hollow Electron Beam Lens scripts.

  8. A study on the establishment of the regulatory guide to the characteristics and classification criteria of low and intermediate level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Geon Jae; Paek, Min Hoon; Park, Jong Gil; Han, Byeong Seop; Cheong, Jae Hak; Lee, Hae Chan; Yang, Jin Yeong; Hong, Hei Kwan; Park, Jin Baek [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1995-01-15

    The objectives of this study are the development of regulatory guidance to the establishment of the necessary technology standard of the characteristics and classification criteria of low and intermediate level radioactive waste for the safe operation of the waste repositories. In followings, the contents of our report will be presented in two parts. Survey of the characteristics of radioactive waste : investigate and analyze the source, types and characteristics of domestic radioactive waste as a basis for this study, radiochemical analysis of radioactive waste based on foreign and domestic data base, determination of the methodology for the application of the characteristic analysis of waste classification technology. Establishment of the classification criteria of the radioactive waste : collection and analysis of foreign and domestic data base on the classification methodology and criteria, development of low and intermediate level waste classification criteria and the set up of the classification methodology through the analysis of waste data, establishment of the systematic classification methodology of the low and intermediate radioactive waste through the careful survey of the current domestic regulation.

  9. Regulatory Guide 1.122: Development of floor design response spectra for seismic design of floor-supported equipment or components

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    ''Reactor Site Criteria,'' requires, in part, that safety-related structures, systems, and components remain functional in the event of a Safe Shutdown Earthquake (SSE). It specifies the use of a suitable dynamic analysis as one method of ensuring that the structures, systems, and components can withstand the seismic loads. Similarly, paragraph (a)(2) of Section VI of the same appendix requires, in part, that the structures, systems, and components necessary for continued operation without undue risk to the health and safety of the public remain functional in the event of an Operating Basis Earthquake (OBE). Again, the use of suitable dynamic analysis is specified as one method of ensuring that the structures, systems, and components can withstand the seismic loads. This guide describes methods acceptable to the NRC staff for developing two horizontal and one vertical floor design response spectra at various floors or other equipment-support locations of interest from the time-history motions resulting from the dynamic analysis of the supporting structure. These floor design response spectra are needed for the dynamic analysis of the systems or equipment supported at various locations of the supporting structure

  10. Radioactive Waste Management Basis

    International Nuclear Information System (INIS)

    Perkins, B.K.

    2009-01-01

    The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  11. An extended action for the effective field theory of dark energy: a stability analysis and a complete guide to the mapping at the basis of EFTCAMB

    International Nuclear Information System (INIS)

    Frusciante, Noemi; Papadomanolakis, Georgios; Silvestri, Alessandra

    2016-01-01

    We present a generalization of the effective field theory (EFT) formalism for dark energy and modified gravity models to include operators with higher order spatial derivatives. This allows the extension of the EFT framework to a wider class of gravity theories such as Hořava gravity. We present the corresponding extended action, both in the EFT and the Arnowitt-Deser-Misner (ADM) formalism, and proceed to work out a convenient mapping between the two, providing a self contained and general procedure to translate a given model of gravity into the EFT language at the basis of the Einstein-Boltzmann solver EFTCAMB. Putting this mapping at work, we illustrate, for several interesting models of dark energy and modified gravity, how to express them in the ADM notation and then map them into the EFT formalism. We also provide for the first time, the full mapping of GLPV models into the EFT framework. We next perform a thorough analysis of the physical stability of the generalized EFT action, in absence of matter components. We work out viability conditions that correspond to the absence of ghosts and modes that propagate with a negative speed of sound in the scalar and tensor sector, as well as the absence of tachyonic modes in the scalar sector. Finally, we extend and generalize the phenomenological basis in terms of α-functions introduced to parametrize Horndeski models, to cover all theories with higher order spatial derivatives included in our extended action. We elaborate on the impact of the additional functions on physical quantities, such as the kinetic term and the speeds of propagation for scalar and tensor modes.

  12. Guide relative to the regulatory requirements applicable to the radioactive materials transport in airport area; Guide relatif aux exigences reglementaires applicables au transport des matieres radioactives en zone aeroportuaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

    This guide makes an inventory of all the points necessary for the correct functioning of the transport of radioactive materials in airport zone. Stowage of the parcels, program of radiological protection (P.R.P.), operation of transport, quality assurance, radiation dose evaluation, radiation monitoring, dose optimization, storage management, are the principal points of this guide. (N.C.)

  13. DLX5, FGF8 and the Pin1 isomerase control ΔNp63α protein stability during limb development: a regulatory loop at the basis of the SHFM and EEC congenital malformations

    Science.gov (United States)

    Restelli, Michela; Lopardo, Teresa; Lo Iacono, Nadia; Garaffo, Giulia; Conte, Daniele; Rustighi, Alessandra; Napoli, Marco; Del Sal, Giannino; Perez-Morga, David; Costanzo, Antonio; Merlo, Giorgio Roberto; Guerrini, Luisa

    2014-01-01

    Ectrodactyly, or Split-Hand/Foot Malformation (SHFM), is a congenital condition characterized by the loss of central rays of hands and feet. The p63 and the DLX5;DLX6 transcription factors, expressed in the embryonic limb buds and ectoderm, are disease genes for these conditions. Mutations of p63 also cause the ectodermal dysplasia–ectrodactyly–cleft lip/palate (EEC) syndrome, comprising SHFM. Ectrodactyly is linked to defects of the apical ectodermal ridge (AER) of the developing limb buds. FGF8 is the key signaling molecule in this process, able to direct proximo-distal growth and patterning of the skeletal primordial of the limbs. In the limb buds of both p63 and Dlx5;Dlx6 murine models of SHFM, the AER is poorly stratified and FGF8 expression is severely reduced. We show here that the FGF8 locus is a downstream target of DLX5 and that FGF8 counteracts Pin1–ΔNp63α interaction. In vivo, lack of Pin1 leads to accumulation of the p63 protein in the embryonic limbs and ectoderm. We show also that ΔNp63α protein stability is negatively regulated by the interaction with the prolyl-isomerase Pin1, via proteasome-mediated degradation; p63 mutant proteins associated with SHFM or EEC syndromes are resistant to Pin1 action. Thus, DLX5, p63, Pin1 and FGF8 participate to the same time- and location-restricted regulatory loop essential for AER stratification, hence for normal patterning and skeletal morphogenesis of the limb buds. These results shed new light on the molecular mechanisms at the basis of the SHFM and EEC limb malformations. PMID:24569166

  14. DLX5, FGF8 and the Pin1 isomerase control ΔNp63α protein stability during limb development: a regulatory loop at the basis of the SHFM and EEC congenital malformations.

    Science.gov (United States)

    Restelli, Michela; Lopardo, Teresa; Lo Iacono, Nadia; Garaffo, Giulia; Conte, Daniele; Rustighi, Alessandra; Napoli, Marco; Del Sal, Giannino; Perez-Morga, David; Costanzo, Antonio; Merlo, Giorgio Roberto; Guerrini, Luisa

    2014-07-15

    Ectrodactyly, or Split-Hand/Foot Malformation (SHFM), is a congenital condition characterized by the loss of central rays of hands and feet. The p63 and the DLX5;DLX6 transcription factors, expressed in the embryonic limb buds and ectoderm, are disease genes for these conditions. Mutations of p63 also cause the ectodermal dysplasia-ectrodactyly-cleft lip/palate (EEC) syndrome, comprising SHFM. Ectrodactyly is linked to defects of the apical ectodermal ridge (AER) of the developing limb buds. FGF8 is the key signaling molecule in this process, able to direct proximo-distal growth and patterning of the skeletal primordial of the limbs. In the limb buds of both p63 and Dlx5;Dlx6 murine models of SHFM, the AER is poorly stratified and FGF8 expression is severely reduced. We show here that the FGF8 locus is a downstream target of DLX5 and that FGF8 counteracts Pin1-ΔNp63α interaction. In vivo, lack of Pin1 leads to accumulation of the p63 protein in the embryonic limbs and ectoderm. We show also that ΔNp63α protein stability is negatively regulated by the interaction with the prolyl-isomerase Pin1, via proteasome-mediated degradation; p63 mutant proteins associated with SHFM or EEC syndromes are resistant to Pin1 action. Thus, DLX5, p63, Pin1 and FGF8 participate to the same time- and location-restricted regulatory loop essential for AER stratification, hence for normal patterning and skeletal morphogenesis of the limb buds. These results shed new light on the molecular mechanisms at the basis of the SHFM and EEC limb malformations. © The Author 2014. Published by Oxford University Press.

  15. Determination of Design Basis Earthquake ground motion

    International Nuclear Information System (INIS)

    Kato, Muneaki

    1997-01-01

    This paper describes principle of determining of Design Basis Earthquake following the Examination Guide, some examples on actual sites including earthquake sources to be considered, earthquake response spectrum and simulated seismic waves. In sppendix of this paper, furthermore, seismic safety review for N.P.P designed before publication of the Examination Guide was summarized with Check Basis Earthquake. (J.P.N.)

  16. Determination of Design Basis Earthquake ground motion

    Energy Technology Data Exchange (ETDEWEB)

    Kato, Muneaki [Japan Atomic Power Co., Tokyo (Japan)

    1997-03-01

    This paper describes principle of determining of Design Basis Earthquake following the Examination Guide, some examples on actual sites including earthquake sources to be considered, earthquake response spectrum and simulated seismic waves. In sppendix of this paper, furthermore, seismic safety review for N.P.P designed before publication of the Examination Guide was summarized with Check Basis Earthquake. (J.P.N.)

  17. Regulatory agencies and regulatory risk

    OpenAIRE

    Knieps, Günter; Weiß, Hans-Jörg

    2008-01-01

    The aim of this paper is to show that regulatory risk is due to the discretionary behaviour of regulatory agencies, caused by a too extensive regulatory mandate provided by the legislator. The normative point of reference and a behavioural model of regulatory agencies based on the positive theory of regulation are presented. Regulatory risk with regard to the future behaviour of regulatory agencies is modelled as the consequence of the ex ante uncertainty about the relative influence of inter...

  18. An Exploration of the Legal and Regulatory Environment of Privacy and Security through Active Research, Guided Study, Blog Creation, and Discussion

    Science.gov (United States)

    Peslak, Alan R.

    2010-01-01

    One of the most important topics for today's information technology professional is the study of legal and regulatory issues as they relate to privacy and security of personal and business data and identification. This manuscript describes the topics and approach taken by the instructors that focuses on independent research of source documents and…

  19. A compact, in vivo screen of all 6-mers reveals drivers of tissue-specific expression and guides synthetic regulatory element design.

    Science.gov (United States)

    Smith, Robin P; Riesenfeld, Samantha J; Holloway, Alisha K; Li, Qiang; Murphy, Karl K; Feliciano, Natalie M; Orecchia, Lorenzo; Oksenberg, Nir; Pollard, Katherine S; Ahituv, Nadav

    2013-07-18

    Large-scale annotation efforts have improved our ability to coarsely predict regulatory elements throughout vertebrate genomes. However, it is unclear how complex spatiotemporal patterns of gene expression driven by these elements emerge from the activity of short, transcription factor binding sequences. We describe a comprehensive promoter extension assay in which the regulatory potential of all 6 base-pair (bp) sequences was tested in the context of a minimal promoter. To enable this large-scale screen, we developed algorithms that use a reverse-complement aware decomposition of the de Bruijn graph to design a library of DNA oligomers incorporating every 6-bp sequence exactly once. Our library multiplexes all 4,096 unique 6-mers into 184 double-stranded 15-bp oligomers, which is sufficiently compact for in vivo testing. We injected each multiplexed construct into zebrafish embryos and scored GFP expression in 15 tissues at two developmental time points. Twenty-seven constructs produced consistent expression patterns, with the majority doing so in only one tissue. Functional sequences are enriched near biologically relevant genes, match motifs for developmental transcription factors, and are required for enhancer activity. By concatenating tissue-specific functional sequences, we generated completely synthetic enhancers for the notochord, epidermis, spinal cord, forebrain and otic lateral line, and show that short regulatory sequences do not always function modularly. This work introduces a unique in vivo catalog of short, functional regulatory sequences and demonstrates several important principles of regulatory element organization. Furthermore, we provide resources for designing compact, reverse-complement aware k-mer libraries.

  20. Radiation practices and regulatory control

    International Nuclear Information System (INIS)

    1997-01-01

    The general principles to be observed in the regulatory control of ionizing radiation use and practices are specified in the guide. It also takes into account of additions and alterations needed for for compliance with the European Union (EU) directives that have not been mentioned in other STUK/ST-guides. (6 refs.)

  1. Radiation practices and regulatory control

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The general principles to be observed in the regulatory control of ionizing radiation use and practices are specified in the guide. It also takes into account of additions and alterations needed for for compliance with the European Union (EU) directives that have not been mentioned in other STUK/ST-guides. (6 refs.).

  2. 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

  3. The integration of the quality assurance approach into the regulatory review stages in Italy

    International Nuclear Information System (INIS)

    Maniori, D.

    1979-01-01

    The control activities of CNEN, the Italian Regulatory Body on Nuclear Power Plant Installations, are carried out on the basis of two main lines of action. These are a thorough and detailed examination of the project at different stages of its development, and a careful assessment of the reliability of the organizations involved in respect of their capability to perform their duties correctly. The paper illustrates in some detail the different stages in which the project examinations are carried out, the documents pertinent to each stage, and the way in which the organizational requirements match the different steps. The regulatory guides and documents prepared on this subject are also briefly presented. (author)

  4. Rationales for regulatory activity

    Energy Technology Data Exchange (ETDEWEB)

    Perhac, R.M. [Univ. of Tennessee, Knoxville, TN (United States)

    1997-02-01

    The author provides an outline which touches on the types of concerns about risk evaluation which are addressed in the process of establishing regulatory guides. Broadly he says regulatory activity serves three broad constituents: (1) Paternalism (private risk); (2) Promotion of social welfare (public risks); (3) Protection of individual rights (public risks). He then discusses some of the major issues encountered in reaching a decision on what is an acceptable level of risk within each of these areas, and how one establishes such a level.

  5. Regulatory environment of transitioning to risk-informed regulations in U.S.A

    International Nuclear Information System (INIS)

    Choi, C. H.; Kim, C. H.

    1999-01-01

    With the publication of the PRA Policy Statement and recent regulatory guides, the U.S.NRC makes a continuous approach towards risk-informed regulations with the goal of establishing an overall framework for risk-informed decisions in all regulatory activities as well as plant specific licensing issues. Faced with the changing environment of deregulation of the electricity generation market, the licensee's effort to reduce design margins to enhance flexibility and to relieve unnecessary regulatory burdens have been focused on the control and reduction of plant operating costs. The risk-informed approach provides a structured, systematic, and defensible method that can be applied not only to rulemaking, but also to licensing, inspection, enforcement, and performance assessment, as well as provides basis for prioritization in the establishment of programs and the allocation of resources. This report describes the current regulatory environment of transitioning to risk-informed regulations with an emphasis on its background, concepts, regulatory guides, proposed options for modifying the 10CFR50, and risk-informed applications in U.S.A. Review of the risk informed applications utilizing the information provided by the PRAs and their insights in the U.S.NRC and nuclear industry will provide the insights of predicting the expected regulation changes in Korea. Also it could provide the applicable methods or guides for the implementation of the risk-informed applications in plant design and operations. (author)

  6. 77 FR 68162 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Regulatory...

    Science.gov (United States)

    2012-11-15

    ... discuss Regulatory Guide 1.79, ``Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors,'' Revision 2, and Regulatory Guide 1.79.1, ``Initial Test Program of Emergency Core...

  7. Regulatory activities

    International Nuclear Information System (INIS)

    2001-01-01

    This publication, compiled in 8 chapters, presents the regulatory system developed by the Nuclear Regulatory Authority (NRA) of the Argentine Republic. The following activities and developed topics in this document describe: the evolution of the nuclear regulatory activity in Argentina; the Argentine regulatory system; the nuclear regulatory laws and standards; the inspection and safeguards of nuclear facilities; the emergency systems; the environmental systems; the environmental monitoring; the analysis laboratories on physical and biological dosimetry, prenatal irradiation, internal irradiation, radiation measurements, detection techniques on nuclear testing, medical program on radiation protection; the institutional relations with national and international organization; the training courses and meeting; the technical information

  8. A Study on Improvement of Test Method of Nuclear Power Plant ESF ACS by applying Regulatory Guide 1.52 (Rev.3)

    International Nuclear Information System (INIS)

    Lee, Sook Kyung; Kim, Kwang Sin; Sohn, Soon Hwan; Song, Kyu Min; Lee, Kae Woo; Cho, Byoung Ho; Park, Jeong Seo; Yoo, Byeang Jea; Hong, Soon Joon; Kang, Sun Haeng

    2010-01-01

    U. S. NRC Regulation Guide 1.52 regulating ESF ACS in nuclear power plants has been revised to revision 3. To apply reduction of operability test time, allowance of alternative challenge agents for in-place leak test of HEPA filters, and upgrade of Methyl Iodide penetration acceptance criterion in activated carbon performance test suggested in Reg. Guide 1.52(Rev.3) on Yonggwang units 5 and 6 ESF ACSes, technical feasibility study was carried out with on-site experiments as well as experiments with a lab-scale model. It was confirmed that the moisture in the system returned to the level before the test in 1 or 4 days even though the moisture was removed during the operability test lasting more than 10 hours. Therefore, it is appropriate to perform monthly operability test in 15 minutes just long enough to check the operability of equipment. To change challenge material for in-place HEPA filter leak test, size of aerosol, production rate, and leak detection capability were compared for DOP and PAO. It was concluded that PAO can be substituted for DOP in nuclear power plants. The upgrade of Methyl Iodide penetration acceptance criterion from 0.175 % to 0.5 % in active carbon filter bed deeper than 4 inches was to conform to the change of activated carbon performance test method to ASTM D3803(1989). It was confirmed that Methyl Iodide penetration acceptance criterion of 0.5 % under 30 .deg. C

  9. Regulatory control for safe usage of radiation sources in India

    International Nuclear Information System (INIS)

    Ghosh, P.K.; Sonawane, A.U.

    1998-01-01

    The widespread applications of radioactive materials and radiation generating equipment in the field of industry, medicine agriculture and research in India necessitated the establishment of an efficient regulatory framework and consequently the Atomic Energy Regulatory Board (AERB) was constituted to exercise regulatory control over the safe usage of the radioactive materials and the radiation generating equipment. The Atomic Energy Act, 1962 and the Radiation Protection Rules, 1971 promulgated under the Act forms the basis of radiation safety in India and Chairman, AERB is the Competent Authority to enforce the regulatory provisions of the Radiation Protection Rules, 1971, for safe use of radiation source in the country. AERB has published a number of documents such as Radiation Surveillance Procedures, Standards, Codes, Guides and Manuals for safe use and handling of radioactive materials and radiation generating equipment. Apart from nuclear fuel cycle documents, these publications pertain to industrial radiography, medical application of radiation, transport of radioactive material, industrial gamma irradiators, X-ray units etc. AERB safety related publications are based on international standards e.g. BSS, IAEA, ICRP, ISO etc. This paper outlines the methodology of regulatory control exercised by AERB for safe use of the radioactive materials and the radiation generating equipment in the country. (author)

  10. Enabling legislation and regulatory determinations for a nuclear power programme

    International Nuclear Information System (INIS)

    Ha Vinh Phuong

    1977-01-01

    General remarks on objectives and scope of enabling legislation, on the regulatory body and on the IAEA activities and assistance in regulatory matters e.g. the IAEA Safety Guides which are in preparation. (HP) [de

  11. System requirements and design description for the document basis database interface (DocBasis)

    International Nuclear Information System (INIS)

    Lehman, W.J.

    1997-01-01

    This document describes system requirements and the design description for the Document Basis Database Interface (DocBasis). The DocBasis application is used to manage procedures used within the tank farms. The application maintains information in a small database to track the document basis for a procedure, as well as the current version/modification level and the basis for the procedure. The basis for each procedure is substantiated by Administrative, Technical, Procedural, and Regulatory requirements. The DocBasis user interface was developed by Science Applications International Corporation (SAIC)

  12. Review of the knowledge available to date on the effects of tritium exposure on health and the environment in Canada - a tool to guide regulatory compliance monitoring

    International Nuclear Information System (INIS)

    Thompson, P.A.; Hamlat, M.S.; Lane, R.; Mihok, S.; Reinhardt, P.; Bundy, K.

    2011-01-01

    The use of tritium in CANDU (Canadian Deuterium-Uranium) reactors, in industry to produce self-luminescent lights and paints, in oil and gas exploration, in hospitals for diagnostic tests and radio-therapeutics, and in research makes the control of tritium releases generated by these activities particularly important in Canada. Releases are regulated and carefully monitored by the Canadian Nuclear Safety Commission (CNSC). Some special interest and citizen groups, however, claim that the scientific uncertainty regarding the effects of tritium on health and on the environment is such that regulation of the facilities releasing or using tritium may be inadequate. In response to these concerns, the CNSC asked its staff to initiate the 'Tritium Studies' project. As part of the project, the environmental fate of tritium and its health effects were studied through direct field measurements and the review of the latest scientific literature on the subject. The project made it possible to conclude that the tritium radiation protection measures and regulatory mechanisms are adequate in protecting the health and safety of Canadians. (authors)

  13. De Minimis waste impacts analysis methodology. IMPACTS - BRC user's guide and methodology for radioactive wastes below regulatory concern. Draft report for comment. Volume 2

    International Nuclear Information System (INIS)

    Forstom, J.M.; Goode, D.J.

    1986-07-01

    This report describes the methodology and computer program used by NRC to evaluate radiological impacts associated with petitions to have specific slightly contaminated radioactive waste streams designated as ''below regulatory concern.'' These wastes could be treated and disposed of at facilities which are not licensed for low-level radioactive waste management. The IMPACTS-BRC computer program is implemented on IBM-PC microcomputers using the FORTRAN programming language. Radiological impacts (doses) are estimated for several pathways including direct gamma radiation exposure, worker inhalation and exposure, offsite atmospheric and water releases, and intruder exposures. Annual impacts are calculated for the maximum individual, critical groups, and general population. The treatment and disposal options include onsite incineration, incineration at municipal and hazardous waste facilities, and disposal at sanitary landfills and hazardous waste landfills. Modifications to the program (from Volume 1) are primarily for microcomputer compatibility and to provide information needed to evaluate the petitions. Default environmental and facility parameters are developed representing conservative assumptions about site selection and operational procedures. In particular, the parameters of the groundwater pathway model are modified to represent more conservative assumptions than the original model (Volume 1)

  14. U.S. Nuclear Regulatory Commission Extremely Low Probability of Rupture pilot study : xLPR framework model user's guide.

    Energy Technology Data Exchange (ETDEWEB)

    Kalinich, Donald A.; Sallaberry, Cedric M.; Mattie, Patrick D.

    2010-12-01

    For the U.S. Nuclear Regulatory Commission (NRC) Extremely Low Probability of Rupture (xLPR) pilot study, Sandia National Laboratories (SNL) was tasked to develop and evaluate a probabilistic framework using a commercial software package for Version 1.0 of the xLPR Code. Version 1.0 of the xLPR code is focused assessing the probability of rupture due to primary water stress corrosion cracking in dissimilar metal welds in pressurizer surge nozzles. Future versions of this framework will expand the capabilities to other cracking mechanisms, and other piping systems for both pressurized water reactors and boiling water reactors. The goal of the pilot study project is to plan the xLPR framework transition from Version 1.0 to Version 2.0; hence the initial Version 1.0 framework and code development will be used to define the requirements for Version 2.0. The software documented in this report has been developed and tested solely for this purpose. This framework and demonstration problem will be used to evaluate the commercial software's capabilities and applicability for use in creating the final version of the xLPR framework. This report details the design, system requirements, and the steps necessary to use the commercial-code based xLPR framework developed by SNL.

  15. An introduction to a new IAEA safety guide: 'ageing management for nuclear power plants'

    International Nuclear Information System (INIS)

    Pachner, J.; Inagaki, T.; Kang, K.S.

    2008-01-01

    This paper reports on a new IAEA Safety Guide entitled 'Ageing Management for Nuclear Power Plants' which is currently in an advanced draft form, awaiting approval of publication. The new Safety Guide will be an umbrella document for a comprehensive set of guidance documents on ageing management which have been issued by the IAEA. The Safety Guide first presents basic concepts of ageing management as a common basis for the recommendations on: proactive management of ageing throughout the life cycle of a nuclear power plant (NPP); systematic approach to managing ageing in the operation of NPPs; managing obsolescence; and review of ageing management for long term operation (life extension). The Safety Guide is intended to assist operators in establishing, implementing and improving systematic ageing management programs in NPPs and may be used by regulators in preparing regulatory standards and guides, and in verifying that ageing in nuclear power plants is being effectively managed. (author)

  16. Development of a regulatory guide about the content and criteria for the elaboration of the radioactive waste management plans in Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Lopez de la Higuera, Julia; Alvarez Alonso, M. Angeles; Simon Cirujano, Maria I.; Suarez Llorente, Beatriz

    2008-01-01

    Full text:The Spanish legislation requires the licensees to develop, among other documents, a Radioactive Waste Management Plan (RWMP) as an official report in the application for the operation and for the dismantling and decommissioning of a nuclear facility. These Plans should describe the types of waste, inventory, characterization, treatment, conditioning and storage of wastes. The Spanish regulatory body, Consejo de Seguridad Nuclear (CSN), promoted a working group to analyze the content and scope of the RWMP, bringing together the electric power industry association (UNESA), the waste management organisation (ENRESA) and the nuclear fuel industry (ENUSA). The objective of the RWMP is to establish the criteria and instructions to ensure a safe and optimized management, taking into account the normative and technological developments. The Plan is based on support Studies that contain the basic information for the analysis of the waste management options and deals with: (1) Actual generation and management options in the facility; (2) Classification of the facility in waste generation zones; (3) Experience analysis and identification of potential management improvements; (4) Selection, justification and introduction of new management modes. The RWMP will develop the following issues: a) Waste generation and management (for each waste type, information in terms of the origin, physico-chemical and radiological properties, volume of production and implemented management routes); b) Classification of the facility in waste zones. The facility will differentiate those areas where contaminated or activated wastes can be produced (Radioactive Waste Zone - RWZ) or not (Conventional Waste Zone - CWZ). To avoid mixing and allow this separation, two lines of defense will be established. The first one is the classification and setting marks in the Zones and the second one the controls on the non-radioactive wastes at the exit of the facility: a) Selection of foreseen lines

  17. Nuclear regulatory regime in Lithuania

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

    The Law on Nuclear Energy establishes the legal basis for nuclear safety in the Republic of Lithuania. It assigns the responsibility for safety to the operating organization of a nuclear facility and outlines the tasks of the operator and the regulatory authority. According to this Law, the Nuclear Power Safety Inspectorate (VATESI) shall implement state regulation of nuclear safety. Standards and rules, guides and regulations of nuclear safety and radiation protection approved by the Government or by the institutions authorised. It is mandatory for all public and local authorities, enterprises, institutions, organisations, their associations, the officials and other persons whose activities are related to the operation of nuclear facilities, to the use and management of nuclear and radioactive materials therein. Safety guarantee in nuclear energy based on the requirements of the laws and regulations of the Republic of Lithuania, on the requirements of the international treaties to which the Republic of Lithuania is a party, also on the recommendations of the IAEA and other international organisations and authorities

  18. A study on the development of regulatory guide to stability conformation and classification criteria of low and intermediate level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Geon Jae; Paek, Min Hoon; Park, Jong Gil; Han, Byeong Seop; Cheong, Jae Hak; Lee, Hae Chan; Yang, Jin Yeong; Hong, Hei Kwan; Park, Jin Baek [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1994-01-15

    The objectives of this study are to examine basic principles and terms and to suggest and recommend definite methods and criteria necessary for the classification and stability conformation of radioactive wastes. In this study, following studies were performed : investigate the domestic regulations related with the stability conformation and classification of radioactive wastes in order to keep mutual relationship and consistency between the regulations, investigate the sources, types and characteristics of domestic radioactive wastes as a basis for this study, investigate the classification criteria and methods of others countries in a general point of view and in the view point of disposal method, select the classification criteria factors for the domestic case and general case in the both general and domestic points of view, investigate the general test items for the stability conformation of radioactive waste forms and analysis on the test items and criteria of others countries for the mined cavity disposal and shallow land disposal in the view point of disposal method, experimental leaching and immersion tests for the borate and spent resin wastes as a study on the stability conformation of waste forms, selection of acceptance criteria for the both of disposal methods in the domestic and general cases.

  19. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  20. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  1. Nuclear regulatory decision making

    International Nuclear Information System (INIS)

    2005-01-01

    The fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear utilities operate their plants at all times in an acceptably safe manner. In meeting this objective, the regulatory body should strive to ensure that its regulatory decisions are technically sound, consistent from case to case, and timely. In addition, the regulator must be aware that its decisions and the circumstances surrounding those decisions can affect how its stakeholders, such as government policy makers, the industry it regulates, and the public, view it as an effective and credible regulator. In order to maintain the confidence of those stakeholders, the regulator should make sure that its decisions are transparent, have a clear basis in law and regulations, and are seen by impartial observers to be fair to all parties. Based on the work of a Nuclear Energy Agency (NEA) expert group, this report discusses some of the basic principles and criteria that a regulatory body should consider in making decisions and describes the elements of an integrated framework for regulatory decision making. (author)

  2. Criticality Safety in the Handling of Fissile Material. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-05-15

    This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The guidance and recommendations are applicable to both regulatory bodies and operating organizations. The objectives of criticality safety are to prevent a self-sustained nuclear chain reaction and to minimize the consequences of this if it were to occur. The Safety Guide makes recommendations on how to ensure subcriticality in systems involving fissile materials during normal operation, anticipated operational occurrences, and, in the case of accident conditions, within design basis accidents, from initial design through commissioning, operation, and decommissioning and disposal.

  3. 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)

  4. Regulatory control of fuel design and manufacturing

    International Nuclear Information System (INIS)

    1994-01-01

    The regulatory control of the design and manufacturing of the nuclear fuel and of the control rods aims to ensure conformance to set requirements during normal operating conditions, anticipated operational transients and postulated accident conditions. The regulatory control of design, manufacturing, receiving inspections and the start of operation of the nuclear fuel are specified in the guide. The regulatory control procedure also applies to the control rods and the shield elements

  5. REPOSITORY RADIATION SHIELDING DESIGN GUIDE

    International Nuclear Information System (INIS)

    M. Haas; E.M. Fortsch

    1997-01-01

    The scope of this document includes radiation safety considerations used in the design of facilities for the Yucca Mountain Site Characterization Project (YMP). The purpose of the Repository Radiation Shielding Design Guide is to document the approach used in the radiological design of the Mined Geologic Disposal System (MGDS) surface and subsurface facilities for the protection of workers, the public, and the environment. This document is intended to ensure that a common methodology is used by all groups that may be involved with Radiological Design. This document will also assist in ensuring the long term survivability of the information basis used for radiological safety design and will assist in satisfying the documentation requirements of the licensing body, the Nuclear Regulatory Commission (NRC). This design guide provides referenceable information that is current and maintained under the YMP Quality Assurance (QA) Program. Furthermore, this approach is consistent with maintaining continuity in spite of a changing design environment. This approach also serves to ensure common inter-disciplinary interpretation and application of data

  6. REPOSITORY RADIATION SHIELDING DESIGN GUIDE

    Energy Technology Data Exchange (ETDEWEB)

    M. Haas; E.M. Fortsch

    1997-09-12

    The scope of this document includes radiation safety considerations used in the design of facilities for the Yucca Mountain Site Characterization Project (YMP). The purpose of the Repository Radiation Shielding Design Guide is to document the approach used in the radiological design of the Mined Geologic Disposal System (MGDS) surface and subsurface facilities for the protection of workers, the public, and the environment. This document is intended to ensure that a common methodology is used by all groups that may be involved with Radiological Design. This document will also assist in ensuring the long term survivability of the information basis used for radiological safety design and will assist in satisfying the documentation requirements of the licensing body, the Nuclear Regulatory Commission (NRC). This design guide provides referenceable information that is current and maintained under the YMP Quality Assurance (QA) Program. Furthermore, this approach is consistent with maintaining continuity in spite of a changing design environment. This approach also serves to ensure common inter-disciplinary interpretation and application of data.

  7. Guide to the economic regulation of the gas industry

    International Nuclear Information System (INIS)

    1999-12-01

    The guide provides: concise information on the institutional structure, legislation and licensing of the gas industry; a history of regulatory and commercial development in the industry; an examination of the current regulatory issues. (Author)

  8. Annual Report 2008. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2009-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2008. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  9. Annual Report 2007. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2008-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across tree parts and seven annexes the activities developed by the organism during 2007. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  10. Annual Report 2009. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2010-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2009. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the environmental monitoring; the occupational surveillance; the training and the public information; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  11. Regulatory Anatomy

    DEFF Research Database (Denmark)

    Hoeyer, Klaus

    2015-01-01

    This article proposes the term “safety logics” to understand attempts within the European Union (EU) to harmonize member state legislation to ensure a safe and stable supply of human biological material for transplants and transfusions. With safety logics, I refer to assemblages of discourses, le...... they arise. In short, I expose the regulatory anatomy of the policy landscape....

  12. Regulatory Governance

    DEFF Research Database (Denmark)

    Kjær, Poul F.; Vetterlein, Antje

    2018-01-01

    Regulatory governance frameworks have become essential building blocks of world society. From supply chains to the regimes surrounding international organizations, extensive governance frameworks have emerged which structure and channel a variety of social exchanges, including economic, political...... by the International Transitional Administrations (ITAs) in Kosovo and Iraq as well as global supply chains and their impact on the garment industry in Bangladesh....

  13. Comparative study of Malaysian and Philippine regulatory infrastructures on radiation and nuclear safety with international standards

    International Nuclear Information System (INIS)

    Cayabo, Lynette B.

    2013-06-01

    This study presents the results of the critical reviews, analysis, and comparison of the regulatory infrastructures for radiation and nuclear safety of Malaysis and the Philippines usi ng the IAEA safety requirements, GSR Part 1, G overnment, Legal and Regulatory Framework for Safety'' as the main basis and in part, the GSR Part 3, R adiation Protection and Safety of Radiation Sources: International Basic Safety Standards . The scope of the comparison includes the elements of the relevant legislations, the regulatory system and processes including the core functions of the regulatory body (authorization, review and assessment, inspection and enforcement, development of regulations and guides); and the staffing and training of regulatory body. The respective availabe data of the Malaysian and Philippine regulatory infrastructures and current practices were gathered and analyzed. Recommendations to fill the gaps and strengthen the existing regulatory infrastructure of each country was given using as bases relevant IAEA safety guides. Based on the analysis made, the main findings are: the legislations of both countries do not contain al the elements of teh national policy and strategy for safety as well as those of teh framework for safety in GR Part I. Among the provision that need to be included in the legislations are: emergency planning and response; decommissioning of facilities safe management of radioactive wastes and spent fuel; competence for safety; and technical sevices. Provisions on coordination of different authorities with safety responsibilities within the regulatory framework for safety as well as liaison with advisory bodies and support organizations need to be enhanced. The Philippines needs to establish an independent regulatory body, ie. separate from organizations charged with promotion of nuclear technologies and responsible for facilitiesand activities. Graded approach on the system of notification and authorization by registration and

  14. Management of the Regulatory Authority Information

    International Nuclear Information System (INIS)

    Suman, H.

    2003-01-01

    Safe Management of the Regulatory Authority Information is one of the essential elements to ensure the effectiveness of the regulatory program as a whole. This paper briefly describes the information management basis in RNRO, which is in charge of the regulatory authority tasks in Syria. SINA-2, a computational tool prepared in RNRO for managing the information related to the inventory of radiation sources and users, is also introduced

  15. Standard Guide for Specifying Thermal Performance of Geothermal Power Systems

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2000-01-01

    1.1 This guide covers power plant performance terms and criteria for use in evaluation and comparison of geothermal energy conversion and power generation systems. The special nature of these geothermal systems makes performance criteria commonly used to evaluate conventional fossil fuel-fired systems of limited value. This guide identifies the limitations of the less useful criteria and defines an equitable basis for measuring the quality of differing thermal cycles and plant equipment for geothermal resources. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  16. Regulatory aspects of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Kristensen, K.

    1985-01-01

    Regulatory systems in the field of radiopharmaceuticals have two main purposes: efficacy and safety. Efficacy expresses the quality of the diagnostic and therapeutic process for the patient. Safety involves the patient, the staff, and the environment. The world situation regarding regulations for radiopharmaceuticals is reviewed on the basis of a survey in WHO Member States. The main content of such regulations is discussed. The special properties of radiopharmaceuticals compared with ordinary drugs may call for modified regulations. Several countries are preparing such regulations. Close co-operation and good understanding among scientists working in hospital research, industry and regulatory bodies will be of great importance for the fast and safe introduction of new radiopharmaceuticals for the benefit of the patient. Before introducing new legislation in this field, a radiopharmaceutical expert should analyse the situation in the country and the relationship to the existing regulations. It is expected that the most important factor in promoting the fast introduction of new, safe and effective radiopharmaceuticals will be the training of people working within the regulatory bodies. It is foreseen that the IAEA and WHO will have an important role to play by providing expert advice and training in this area. (author)

  17. Manual on brachytherapy. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to brachytherapy: its application and procedures guides

  18. Strengthening Regulatory Competence in Pakistan

    International Nuclear Information System (INIS)

    Sadiq, M.

    2016-01-01

    Capacity building of Pakistan Nuclear Regulatory Authority is considered an essential element in pursuit of its vision to become a world class regulatory body. Since its inception in 2001, PNRA has continuously endeavoured to invest in its people, develop training infrastructure and impart sound knowledge and professional skills with the aim to improve its regulatory effectiveness. The use of nuclear and radioactive material in Pakistan has increased manifold in recent years, thus induction of more manpower was needed for regulatory oversight. PNRA adopted two pronged approach for meeting the manpower demand (a) employment of university graduates through fast track recruitment drive and (b) induction of graduates by offering fellowships for Master degree programs. Although, the newly employed staff was selected on the basis of their excellent academic qualifications in basic and applied sciences, but they required rigorous knowledge and skills in regulatory perspectives. In order to implement a structured training program, PNRA conducted Training Needs Assessment (TNA) and identified competency gaps of the regulatory staff in legal, technical, regulatory practice and behavioural domains. PNRA took several initiatives for capacity building which included establishment of a training centre for sustainability of trainings, initiation of a fellowship scheme for Master program, attachment of staff at local institutes for on-the-job training and placement at foreign regulatory bodies and organizations for technical development with the assistance of IAEA. The above strategies have been very beneficial in competence building of the PNRA staff to perform all regulatory activities indigenously for nuclear power plants, research reactors and radiation facilities. Provision of vibrant technical support to IAEA and Member States in various programs by PNRA is a landmark of these competence development efforts. This paper summarizes PNRA initiatives and the International Atomic

  19. National practices in physical protection of nuclear materials. Regulatory basis

    International Nuclear Information System (INIS)

    Goltsov, V.Y.

    2002-01-01

    Full text: The Federal law 'On The Use Of Atomic Energy' containing the section on physical protection of nuclear materials and nuclear facilities was issued in 1995 in Russian Federation. This document became the first federal level document regulating the general requirements to physical protection (PP). The federal PP rules developed on the base of this law by Minatom of Russia and other federal bodies of the Russian Federation were put in force by the government of Russia in 1997. The requirements of the convention on physical protection of nuclear materials (INFCIRC 274) and the modern IAEA recommendations (INFCIRC/225/Rev.4) are taken into account in the PP rules. Besides, while developing the PP rules the other countries' experience in this sphere has been studied and taken into account. The PP rules are action-obligatory for all juridical persons dealing with nuclear activity and also for those who are coordinating and monitoring this activity. Nuclear activity without physical protection ensured in accordance with PP rules requirements is prohibited. The requirements of PP Rules are stronger than the IAEA recommendations. The PP rules are establishing: physical protection objectives; federal executive bodies and organizations functions an implementation of physical protection; categorization of nuclear materials; requirements for nuclear materials physical protection as during use and storage as during transportation; main goals of state supervision and ministry level control for physical protection; notification order about the facts of unauthorized actions regarding nuclear materials and facilities. Besides the above mentioned documents, there were put in force president decrees, federal laws and regulations in the field of: counteraction to nuclear terrorism; interactions in physical protection systems; military and ministerial on-site guard activities; information protection. By the initiative of Minatom of Russia the corrections were put into the criminal code of Russian Federation regarding improper execution of duties on and theft of nuclear materials and equipment that could be used for weapons of mass destruction construction. Minatom of Russia is actively elaborating ministerial documents on physical protection. Since 1995 till 2001 there were developed and put in force 21 this topic related documents including the following: physical protection terminology; general approaches to physical protection ensuring; vulnerability analysis of nuclear-hazardous facilities; physical protection systems designing; organizing of safeguards and security services at nuclear-hazardous facilities; operation of automated physical protection systems; communication and data exchange in physical protection systems; certification of technical means of physical protection; physical protection system information protection; ministerial on-site guarding of nuclear-hazardous facilities; provision of ministerial control of physical protection condition; interaction of different entities participating physical protection at ministerial level. (author)

  20. The regulatory basis for site selection for radioactive buildings

    International Nuclear Information System (INIS)

    Sirag, N.M.

    2012-01-01

    The architectural bases and the design standard for radiation research buildings differ than other research building, that the nature of the used radioactive materials in the nature of the carried an work in the building will decide the planning in the design of the building, and we shall discus in this research what already had been reached of results about the architectural bases in the used standard in the used safe design of research building and establishing design standard, that archaistic rely upon when designing these project which have specific and special characters

  1. Regulatory pathways for vaccines for developing countries.

    Science.gov (United States)

    Milstien, Julie; Belgharbi, Lahouari

    2004-01-01

    Vaccines that are designed for use only in developing countries face regulatory hurdles that may restrict their use. There are two primary reasons for this: most regulatory authorities are set up to address regulation of products for use only within their jurisdictions and regulatory authorities in developing countries traditionally have been considered weak. Some options for regulatory pathways for such products have been identified: licensing in the country of manufacture, file review by the European Medicines Evaluation Agency on behalf of WHO, export to a country with a competent national regulatory authority (NRA) that could handle all regulatory functions for the developing country market, shared manufacturing and licensing in a developing country with competent manufacturing and regulatory capacity, and use of a contracted independent entity for global regulatory approval. These options have been evaluated on the basis of five criteria: assurance of all regulatory functions for the life of the product, appropriateness of epidemiological assessment, applicability to products no longer used in the domestic market of the manufacturing country, reduction of regulatory risk for the manufacturer, and existing rules and regulations for implementation. No one option satisfies all criteria. For all options, national infrastructures (including the underlying regulatory legislative framework, particularly to formulate and implement local evidence-based vaccine policy) must be developed. WHO has led work to develop this capacity with some success. The paper outlines additional areas of action required by the international community to assure development and use of vaccines needed for the developing world. PMID:15042235

  2. Regulatory difficulties in a developing country

    International Nuclear Information System (INIS)

    Jacobs, W.R. Jr.

    1978-01-01

    The regulatory agency assigned the task of regulating the initial entry into the field of nuclear power generation by a developing country has a very difficult job. Based on the authors' experience during the start-up and initial operation of Ko-Ri Unit I, the first power reactor in the Republic of Korea, observations on regulatory difficulties and recommendations for improved regulatory effectiveness are offered. The problem areas can be loosely grouped into three general categories: (1) Lack of adequate technical knowledge which is the basis for all effective regulation; (2) Difficulties with understanding and utilization of the required regulatory documentation; (3) Failure to establish the proper regulatory environment. Examples are cited from actual experience during the Ko-Ri Unit I start-up to demonstrate the impact that regulatory activities can have on a plant construction and testing programme. The problems encountered are not unique to developing countries but also exist in the United States of America. Recommendations are offered which should be beneficial to either newly formed regulatory agencies or agencies wishing to improve their abilities and effectiveness. These include: (1) Additional training of regulatory inspectors in plant operations; (2) Additional experience gained by participation in regulatory activities in other countries; (3) Increased attention given to regulatory documents, especially plant technical specifications; (4) Establishment of formal lines of communication between the utility and the regulatory agency; (5) Clear definition of regulatory responsibilities to avoid areas of overlapping jurisdiction; (6) Active participation by the regulatory staff very early in the project. It is hoped that these and other recommendations offered will greatly improve regulatory effectiveness and at the same time demonstrate that when the decision is made to 'go nuclear', a strong commitment must be made to develop and support a technically

  3. Assessment of compliance with regulatory requirements for a best estimate methodology for evaluation of ECCS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Un Chul; Jang, Jin Wook; Lim, Ho Gon; Jeong, Ik [Seoul National Univ., Seoul (Korea, Republic of); Sim, Suk Ku [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2000-03-15

    Best estimate methodology for evaluation of ECCS proposed by KEPCO(KREM) os using thermal-hydraulic best-estimate code and the topical report for the methodology is described that it meets the regulatory requirement of USNRC regulatory guide. In this research the assessment of compliance with regulatory guide. In this research the assessment of compliance with regulatory requirements for the methodology is performed. The state of licensing procedure of other countries and best-estimate evaluation methodologies of Europe is also investigated, The applicability of models and propriety of procedure of uncertainty analysis of KREM are appraised and compliance with USNRC regulatory guide is assessed.

  4. BWR NSSS design basis documentation

    International Nuclear Information System (INIS)

    Vij, R.S.; Bates, R.E.

    2004-01-01

    In 1985 an incident at Toledo Edison's Davis Besse plant caused the U.S. Nuclear Regulatory Commission (NRC) to re-evaluate the technical information that the utilities had readily available to support the design of their plants. The Design Basis programs, currently on going in most U.S. utilities, have been the nuclear industry's response to the needs identified by this re-evaluation. In order to understand the Design Basis programs which have been implemented by the U.S. nuclear utilities, it is necessary to understand the problem as it was perceived by the nuclear industry (the utilities, the original NSSS designers and the regulators) after the Davis-Besse incident, the subsequent programs undertaken by the industry under the leadership of INPO and NUMARC, the NRC's actions, and the overall evolution of the industry's vision in relation to this problem. This paper presents the history of the design basis efforts from the first recognition of the problem by the NRC after the Davis-Besse incident, describes the actions taken by the NRC, INPO, NUMARC, the U.S. utilities and the NSSS designers, and brings the problem statement up-to-date in relation to the vision presently held by the U.S. nuclear industry. It then presents a technical discussion to develop a detailed definition of design basis information to support the problem statement. The information originally supplied by the NSSS designers during the plant design and construction is discussed as well as its relationship to the previously defined design basis information. This section of the paper concludes by defining the additional information needed by nuclear utilities to satisfy the requirements developed from the problem statement. Having developed a definition of the additional information (i.e., information not originally supplied during design and construction) required to solve the design basis problem as it is presently perceived by the U.S. nuclear industry, the paper then discusses design basis

  5. Regulatory Physiology

    Science.gov (United States)

    Lane, Helen W.; Whitson, Peggy A.; Putcha, Lakshmi; Baker, Ellen; Smith, Scott M.; Stewart, Karen; Gretebeck, Randall; Nimmagudda, R. R.; Schoeller, Dale A.; Davis-Street, Janis

    1999-01-01

    As noted elsewhere in this report, a central goal of the Extended Duration Orbiter Medical Project (EDOMP) was to ensure that cardiovascular and muscle function were adequate to perform an emergency egress after 16 days of spaceflight. The goals of the Regulatory Physiology component of the EDOMP were to identify and subsequently ameliorate those biochemical and nutritional factors that deplete physiological reserves or increase risk for disease, and to facilitate the development of effective muscle, exercise, and cardiovascular countermeasures. The component investigations designed to meet these goals focused on biochemical and physiological aspects of nutrition and metabolism, the risk of renal (kidney) stone formation, gastrointestinal function, and sleep in space. Investigations involved both ground-based protocols to validate proposed methods and flight studies to test those methods. Two hardware tests were also completed.

  6. Regulatory Benchmarking

    DEFF Research Database (Denmark)

    Agrell, Per J.; Bogetoft, Peter

    2017-01-01

    Benchmarking methods, and in particular Data Envelopment Analysis (DEA), have become well-established and informative tools for economic regulation. DEA is now routinely used by European regulators to set reasonable revenue caps for energy transmission and distribution system operators. The appli......Benchmarking methods, and in particular Data Envelopment Analysis (DEA), have become well-established and informative tools for economic regulation. DEA is now routinely used by European regulators to set reasonable revenue caps for energy transmission and distribution system operators....... The application of bench-marking in regulation, however, requires specific steps in terms of data validation, model specification and outlier detection that are not systematically documented in open publications, leading to discussions about regulatory stability and economic feasibility of these techniques...

  7. Regulatory Benchmarking

    DEFF Research Database (Denmark)

    Agrell, Per J.; Bogetoft, Peter

    2017-01-01

    Benchmarking methods, and in particular Data Envelopment Analysis (DEA), have become well-established and informative tools for economic regulation. DEA is now routinely used by European regulators to set reasonable revenue caps for energy transmission and distribution system operators. The appli......Benchmarking methods, and in particular Data Envelopment Analysis (DEA), have become well-established and informative tools for economic regulation. DEA is now routinely used by European regulators to set reasonable revenue caps for energy transmission and distribution system operators....... The application of benchmarking in regulation, however, requires specific steps in terms of data validation, model specification and outlier detection that are not systematically documented in open publications, leading to discussions about regulatory stability and economic feasibility of these techniques...

  8. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

  9. RADTRAN 4: User guide

    International Nuclear Information System (INIS)

    Neuhauser, K.S.; Kanipe, F.L.

    1992-01-01

    RADTRAN 4 is used to evaluate radiological consequences of incident-free transportation, as well as the radiological risks from vehicular accidents occurring during transportation. This User Guide is Volume 3 in a series of four volume of the documentation of the RADTRAN 4 computer code for transportation risk analysis. The other three volumes are Volume 1, the Executive Summary; Volume 2, the Technical Manual; and Volume 4, the Programmer's Manual. The theoretical and calculational basis for the operations performed by RADTRAN 4 are discussed in Volume 2. Throughout this User Guide the reader will be referred to Volume 2 for detailed discussions of certain RADTRAN features. This User Guide supersedes the document ''RADTRAN III'' by Madsen et al. (1983). This RADTRAN 4 User Guide specifies and describes the required data, control inputs, input sequences, user options, program limitations, and other activities necessary for execution of the RADTRAN 4 computer code

  10. ENSI’s regulatory framework strategy

    International Nuclear Information System (INIS)

    2015-03-01

    This short brochure issued by the Swiss Federal Nuclear Safety Inspectorate ENSI defines the organisation’s regulatory framework strategy. Six guiding principles are declared and discussed: Comprehensive harmonisation with relevant international requirements, basing the regulatory framework on existing, tried-and-tested regulations, issuing of its own guidelines only when it is necessary to do so, guidelines to be drawn up transparently and with the involvement of all stakeholders and basing the level of detail of its regulatory framework on hazard potential and risk

  11. Annual Report 2010. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2010-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across six chapters and seven annexes the activities developed by the organism during 2010. The main topic are: institutional issues; regulatory guides and standards; argentinean nuclear regulatory system; quality assurance of the ARN; the institutional communications; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the safeguards and the physical protection; the environmental control; the institutional relations; the training and the public information. Also, this publication have annexes with the following content: the regulatory framework; regulatory documents; inspections to medical, industrial and training installations; measurement and evaluation of the drinking water of Ezeiza; international expert's report on the application of the international standards of radiological protection of the public in the zone of the Ezeiza Atomic Center; ethical code

  12. Annual Report 2011. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2011-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across six chapters and seven annexes the activities developed by the organism during 2011. The main topic are: institutional issues; regulatory guides and standards; argentinean nuclear regulatory system; quality assurance of the ARN; the institutional communications; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the safeguards and the physical protection; the environmental control; the institutional relations; the training and the public information. Also, this publication have annexes with the following content: the regulatory framework; regulatory documents; inspections to medical, industrial and training installations; measurement and evaluation of the drinking water of Ezeiza; international expert's report on the application of the international standards of radiological protection of the public in the zone of the Ezeiza Atomic Center; ethical code

  13. Structural Basis of Rap Phosphatase Inhibition by Phr Peptides

    Science.gov (United States)

    Gallego del Sol, Francisca; Marina, Alberto

    2013-01-01

    Two-component systems, composed of a sensor histidine kinase and an effector response regulator (RR), are the main signal transduction devices in bacteria. In Bacillus, the Rap protein family modulates complex signaling processes mediated by two-component systems, such as competence, sporulation, or biofilm formation, by inhibiting the RR components involved in these pathways. Despite the high degree of sequence homology, Rap proteins exert their activity by two completely different mechanisms of action: inducing RR dephosphorylation or blocking RR binding to its target promoter. However the regulatory mechanism involving Rap proteins is even more complex since Rap activity is antagonized by specific signaling peptides (Phr) through a mechanism that remains unknown at the molecular level. Using X-ray analyses, we determined the structure of RapF, the anti-activator of competence RR ComA, alone and in complex with its regulatory peptide PhrF. The structural and functional data presented herein reveal that peptide PhrF blocks the RapF-ComA interaction through an allosteric mechanism. PhrF accommodates in the C-terminal tetratricopeptide repeat domain of RapF by inducing its constriction, a conformational change propagated by a pronounced rotation to the N-terminal ComA-binding domain. This movement partially disrupts the ComA binding site by triggering the ComA disassociation, whose interaction with RapF is also sterically impaired in the PhrF-induced conformation of RapF. Sequence analyses of the Rap proteins, guided by the RapF-PhrF structure, unveil the molecular basis of Phr recognition and discrimination, allowing us to relax the Phr specificity of RapF by a single residue change. PMID:23526880

  14. 78 FR 40776 - Issuance of Regulatory Guide 1.124 and Regulatory Guide 1.130

    Science.gov (United States)

    2013-07-08

    ... constitute backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise inconsistent with... the availability of information regarding these documents. You may access information related to these... section of this document. NRC's Agencywide Documents Access and Management System (ADAMS): You may access...

  15. 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

  16. The Regulatory Independence of FANR

    International Nuclear Information System (INIS)

    ALNuaimi, Fatema; Choi, Kwang Shik

    2012-01-01

    Regulatory independence is meant to provide a conservative system of policy making in order to comply with the problems that are forecasted upon the basis of assumptions. The Federal Authorization of Nuclear Regulation (FANR) is a regulatory commission that was formed to be regulatory body that governs the generation of nuclear power in United Arab Emirates. It was established under the UAE nuclear law (9/2009) as an independent regulatory body that was tasked with the regulation of all nuclear activities in the United Arab Emirates. As an independent body, FANR was tasked with ensuring that the regulation of the nuclear sector is done in effective and transparent manner to ensure its accountability to the people. Being independent, the regulatory body develops national nuclear regulations based on laid down safety standards by the International Atomic Energy Agency, ensuring that they are based on scientific and proven technologies The role of FANR is to ensure that the all corporations that undertake nuclear activities follow the laid down procedures and objectives and ensure safety measures are taken keenly to ensure the safety of the workers and the general public while at the same time ensuring the environment is free from nuclear radiations

  17. The Regulatory Independence of FANR

    Energy Technology Data Exchange (ETDEWEB)

    ALNuaimi, Fatema; Choi, Kwang Shik [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-05-15

    Regulatory independence is meant to provide a conservative system of policy making in order to comply with the problems that are forecasted upon the basis of assumptions. The Federal Authorization of Nuclear Regulation (FANR) is a regulatory commission that was formed to be regulatory body that governs the generation of nuclear power in United Arab Emirates. It was established under the UAE nuclear law (9/2009) as an independent regulatory body that was tasked with the regulation of all nuclear activities in the United Arab Emirates. As an independent body, FANR was tasked with ensuring that the regulation of the nuclear sector is done in effective and transparent manner to ensure its accountability to the people. Being independent, the regulatory body develops national nuclear regulations based on laid down safety standards by the International Atomic Energy Agency, ensuring that they are based on scientific and proven technologies The role of FANR is to ensure that the all corporations that undertake nuclear activities follow the laid down procedures and objectives and ensure safety measures are taken keenly to ensure the safety of the workers and the general public while at the same time ensuring the environment is free from nuclear radiations

  18. Safety Basis Report

    International Nuclear Information System (INIS)

    R.J. Garrett

    2002-01-01

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities

  19. Safety Basis Report

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2002-01-14

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

  20. 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

  1. Regulatory framework for nuclear power plant operation

    International Nuclear Information System (INIS)

    Perez Alcaniz, T.; Esteban Barriendos, M.

    1995-01-01

    As the framework of standards and requirements covering each phase of nuclear power plant project and operation developed, plant owners defined their licensing commitments (codes, rules and design requirements) during the project and construction phase before start-up and incorporated regulatory requirements imposed by the regulatory Body during the licensing process prior to operation. This produces a regulatory framework for operating a plant. It includes the Licensing Basis, which is the starting point for analyzing and incorporating new requirements, and for re-evaluation of existing ones. This presentation focuses on the problems of applying this regulatory framework to new operating activities, in particular to new projects, analyzing new requirements, and reconsidering existing ones. Clearly establishing a plant's licensing basis allows all organizations involved in plant operation to apply the requirements in a more rational way. (Author)

  2. Regulatory control of nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    The purpose of this book is to support IAEA training courses and workshops in the field of regulatory control of nuclear power plants as well as to support the regulatory bodies of Member States in their own training activities. The target group is the professional staff members of nuclear safety regulatory bodies supervising nuclear power plants and having duties and responsibilities in the following regulatory fields: regulatory framework; regulatory organization; regulatory guidance; licensing and licensing documents; assessment of safety; and regulatory inspection and enforcement. Important topics such as regulatory competence and quality of regulatory work as well as emergency preparedness and public communication are also covered. The book also presents the key issues of nuclear safety such as 'defence-in-depth' and safety culture and explains how these should be taken into account in regulatory work, e.g. during safety assessment and regulatory inspection. The book also reflects how nuclear safety has been developed during the years on the basis of operating experience feedback and results of safety research by giving topical examples. The examples cover development of operating procedures and accident management to cope with complicated incidents and severe accidents to stress the importance of regulatory role in nuclear safety research. The main target group is new staff members of regulatory bodies, but the book also offers good examples for more experienced inspectors to be used as comparison and discussion basis in internal workshops organized by the regulatory bodies for refreshing and continuing training. The book was originally compiled on the basis of presentations provided during the two regulatory control training courses in 1997 and 1998. The textbook was reviewed at the beginning of the years 2000 and 2002 by IAEA staff members and consistency with the latest revisions of safety standards have been ensured. The textbook was completed in the

  3. Radioactive Waste Management BasisApril 2006

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  4. Federal and state regulatory requirements for decontamination and decommissioning at US Department of Energy Oak Ridge Operations Facilities

    International Nuclear Information System (INIS)

    Etnier, E.L.; Houlberg, L.M.; Bock, R.E.

    1994-06-01

    The purpose of this report is to address regulatory requirements for decontamination and decommissioning (D and D) activities at the Oak Ridge Reservation and Paducah Gaseous Diffusion Plant. This report is a summary of potential federal and state regulatory requirements applicable to general D and D activities. Excerpts are presented in the text and tables from the complete set of regulatory requirements. This report should be used as a guide to the major regulatory issues related to D and D. Compliance with other federal, state, and local regulations not addressed here may be required and should be addressed carefully by project management on a site-specific basis. The report summarizes the major acts and implementing regulations (e.g., Resource and Conservation Recovery Act, Clean Air Act, and Toxic Substances Control Act) only with regard to D and D activities. Additional regulatory drivers for D and D activities may be established through negotiated agreements, such as the Federal Facility Agreement and the US Environmental Protection Agency Mixed Waste Federal Facility Compliance Agreement; these are discussed in this report. The DOE orders and Energy Systems procedures also are summarized briefly in instances where they directly apply to D and D

  5. Regulatory guidance for license renewal

    International Nuclear Information System (INIS)

    Thoma, John A.

    1991-01-01

    The proposed 10 CFR Part 54 rule proceduralizes the process for license renewal by identifying both the administrative and technical requirements for a renewal application. To amplify and support this regulation, written guidance has been provided in the form of a draft Regulatory Guide (DG 1009) and a draft Standard Review Plan for License Renewal (NUREG 1299). This guidance is scheduled to be finalized in 1992. Similar guidance will be provided for the proposed revisions to 10 CFR Part 51 concerning the environmental aspects of license renewal. (author)

  6. Advances in Canadian regulatory practice

    International Nuclear Information System (INIS)

    Waddington, J.G.

    1993-03-01

    The new General Amendments to the Regulations, new recommendations on dose limits, developments in techniques and safety thinking, and aging of plant are all contributing to the need for a significant number of new regulatory document on a wide range of topics. this paper highlights a number of initiatives taken in response to these pressures, giving a brief background to the initiative and, where possible, outlining some of the ideas in the document licensing guides on new dose limits, dosimetry, safety analysis, reliability, fault tree analysis, reporting requirements, human factors, software, the ALARA principle, backfitting and the licensing process. (Author) 29 refs., fig., 4 tabs

  7. Views from the japanese regulatory authority

    International Nuclear Information System (INIS)

    Aoyama, S.

    2004-01-01

    The legislation system for regulation of radioisotope in Japan was established in 1957. The system has been revised gradually since its establishment. Major amendments of the law were made in 1988 on the basis of ICRP Publication 26 and in 2000 on the basis of Publication 60. Main principles provided in the publication have been already introduced into the law. However, some concepts proposed in the recommendations are still under discussion. The current status of implementation of the ICRP recommendations in the Japanese regulatory system is summarised. Views from the regulatory authority of Japan on the points to be improved in the current system of radiological protection are presented. (author)

  8. Regulatory systems-based licensing guidance documentation

    International Nuclear Information System (INIS)

    Delligatti, M.S.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

  9. As to achieve regulatory action, regulatory approaches

    International Nuclear Information System (INIS)

    Cid, R.; Encinas, D.

    2014-01-01

    The achievement of the effectiveness in the performance of a nuclear regulatory body has been a permanent challenge in the recent history of nuclear regulation. In the post-Fukushima era this challenge is even more important. This article addresses the subject from two complementary points of view: the characteristics of an effective regulatory body and the regulatory approaches. This work is based on the most recent studies carried out by the Committee on Nuclear Regulatory Activities, CNRA (OECD/NEA), as well as on the experience of the Consejo de Seguridad Nuclear, CSN, the Spanish regulatory body. Rafael Cid is the representative of CSN in these project: Diego Encinas has participated in the study on regulatory approaches. (Author)

  10. Theoretical basis for dosimetry

    International Nuclear Information System (INIS)

    Carlsson, G.A.

    1985-01-01

    Radiation dosimetry is fundamental to all fields of science dealing with radiation effects and is concerned with problems which are often intricate as hinted above. A firm scientific basis is needed to face increasing demands on accurate dosimetry. This chapter is an attempt to review and to elucidate the elements for such a basis. Quantities suitable for radiation dosimetry have been defined in the unique work to coordinate radiation terminology and usage by the International Commission on Radiation Units and Measurements, ICRU. Basic definitions and terminology used in this chapter conform with the recent ''Radiation Quantities and Units, Report 33'' of the ICRU

  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. From BASIS to MIRACLES

    DEFF Research Database (Denmark)

    Tsapatsaris, Nikolaos; Willendrup, Peter Kjær; E. Lechner, Ruep

    2015-01-01

    Results based on virtual instrument models for the first high-flux, high-resolution, spallation based, backscattering spectrometer, BASIS are presented in this paper. These were verified using the Monte Carlo instrument simulation packages McStas and VITESS. Excellent agreement of the neutron count...... are pivotal to the conceptual design of the next generation backscattering spectrometer, MIRACLES at the European Spallation Source....

  13. Communication Regulatory Science: Mapping a New Field.

    Science.gov (United States)

    Noar, Seth M; Cappella, Joseph N; Price, Simani

    2017-12-13

    Communication regulatory science is an emerging field that uses validated techniques, tools, and models to inform regulatory actions that promote optimal communication outcomes and benefit the public. In the opening article to this special issue on communication and tobacco regulatory science, we 1) describe Food and Drug Administration (FDA) regulation of tobacco products in the US; 2) introduce communication regulatory science and provide examples in the tobacco regulatory science realm; and 3) describe the special issue process and final set of articles. Communication research on tobacco regulatory science is a burgeoning area of inquiry, and this work advances communication science, informs and potentially guides the FDA, and may help to withstand legal challenges brought by the tobacco industry. This research has the potential to have a major impact on the tobacco epidemic and population health by helping implement the most effective communications to prevent tobacco initiation and increase cessation. This special issue provides an example of 10 studies that exemplify tobacco regulatory science and demonstrate how the health communication field can affect regulation and benefit public health.

  14. Neural basis of decision making guided by emotional outcomes

    OpenAIRE

    Katahira, Kentaro; Matsuda, Yoshi-Taka; Fujimura, Tomomi; Ueno, Kenichi; Asamizuya, Takeshi; Suzuki, Chisato; Cheng, Kang; Okanoya, Kazuo; Okada, Masato

    2015-01-01

    Emotional events resulting from a choice influence an individual's subsequent decision making. Although the relationship between emotion and decision making has been widely discussed, previous studies have mainly investigated decision outcomes that can easily be mapped to reward and punishment, including monetary gain/loss, gustatory stimuli, and pain. These studies regard emotion as a modulator of decision making that can be made rationally in the absence of emotions. In our daily lives, how...

  15. The path from biomarker discovery to regulatory qualification

    CERN Document Server

    Goodsaid, Federico

    2013-01-01

    The Path from Biomarker Discovery to Regulatory Qualification is a unique guide that focuses on biomarker qualification, its history and current regulatory settings in both the US and abroad. This multi-contributed book provides a detailed look at the next step to developing biomarkers for clinical use and covers overall concepts, challenges, strategies and solutions based on the experiences of regulatory authorities and scientists. Members of the regulatory, pharmaceutical and biomarker development communities will benefit the most from using this book-it is a complete and practical guide to biomarker qualification, providing valuable insight to an ever-evolving and important area of regulatory science. For complimentary access to chapter 13, 'Classic' Biomarkers of Liver Injury, by John R. Senior, Associate Director for Science, Food and Drug Administration, Silver Spring, Maryland, USA, please visit the following site:  http://tinyurl.com/ClassicBiomarkers Contains a collection of experiences of different...

  16. Establishing 'design basis threat' in Norway

    International Nuclear Information System (INIS)

    Maerli, M.B.; Naadland, E.; Reistad, O.

    2002-01-01

    Full text: INFCIRC 225 (Rev. 4) assumes that a state's physical protection system should be based on the state's evaluation of the threat, and that this should be reflected in the relevant legislation. Other factors should also be considered, including the state's emergency response capabilities and the existing and relevant measures of the state's system of accounting for and control of nuclear material. A design basis threat developed from an evaluation by the state of the threat of unauthorized removal of nuclear material and of sabotage of nuclear material and nuclear facilities is an essential element of a state's system of physical protection. The state should continuously review the threat, and evaluate the implications of any changes in that threat for the required levels and the methods of physical protection. As part of a national design basis threat assessment, this paper evaluates the risk of nuclear or radiological terrorism and sabotage in Norway. Possible scenarios are presented and plausible consequences are discussed with a view to characterize the risks. The need for more stringent regulatory requirements will be discussed, together with the (positive) impact of improved systems and procedures of physical protection on nuclear emergency planning. Special emphasis is placed on discussing the design basis threat for different scenarios in order to systemize regulatory efforts to update the current legislation, requirement for operators' contingency planning, response efforts and the need for emergency exercises. (author)

  17. Regulations and guides for nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    The purpose of the present Guide is to provide information, guidance and recommendations to assist the regulatory body of a Member State in establishing its own regulations and guides. It discusses the purpose, the method and procedure of establishment, and the content and legal status of these documents, and it explains how to use the Codes of Practice and Safety Guides issued by the IAEA under the Nuclear Safety Standards (NUSS) programme. Certain aspects of how to use other international standards and appropriate regulations and guides from other countries are discussed

  18. Guided labworks

    DEFF Research Database (Denmark)

    Jacobsen, Lærke Bang

    For the last 40 years physics education research has shown poor learning outcomes of guided labs. Still this is found to be a very used teaching method in the upper secodary schools. This study explains the teacher's choice of guided labs throught the concept of redesign as obstacle dislodgement...

  19. Probabilistic safety analysis procedures guide

    International Nuclear Information System (INIS)

    Papazoglou, I.A.; Bari, R.A.; Buslik, A.J.

    1984-01-01

    A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of tissues affecting reactor safety. This guide addresses the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant and from loss of offsite electric power. The scope includes analyses of problem-solving (cognitive) human errors, a determination of importance of the various core damage accident sequences, and an explicit treatment and display of uncertainties for the key accident sequences. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance) and the risk associated with external accident initiators, as consensus is developed regarding suitable methodologies in these areas. This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are essential for regulatory decision making. Methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study

  20. Packaging supplier inspection guide

    International Nuclear Information System (INIS)

    Stromberg, H.M.; Gregg, R.E.; Kido, C.; Boyle, C.D.

    1991-05-01

    This is document is a guide for conducting quality assurance inspections of transportations packaging suppliers, where suppliers are defined as designers, fabricators, distributors, users, or owners of transportation packaging. This document can be used during an inspection to determine regulatory compliance within the requirements of 10 Code of Federal Regulations, Part 71, Subpart H (10 CFR 71.101--71.135). The guidance described in this document provides a framework for an inspection. It provides the inspector with the flexibility to adapt the methods and concepts presented here to meet the needs of the particular facility being inspected. The guide was developed to ensure a structured and consistent approach for inspections. The method treats each activity at a supplier facility as a separate entity (or functional element), and combines the activities within the framework of an ''inspection tree.'' The method separates each functional element into several areas of performance and then identifies guidelines, based on regulatory requirements, to be used to qualitatively rate each area. This document was developed to serve as a field manual to facilitate the work of inspectors. 1 ref., 1 fig., 5 tabs

  1. 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

  2. Dynamical basis set

    International Nuclear Information System (INIS)

    Blanco, M.; Heller, E.J.

    1985-01-01

    A new Cartesian basis set is defined that is suitable for the representation of molecular vibration-rotation bound states. The Cartesian basis functions are superpositions of semiclassical states generated through the use of classical trajectories that conform to the intrinsic dynamics of the molecule. Although semiclassical input is employed, the method becomes ab initio through the standard matrix diagonalization variational method. Special attention is given to classical-quantum correspondences for angular momentum. In particular, it is shown that the use of semiclassical information preferentially leads to angular momentum eigenstates with magnetic quantum number Vertical BarMVertical Bar equal to the total angular momentum J. The present method offers a reliable technique for representing highly excited vibrational-rotational states where perturbation techniques are no longer applicable

  3. Design basis 2

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, G.; Soerensen, P. [Risoe National Lab., Roskilde (Denmark)

    1996-09-01

    Design Basis Program 2 (DBP2) is comprehensive fully coupled code which has the capability to operate in the time domain as well as in the frequency domain. The code was developed during the period 1991-93 and succeed Design Basis 1, which is a one-blade model presuming stiff tower, transmission system and hub. The package is designed for use on a personal computer and offers a user-friendly environment based on menu-driven editing and control facilities, and with graphics used extensively for the data presentation. Moreover in-data as well as results are dumped on files in Ascii-format. The input data is organized in a in-data base with a structure that easily allows for arbitrary combinations of defined structural components and load cases. (au)

  4. Help guide for the application of regulatory requirements on the transport of radioactive material; Guia de ayuda para la aplicacion de requisitos reglementarios sobr el transporte de material radiactivo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Rodriguez, S.; Acena Moreno, V.; Zamora Martin, F.; Rubio de Juan, E.

    2011-07-01

    The regulation of transport of radioactive material by road in Spain refers to compliance with the requirements of the European Agreement concerning the International Carriage of Dangerous Goods by Road (ADR) in force. The structure presented by this legislation, which is international, and the inclusion in it of requirements that apply to other dangerous goods makes it difficult to consult the requirements that specifically apply to the transport of radioactive material. Therefore, the Nuclear Safety Council (CSN) has found it necessary to publish a guide that facilitates users to comply with its provisions and, consequently, this transport security.

  5. Radiation Safety of Gamma, Electron and X Ray Irradiation Facilities. Specific Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    The objective of this Safety Guide is to provide recommendations on how to meet the requirements of the BSS with regard to irradiation facilities. This Safety Guide provides specific, practical recommendations on the safe design and operation of gamma, electron and X ray irradiators for use by operating organizations and the designers of these facilities, and by regulatory bodies. SCOPE. The facilities considered in this publication include five types of irradiator, whether operated on a commercial basis or for research and development purposes. This publication is concerned with radiation safety issues and not with the uses of irradiators, nor does it cover the irradiation of product or its quality management. The five types of irradiator are: - Panoramic dry source storage irradiators; - Underwater irradiators, in which both the source and the product being irradiated are under water; - Panoramic wet source storage irradiators; - Electron beam irradiation facilities, in which irradiation is performed in an area that is potentially accessible to personnel, but that is kept inaccessible during the irradiation process; - X ray irradiation facilities, in which irradiation is performed in an area that is potentially accessible to personnel, but that is kept inaccessible during the irradiation process. Consideration of non-radiation-related risks and of the benefits resulting from the operation of irradiators is outside the scope of this Safety Guide. The practices of radiotherapy and radiography are also outside the scope of this Safety Guide. Category I gamma irradiators (i.e. 'self-shielded' irradiators) are outside the scope of this Safety Guide

  6. Impact of regulatory science on global public health

    OpenAIRE

    Meghal Patel; Margaret Ann Miller

    2012-01-01

    Regulatory science plays a vital role in protecting and promoting global public health by providing the scientific basis for ensuring that food and medical products are safe, properly labeled, and effective. Regulatory science research was first developed for the determination of product safety in the early part of the 20th Century, and continues to support innovation of the processes needed for regulatory policy decisions. Historically, public health laws and regulations were enacted followi...

  7. Information resources in state regulatory agencies-a California perspective

    Energy Technology Data Exchange (ETDEWEB)

    DiZio, S.M. [California Environmental Protection Agency, Sacramento (United States)

    1990-12-31

    Various state regulatory agencies have expressed a need for networking with information gatherers/researchers to produce a concise compilation of primary information so that the basis for regulatory standards can be scientifically referenced. California has instituted several programs to retrieve primary information, generate primary information through research, and generate unique regulatory standards by integrating the primary literature and the products of research. This paper describes these programs.

  8. HBR guides

    CERN Document Server

    Duarte, Nancy; Dillon, Karen

    2015-01-01

    Master your most pressing professional challenges with this seven-volume set that collects the smartest best practices from leading experts all in one place. "HBR Guide to Better Business Writing" and "HBR Guide to Persuasive Presentations" help you perfect your communication skills; "HBR Guide to Managing Up and Across" and "HBR Guide to Office Politics" show you how to build the best professional relationships; "HBR Guide to Finance Basics for Managers" is the one book you'll ever need to teach you about the numbers; "HBR Guide to Project Management" addresses tough questions such as how to manage stakeholder expectations and how to manage uncertainty in a complex project; and "HBR Guide to Getting the Right Work Done" goes beyond basic productivity tips to teach you how to prioritize and focus on your work. This specially priced set of the most popular books in the series makes a perfect gift for aspiring leaders looking for trusted advice. Arm yourself with the advice you need to succeed on the job, from ...

  9. Professional and Regulatory Search

    Science.gov (United States)

    Professional and Regulatory search are designed for people who use EPA web resources to do their job. You will be searching collections where information that is not relevant to Environmental and Regulatory professionals.

  10. 78 FR 19057 - Self-Regulatory Organizations; ICE Clear Europe Limited; Notice of Filing Proposed Rule Changes...

    Science.gov (United States)

    2013-03-28

    ... categories. II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the... by ICEEU. A. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the.... 78q-1(b)(3)(F). B. Self-Regulatory Organization's Statement on Burden on Competition ICE Clear Europe...

  11. Transportation and packaging resource guide

    International Nuclear Information System (INIS)

    Arendt, J.W.; Gove, R.M.; Welch, M.J.

    1994-12-01

    The purpose of this resource guide is to provide a convenient reference document of information that may be useful to the U.S. Department of Energy (DOE) and DOE contractor personnel involved in packaging and transportation activities. An attempt has been made to present the terminology of DOE community usage as it currently exists. DOE's mission is changing with emphasis on environmental cleanup. The terminology or nomenclature that has resulted from this expanded mission is included for the packaging and transportation user for reference purposes. Older terms still in use during the transition have been maintained. The Packaging and Transportation Resource Guide consists of four sections: Sect. 1, Introduction; Sect. 2, Abbreviations and Acronyms; Sect. 3, Definitions; and Sect. 4, References for packaging and transportation of hazardous materials and related activities, and Appendices A and B. Information has been collected from DOE Orders and DOE documents; U.S Department of Transportation (DOT), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) regulations; and International Atomic Energy Agency (IAEA) standards and other international documents. The definitions included in this guide may not always be a regulatory definition but are the more common DOE usage. In addition, the definitions vary among regulatory agencies. It is, therefore, suggested that if a definition is to be used in a regulatory or a legal compliance issue, the definition should be verified with the appropriate regulation. To assist in locating definitions in the regulations, a listing of all definition sections in the regulations are included in Appendix B. In many instances, the appropriate regulatory reference is indicated in the right-hand margin

  12. Transportation and packaging resource guide

    Energy Technology Data Exchange (ETDEWEB)

    Arendt, J.W.; Gove, R.M.; Welch, M.J.

    1994-12-01

    The purpose of this resource guide is to provide a convenient reference document of information that may be useful to the U.S. Department of Energy (DOE) and DOE contractor personnel involved in packaging and transportation activities. An attempt has been made to present the terminology of DOE community usage as it currently exists. DOE`s mission is changing with emphasis on environmental cleanup. The terminology or nomenclature that has resulted from this expanded mission is included for the packaging and transportation user for reference purposes. Older terms still in use during the transition have been maintained. The Packaging and Transportation Resource Guide consists of four sections: Sect. 1, Introduction; Sect. 2, Abbreviations and Acronyms; Sect. 3, Definitions; and Sect. 4, References for packaging and transportation of hazardous materials and related activities, and Appendices A and B. Information has been collected from DOE Orders and DOE documents; U.S Department of Transportation (DOT), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) regulations; and International Atomic Energy Agency (IAEA) standards and other international documents. The definitions included in this guide may not always be a regulatory definition but are the more common DOE usage. In addition, the definitions vary among regulatory agencies. It is, therefore, suggested that if a definition is to be used in a regulatory or a legal compliance issue, the definition should be verified with the appropriate regulation. To assist in locating definitions in the regulations, a listing of all definition sections in the regulations are included in Appendix B. In many instances, the appropriate regulatory reference is indicated in the right-hand margin.

  13. Future nuclear regulatory challenges

    International Nuclear Information System (INIS)

    Royen, J.

    1998-01-01

    In December 1996, the NEA Committee on Nuclear Regulatory Activities concluded that changes resulting from economic deregulation and other recent developments affecting nuclear power programmes have consequences both for licensees and regulatory authorities. A number of potential problems and issues which will present a challenge to nuclear regulatory bodies over the next ten years have been identified in a report just released. (author)

  14. Regulatory document R-104, Regulatory objectives, requirements and guidelines for the disposal of radioactive wastes - long-term aspects

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose and scope of this document is to present the regulatory basis for judging the long-term acceptability of radioactive waste disposal options. The basic objectives of radioactive waste disposal are given as are the regulatory requirements to be satisfied. (NEA)

  15. Medication Guide

    Science.gov (United States)

    ... Size Small Text Medium Text Large Text Contrast Dark on Light Light on Dark Donate Search Menu Donate What is Glaucoma? Care ... Low Vision Resources Medication Guide Resources on the Web » See All Articles Where the Money Goes Have ...

  16. Global Social Media Directory: A Resource Guide

    Energy Technology Data Exchange (ETDEWEB)

    Noonan, Christine F.; Piatt, Andrew W.

    2014-10-23

    The Global Social Media Directory is a resource guide providing information on social networking services around the globe. This information changes rapidly, therefore, this document will be updated on a regular basis and as funding permits.

  17. Assessment guide for tornado effect on Nuclear Power Plants (draft) with its commentaries

    International Nuclear Information System (INIS)

    Inoue, Hiroto; Fukunishi, Shiro; Suzuki, Tetsuo

    2013-10-01

    In the context of a severe accident at the Fukushima Daiichi Nuclear Power Station (NPS) operated by the Tokyo Electric Power Company (TEPCO) due to the 2011 off the Pacific coast of Tohoku Earthquake and Tsunami, Nuclear Regulation Authority (NRA) was established on September 19, 2012 under the relevant law. After that NRA organized a task force for studying new regulatory standards for nuclear power plants (NPPs) in consideration of lessons learned from the severe accident at Fukushima. In the task force open meeting, through discussing about design basis external natural events which should be considered in the new regulatory standards, tornado was newly introduced into new regulatory standards as an external natural event. Based on the decision that tornado was newly introduced into new regulatory standards, the Secretariat of the Nuclear Regulation Authority (SNRA) commissioned the Japan Nuclear Energy Safety Organization (JNES) to study an assessment guide for tornado effect on NPPs intended to be used for an official safety review for a NPP construction. JNES organized Sectional Committee for Tornado Effect Assessment Guide consisting of experts in meteorology and wind engineering fields, discussing about assessment methods for tornado effect on NPPs, draft version of the assessment guide for tornado effect on NPPs was completed on April 4, 2013, and JNES submitted the draft guide to SNRA on the same date. After that NRA called for public comments for the draft version of the assessment guide, the draft version of the assessment guide was partly amended taking posted public comments account, and tornado effect assessment guide was officially released on June 19, 2013. Contents in this paper are as follows, assessment guide for tornado effect on NPPs (Draft version on April 4, 2013), supplementary documents, calculation examples, and future tasks for further improved reliability of tornado effect assessment on NPPs. This draft guide consists of six chapters

  18. Assessment guide for tornado effect on Nuclear Power Plants (draft) with its commentaries

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, Hiroto; Fukunishi, Shiro; Suzuki, Tetsuo [Japan Nuclear Energy Safety Organization, Seismic Safety Department, Tokyo (Japan)

    2013-10-15

    In the context of a severe accident at the Fukushima Daiichi Nuclear Power Station (NPS) operated by the Tokyo Electric Power Company (TEPCO) due to the 2011 off the Pacific coast of Tohoku Earthquake and Tsunami, Nuclear Regulation Authority (NRA) was established on September 19, 2012 under the relevant law. After that NRA organized a task force for studying new regulatory standards for nuclear power plants (NPPs) in consideration of lessons learned from the severe accident at Fukushima. In the task force open meeting, through discussing about design basis external natural events which should be considered in the new regulatory standards, tornado was newly introduced into new regulatory standards as an external natural event. Based on the decision that tornado was newly introduced into new regulatory standards, the Secretariat of the Nuclear Regulation Authority (SNRA) commissioned the Japan Nuclear Energy Safety Organization (JNES) to study an assessment guide for tornado effect on NPPs intended to be used for an official safety review for a NPP construction. JNES organized Sectional Committee for Tornado Effect Assessment Guide consisting of experts in meteorology and wind engineering fields, discussing about assessment methods for tornado effect on NPPs, draft version of the assessment guide for tornado effect on NPPs was completed on April 4, 2013, and JNES submitted the draft guide to SNRA on the same date. After that NRA called for public comments for the draft version of the assessment guide, the draft version of the assessment guide was partly amended taking posted public comments account, and tornado effect assessment guide was officially released on June 19, 2013. Contents in this paper are as follows, assessment guide for tornado effect on NPPs (Draft version on April 4, 2013), supplementary documents, calculation examples, and future tasks for further improved reliability of tornado effect assessment on NPPs. This draft guide consists of six chapters

  19. Regulatory activities; Actividades regulatorias

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This publication, compiled in 8 chapters, presents the regulatory system developed by the Nuclear Regulatory Authority (NRA) of the Argentine Republic. The following activities and developed topics in this document describe: the evolution of the nuclear regulatory activity in Argentina; the Argentine regulatory system; the nuclear regulatory laws and standards; the inspection and safeguards of nuclear facilities; the emergency systems; the environmental systems; the environmental monitoring; the analysis laboratories on physical and biological dosimetry, prenatal irradiation, internal irradiation, radiation measurements, detection techniques on nuclear testing, medical program on radiation protection; the institutional relations with national and international organization; the training courses and meeting; the technical information.

  20. Radioactive Waste Management BasisSept 2001

    International Nuclear Information System (INIS)

    Goodwin, S.S.

    2011-01-01

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  1. Study on risk factors of PWR accidents beyond design basis

    International Nuclear Information System (INIS)

    Ahn, Seung Hoon; Nah, W. J.; Bang, Y. S.; Oh, D. Y.; Oh, S. H.

    2005-01-01

    Development of the regulatory guidelines for Beyond Design Basis Accidents (BDBA) with high risk requires a detailed investigation of major factors contributing to the event risk. In this study, each event was classified by the level of risk, based on the probabilistic safety assessment results, so that BDBA with high risk could be selected, with consideration of foreign and domestic regulations, and operating experiences. The regulatory requirements and technical backgrounds for the selected accidents were investigated, and effective regulatory approaches for risk reduction of the accidents. The following conclusions were drawn from this study: - Selected high risk BDBA is station blackout, anticipated without scram, total loss of feedwater. - Major contributors to the risk of selected events were investigated, and appropriate assessment of them was recommended for development of the regulatory guidelines

  2. Exemption from Regulatory Control of Goods Containing Small Amounts of Radioactive Material

    International Nuclear Information System (INIS)

    2012-01-01

    Small amounts of radioactive material may be added to various goods for functional reasons. Several such items are currently available for either professional or personal use. These include ionization chamber smoke detectors, thoriated-tungsten welding rods, luminous dials, electrical devices and electric discharge lamps. Some of these goods may be intended for particular types of market such as cinemas or other places to which the public may have access, but they are unlikely to be provided directly to members of the public. Other goods may be intended for wide scale use and therefore readily available on the market as consumer products through commercial outlets where personal and household products are normally purchased. Members of the public may be exposed to ionizing radiation as a consequence of activities such as transport, storage, use and disposal of such goods. The IAEA safety standards provide the basic requirements for regulatory control of such goods. The most relevant documents are the Governmental, Legal and Regulatory Framework for Safety and the International Basic Safety Standards (hereafter referred to as the BSS). These requirements include notification of a practice to the regulatory body and authorization of the practice by the regulatory body. Provision is made for the exemption of practices from these and other regulatory requirements based on general criteria given in the BSS or any exemption levels specified by the regulatory body on the basis of these criteria. The BSS, which are jointly sponsored by the IAEA and several other international organizations, apply to all facilities and all activities for peaceful purposes that give rise to exposure to radiation. In the interest of harmonization of approaches among Member States, some guidance on the application of the criteria for exemption has been provided in a number of Safety Guides, e.g. Regulatory Control of Radiation Sources, IAEA Safety Standards Series No. GS-G-1.5 (2004) and the

  3. Electromobility guide; Wegweiser Elektromobilitaet

    Energy Technology Data Exchange (ETDEWEB)

    Becks, Thomas; De Doncker, Rik; Karg, Ludwig; Rehtanz, Christian; Reinhardt, Andreas-Michael; Willums, Jan-Olaf [eds.

    2010-07-01

    Knowing about funded projects and their results helps to safeguard own innovation activities, promotes precompetition know-how transfer and makes it easier to use synergetic effects. This is where the new ''Electromobility Guide'' has a contribution to make. It gives the reader basic information on more than 150 national and international projects about electromobility. It names contact partners and gives corresponding details to make it easier to collect additional information. Our intention is for the Electromobility Guide to act as an incentive for sharing current, authentic, correct and reliable information about all electromobility projects in order to expand the joint data basis. Please help us in this respect and support electromobility in Germany with your knowledge. (orig.)

  4. ITER technical basis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.

  5. ITER technical basis

    International Nuclear Information System (INIS)

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

  6. Nuclear Regulatory Infrastructure in the Philippines

    International Nuclear Information System (INIS)

    Leonin, Teofilo V. Jr.

    2015-01-01

    Regulating the use of radioactive materials in the Philippines involves the adherence to legislation, regulations, standards and regulatory guides. It is based on a detailed review and assessment of the radiation safety program of owners and users of these materials and associated equipment against safety requirements and on additional verification of the operating practices and procedures. Republic Acts 5207 and 2067, both as amended, are implemented through the regulations which are titled Code of PNRI Regulations or CPRs are developed and issued together with supporting regulatory guides, Bulletins and other documents detailing the safety requirements. These issuance adhere to internationally accepted requirements on radiation protection, and nuclear safety and security, as well as safeguards. Design documents and technical Specifications of important radioactive materials, equipment and components are required to be submitted and reviewed by the PNRI before the issuance of an authorization in the form of a license Verification of adherence to regulations and safety requirements are periodically checked through the implementation of an inspection and enforcement program. The ISO certified regulatory management system of PNRI is documented in a QMS manual that provides guidance on all work processes. It involves systematic planning and evaluation of activities, multiple means of getting feedback on the work processes, and continuous efforts to improve its effectiveness. Efforts are implemented in order to strengthen the transparency openness, independence, technical competence and effectiveness of the regulatory body. (author)

  7. Competent authority regulatory control of the transport of radioactive material

    International Nuclear Information System (INIS)

    1987-04-01

    The purpose of this guide is to assist competent authorities in regulating the transport of radioactive materials and to assist users of transport regulations in their interactions with competent authorities. The guide should assist specifically those countries which are establishing their regulatory framework and further assist countries with established procedures to harmonize their application and implementation of the IAEA Regulations. This guide specifically covers various aspects of the competent authority implementation of the IAEA Regulations for the Safe Transport of Radioactive Material. In addition, physical protection and safeguards control of the transport of nuclear materials as well as third party liability aspects are briefly discussed. This is because they have to be taken into account in overall transport regulatory activities, especially when establishing the regulatory framework

  8. Technical basis document for natural event hazards

    International Nuclear Information System (INIS)

    CARSON, D.M.

    2003-01-01

    This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for natural event hazards (NEH)-initiated representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

  9. Guide device

    International Nuclear Information System (INIS)

    Brammer, C.M. Jr.

    1977-01-01

    Disclosed is a fuel handling guide tube centering device for use in nuclear reactors during fuel assembly handling operations. The device comprises an outer ring secured to the flange of a nuclear reactor pressure vessel, a rotatable table rotatably coupled to the outer ring, and a plurality of openings through the table. Truncated locating cones are positioned in each of the openings in the table, and the locating cones center the guide tube during fuel handling operations. The openings in the table are located such that each fuel assembly in the nuclear core may be aligned with one of the openings by a suitable rotation of the table. The locating cones thereby provide alignment between the fuel handling mechanism located in the guide tube and the individual fuel assemblies of the cone. The need for a device to provide alignment is especially critical for floating nuclear power plants, where wave motion may exist during fuel handling operations. 5 claims, 4 figures

  10. 76 FR 77275 - Self-Regulatory Organizations; International Securities Exchange, LLC; Notice of Filing of...

    Science.gov (United States)

    2011-12-12

    ... SECURITIES AND EXCHANGE COMMISSION [Release No. 34-65900; File No. SR-ISE-2011-82] Self-Regulatory... text of these statements may be examined at the places specified in Item IV below. The self-regulatory... such statements. A. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for...

  11. 77 FR 306 - Self-Regulatory Organizations; Chicago Board Options Exchange, Incorporated; Notice of Filing of...

    Science.gov (United States)

    2012-01-04

    ...). \\2\\ 17 CFR 240.19b-4. Self-Regulatory Organization's Statement of the Terms of Substance of the... contained in Chapter XXIVB. II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the Proposed Rule Change In its filing with the Commission, the self-regulatory organization...

  12. 76 FR 61447 - Self-Regulatory Organizations; Chicago Board Options Exchange, Incorporated; Notice of Proposed...

    Science.gov (United States)

    2011-10-04

    ... 240.19b-4. I. Self-Regulatory Organization's Statement of the Terms of Substance of the Proposed Rule... its filing with the Commission, the self-regulatory organization included statements concerning the... such statements. A. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for...

  13. Research and regulatory review

    International Nuclear Information System (INIS)

    Macleod, J.S.; Fryer, D.R.H.

    1979-01-01

    To enable the regulatory review to be effectively undertaken by the regulatory body, there is a need for it to have ready access to information generated by research activities. Certain advantages have been seen to be gained by the regulatory body itself directly allocating and controlling some portion of these activities. The princial reasons for reaching this conclusion are summarised and a brief description of the Inspectorates directly sponsored programme outlined. (author)

  14. 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

  15. Homebuyer's Guide.

    Science.gov (United States)

    Sindt, Roger P.; Harris, Jack

    Designed to assist prospective buyers in making such important decisions as whether to buy a new or older home and within what price range, the guide provides information on the purchase process. Discussion of the purchase process covers the life-cycle costs (recurring homeownership costs that must be met every month); selection of a home;…

  16. International regulatory activities

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    The 48. session of the IAEA general conference was held in Vienna from 20 to 24 september 2004 with the participation of delegates from 125 members states and representatives of various international organisations. A number of resolutions were adopted by the conference in the following fields: nuclear safety, radiation, transport and waste safety. The general conference also adopted a resolution on measures to protect against nuclear terrorism. The Director General decided in 2003 to appoint a group of experts to explore and advise on issues related to nuclear liability. This group called the International Expert Group on Nuclear Liability (I.N.L.E.X.) consists of 20 experts members from nuclear power and non nuclear power countries and from shipping and non shipping states. It serves three major functions: to create a forum of expertise to explore and advise on issues related to nuclear liability; to enhance global adherence by nuclear and non nuclear states to an effective nuclear liability regime, inter alia, on the basis of the convention on supplementary compensation for nuclear damage and the annex thereto, the Vienna convention on civil liability for nuclear damage, the Paris convention on third party liability in the field of nuclear energy, the joint protocol relating to the application of the vienna convention and the paris convention and the amendments thereto; and to assist in the development and strengthening of the national nuclear liability legal frameworks in IAEA members states to protect the public and the environment and to enhance nuclear safety. The second part of international regulatory concerns a directive on public access to environmental information made by the European Parliament. (N.C.)

  17. Design Guide for Category I reactors critical facilities

    International Nuclear Information System (INIS)

    Brynda, W.J.; Powell, R.W.

    1978-08-01

    The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned critical facilities be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission

  18. Defining Tobacco Regulatory Science Competencies.

    Science.gov (United States)

    Wipfli, Heather L; Berman, Micah; Hanson, Kacey; Kelder, Steven; Solis, Amy; Villanti, Andrea C; Ribeiro, Carla M P; Meissner, Helen I; Anderson, Roger

    2017-02-01

    In 2013, the National Institutes of Health and the Food and Drug Administration funded a network of 14 Tobacco Centers of Regulatory Science (TCORS) with a mission that included research and training. A cross-TCORS Panel was established to define tobacco regulatory science (TRS) competencies to help harmonize and guide their emerging educational programs. The purpose of this paper is to describe the Panel's work to develop core TRS domains and competencies. The Panel developed the list of domains and competencies using a semistructured Delphi method divided into four phases occurring between November 2013 and August 2015. The final proposed list included a total of 51 competencies across six core domains and 28 competencies across five specialized domains. There is a need for continued discussion to establish the utility of the proposed set of competencies for emerging TRS curricula and to identify the best strategies for incorporating these competencies into TRS training programs. Given the field's broad multidisciplinary nature, further experience is needed to refine the core domains that should be covered in TRS training programs versus knowledge obtained in more specialized programs. Regulatory science to inform the regulation of tobacco products is an emerging field. The paper provides an initial list of core and specialized domains and competencies to be used in developing curricula for new and emerging training programs aimed at preparing a new cohort of scientists to conduct critical TRS research. © The Author 2016. Published by Oxford University Press on behalf of the Society for Research on Nicotine and Tobacco. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  19. The biological basis of radiotherapy

    International Nuclear Information System (INIS)

    Steel, G.G.; Adams, G.E.; Horwich, A.

    1989-01-01

    The focus of this book is the biological basis of radiotherapy. The papers presented include: Temporal stages of radiation action:free radical processes; The molecular basis of radiosensitivity; and Radiation damage to early-reacting normal tissue

  20. Modifications to nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

  1. Modifications to nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2007-01-01

    This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

  2. The Role of Level-3 PSA in the Regulatory Structure for the Licensing of Future NPPs

    International Nuclear Information System (INIS)

    Jeong, Jong Tae; Han, Sang Hoon

    2008-01-01

    The probabilistic safety assessment (PSA) provides a systematic analysis to identify and quantify all risks that the plant imposed to the operators, general public and the environment and thus demonstrates compliance to regulatory risk criteria. Therefore, the PSA has been being played an important role in the development of safety requirements for the existing plants, mainly reactors using light water technology. However, the existing safety requirements may not be fully applicable to the future reactors due to the advances in technology, new safety options, and new strategies for managing abnormal plant conditions. Therefore, a comprehensive set of technology-neutral safety requirements are being developed by the IAEA and USNRC. Especially, USNRC is developing a basis for a regulatory structure that is applicable to all types of reactor designs, including gas-cooled, liquid metal, and heavy and light water-moderated reactors because metrics such as core damage and large early release may not be applicable to some advanced reactor designs. They are developing this kind of basis for a regulatory structure in order to provide a technology neutral safety approach that will guide the design, construction and operation, as well as safety assessment, of innovative reactors. They are using the quantitative safety goals expressed by means of a frequency-consequence diagram. Within this approach, the scope of the PSA needs to encompass a whole spectrum of off-normal events including frequent, infrequent, and rare initiating events and event sequences. These events include a spectrum of releases from minor to major, and sequences that address conditions less than the core damage sequences. It also needs to address the dose consequences of these event sequences as measured at the exclusion area boundary (EAB). In order to obtain dose consequences for the whole spectrum of off-normal events, the dose evaluation by using the deterministic and probabilistic approaches has to be

  3. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1991-10-01

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

  4. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1993-04-01

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

  5. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1990-01-01

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

  6. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1991-04-01

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

  7. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1991-08-01

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

  8. Trust in regulatory regimes

    NARCIS (Netherlands)

    Six, Frédérique; Verhoest, Koen

    2017-01-01

    Within political and administrative sciences generally, trust as a concept is contested, especially in the field of regulatory governance. This groundbreaking book is the first to systematically explore the role and dynamics of trust within regulatory regimes. Conceptualizing, mapping and analyzing

  9. Nuclear Regulatory legislation

    International Nuclear Information System (INIS)

    1984-06-01

    This compilation of statutes and material pertaining to nuclear regulatory legislation through the 97th Congress, 2nd Session, has been prepared by the Office of the Executive Legal Director, U.S. Nuclear Regulatory Commission, with the assistance of staff, for use as an internal resource document

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

    International Nuclear Information System (INIS)

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

    1996-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-08-01

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

  12. 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)

  13. Improving nuclear regulatory effectiveness

    International Nuclear Information System (INIS)

    2001-01-01

    Ensuring that nuclear installations are operated and maintained in such a way that their impact on public health and safety is as low as reasonably practicable has been and will continue to be the cornerstone of nuclear regulation. In the past, nuclear incidents provided the main impetus for regulatory change. Today, economic factors, deregulation, technological advancements, government oversight and the general requirements for openness and accountability are leading regulatory bodies to review their effectiveness. In addition, seeking to enhance the present level of nuclear safety by continuously improving the effectiveness of regulatory bodies is seen as one of the ways to strengthen public confidence in the regulatory systems. This report covers the basic concepts underlying nuclear regulatory effectiveness, advances being made and future requirements. The intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

  14. Ontario hydro radioactive material transportation field guide

    International Nuclear Information System (INIS)

    Howe, W.

    1987-01-01

    The recent introduction of both the AECB Transport Packaging of Radioactive Material Regulations and Transport Canada's Transportation of Dangerous Goods Regulations have significantly altered the requirements for transporting radioactive material in Canada. Extensive additional training as well as certification of several hundred Ontario Hydro employees has been necessary to ensure compliance with the additional and revised regulatory requirements. To assist in the training of personnel, an 'active' corporate Ontario Hydro Field Guide for Radioactive Material Transport document has been developed and published. The contents of this Field Guide identify current Ontario Hydro equipment and procedures as well as the updated relevant regulatory requirements within Canada. In addition, to satisfying Ontario Hydro requirements for this type of information over two thousand of these Field Guides have been provided to key emergency response personnel throughout the province of Ontario to assist in their transportation accident response training

  15. 77 FR 64148 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Regulatory...

    Science.gov (United States)

    2012-10-18

    ... Regulatory Guides (RG) RG 1.79, ````Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors,'' Revision 2 and RG 1.79.1, ``Initial Test Program of Emergency Core Cooling Systems for...

  16. PFP functional development planning guide

    International Nuclear Information System (INIS)

    SINCLAIR, J.C.

    1999-01-01

    The PFP Functional Development Planning Guide presents the strategy and process used for the identification, development, and analysis of functions (activities) necessary to satisfy the requirements within the Plutonium Finishing Plant (PFP) integrated project baseline. The functional analysis will provide the basis for the development of a function driven work breakdown structure. Future revisions to this document will include as attachments the results of the PFP Functional Analysis resulting from this approach. This document is intended be a Project-owned management tool. As such, the guide will periodically require revisions resulting from improvements of the information, processes, and techniques as now described

  17. National legislative and regulatory activities

    International Nuclear Information System (INIS)

    2015-01-01

    uses of nuclear energy, signed on 1 September 2014, in Beijing; Nuclear security - Order No. 181/2014 for approval of norms regarding the protection of nuclear installation against cyber threats; Nuclear safety and radiological protection - Order No. 51/2015 for approval of the Nuclear Safety Guide regarding industrial codes and standards for nuclear power plants; Order No. 199/2015 for approval of the norms regarding nuclear safety policy and technical operation conditions for nuclear installations; Order No. 177/2015 for approval of norms regarding nuclear safety policy and independent assessment of nuclear safety; Order No. 180/2015 for approval of the guide regarding independent verification of the nuclear safety analyses and evaluation for nuclear installations; Order No. 198/2015 for approval of the guide regarding the framework and content of the nuclear safety final report for nuclear power plants; 7 - Slovak Republic: International co-operation - Details about international agreements concluded by the Slovak Republic; Liability and compensation - Regulation No. 170/2015 Establishing a List of Radioactive Materials, Their Quantities and Their Physical and Chemical Parameters Justifying the Low Risk of Nuclear Damage; General legislation - amendments to existing NRA regulations; 8 - Slovenia: General legislation - Amendments to the Ionising Radiation Protection and Nuclear Safety Act; 9 - Switzerland: Radioactive waste management; Liability and compensation Obligation of insurance, risks not covered by private insurers - Partial revision of the Ordinance on Nuclear Third Party Liability (ORCN); 10 - USA: Licensing and regulatory infrastructure - Commission authorises issuance of combined licence for Fermi Nuclear Power Plant in Monroe County, Michigan; Radioactive waste management - NRC conducts final public meetings on Yucca Mountain Environmental Report Supplement

  18. Standard Guide for Packaging Materials for Foods to Be Irradiated

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This guide provides a format to assist producers and users of food packaging materials in selecting materials that have the desirable characteristics for their intended use and comply with applicable standards or government authorizations. It outlines parameters that should be considered when selecting food-contact packaging materials intended for use during irradiation of prepackaged foods and it examines the criteria for fitness for their use. 1.2 This guide identifies known regulations and regulatory frameworks worldwide pertaining to packaging materials for holding foods during irradiation; but it does not address all regulatory issues associated with the selection and use of packaging materials for foods to be irradiated. It is the responsibility of the user of this guide to determine the pertinent regulatory issues in each country where foods are to be irradiated and where irradiated foods are distributed. 1.3 This guide does not address all of the food safety issues associated with the synergisti...

  19. Accelerator production of tritium authorization basis strategy

    International Nuclear Information System (INIS)

    Miller, L.A.; Edwards, J.; Rose, S.

    1996-01-01

    The Accelerator Production of Tritium (APT) project has proposed a strategy to develop the APT authorization basis and safety case based on DOE orders and fundamental requirements for safe operation. The strategy is viable regardless of whether the APT is regulated by DOE or by an external regulatory body. Currently the operation of Department of Energy (DOE) facilities is authorized by DOE and regulated by DOE orders and regulations while meeting the environmental protection requirements of the Environmental Protection Agency (EPA) and the states. In the spring of 1994, Congress proposed legislation and held hearings related to requiring all DOE operations to be subject to external regulation. On January 25, 1995, DOE, with the support of the White House Council on Environmental Quality, created the Advisory Committee on External Regulation of Department of Energy Nuclear Safety. This committee divided its recommendations into three areas: (1) facility safety, (2) worker safety, and (3) environmental protection. In the area of facility safety the committee recommended external regulation of DOE nuclear facilities by either the Nuclear Regulatory Commission (NRC) or a restructured Defense Nuclear Facilities Safety Board (DNFSB). In the area of worker safety, the committee recommended that the Occupational Safety and Health Administration (OSHA) regulate DOE nuclear facilities. In the environmental protection area, the committee did not recommend a change in the regulation by the EPA and the states of DOE nuclear facilities. If these recommendations are accepted, all DOE nuclear facilities will be impacted to some extent

  20. A technical basis for meeting waste form stability requirements of 10 CFR 61

    International Nuclear Information System (INIS)

    Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

    1988-01-01

    To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

  1. Regulatory guidance document

    International Nuclear Information System (INIS)

    1994-05-01

    The Office of Civilian Radioactive Waste Management (OCRWM) Program Management System Manual requires preparation of the OCRWM Regulatory Guidance Document (RGD) that addresses licensing, environmental compliance, and safety and health compliance. The document provides: regulatory compliance policy; guidance to OCRWM organizational elements to ensure a consistent approach when complying with regulatory requirements; strategies to achieve policy objectives; organizational responsibilities for regulatory compliance; guidance with regard to Program compliance oversight; and guidance on the contents of a project-level Regulatory Compliance Plan. The scope of the RGD includes site suitability evaluation, licensing, environmental compliance, and safety and health compliance, in accordance with the direction provided by Section 4.6.3 of the PMS Manual. Site suitability evaluation and regulatory compliance during site characterization are significant activities, particularly with regard to the YW MSA. OCRWM's evaluation of whether the Yucca Mountain site is suitable for repository development must precede its submittal of a license application to the Nuclear Regulatory Commission (NRC). Accordingly, site suitability evaluation is discussed in Chapter 4, and the general statements of policy regarding site suitability evaluation are discussed in Section 2.1. Although much of the data and analyses may initially be similar, the licensing process is discussed separately in Chapter 5. Environmental compliance is discussed in Chapter 6. Safety and Health compliance is discussed in Chapter 7

  2. Risk-based regulation: A regulatory perspective

    International Nuclear Information System (INIS)

    Scarborough, J.C.

    1993-01-01

    In the early development of regulations for nuclear power plants, risk was implicitly considered through qualitative assessments and engineering reliability principles and practices. Examples included worst case analysis, defense in depth, and the single failure criterion. However, the contributions of various systems, structures, components and operator actions to plant safety were not explicitly assessed since a methodology for this purpose had not been developed. As a consequence of the TMI accident, the use of more quantitative risk methodology and information in regulation such as probabilistic risk analysis (PRA) increased. The use of both qualitative and quantitative consideration of risk in regulation has been a set of regulations and regulatory guides and practices that ensure adequate protection of public health and safety. Presently, the development of PRA techniques has developed to the point that safety goals, expressed in terms of risk, have been established to help guide further regulatory decision making. This paper presents the personal opinions of the author as regards the use of risk today in nuclear power plant regulation, areas of further information needs, and necessary plans for moving toward a more systematic use of risk-based information in regulatory initiatives in the future

  3. Managing Regulatory Body Competence

    International Nuclear Information System (INIS)

    2013-01-01

    In 2001, the IAEA published TECDOC 1254, which examined the way in which the recognized functions of a regulatory body for nuclear facilities results in competence needs. Using the systematic approach to training (SAT), TECDOC 1254 provided a framework for regulatory bodies for managing training and developing and their maintaining their competence. It has been successfully used by many regulators. The IAEA has also introduced a methodology and an assessment tool - Guidelines for Systematic Assessment of Regulatory Competence Needs (SARCoN) - which provides practical guidance on analysing the training and development needs of a regulatory body and, through a gap analysis, guidance on establishing competence needs and how to meet them. In 2009, the IAEA established a steering committee (supported by a bureau) with the mission to advise the IAEA on how it could best assist Member States to develop suitable competence management systems for their regulatory bodies. The committee recommended the development of a safety report on managing staff competence as an integral part of a regulatory body's management system. This Safety Report was developed in response to this request. It supersedes TECDOC 1254, broadens its application to regulatory bodies for all facilities and activities, and builds upon the experience gained through the application of TECDOC 1254 and SARCoN and the feedback received from Member States. This Safety Report applies to the management of adequate competence as needs change, and as such is equally applicable to the needs of States 'embarking' on a nuclear power programme. It also deals with the special case of building up the competence of regulatory bodies as part of the overall process of establishing an 'embarking' State's regulatory system

  4. 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

  5. Regulatory control of nuclear facility valves and their actuators

    International Nuclear Information System (INIS)

    1993-01-01

    The methods and procedures by which the Finnish Centre for Radiation and Nuclear Safety (STUK) regulates valves and their actuators in nuclear power plants and in other nuclear facilities are specified in the guide. The scope of regulation depends on the Safety Class of the valve and the actuator in question. The Safety Classification principles for the systems, structures and components of the nuclear power plants are described in the guide YVL 2.1 and the regulatory control of the nuclear facility safety valves is described in the guide YVL 5.4

  6. Use and regulatory control of dental X-ray installations

    International Nuclear Information System (INIS)

    1999-01-01

    In the guide the safety requirements concerning dental X-ray installations and their use, prerequisities for exemption from a safety licence, and regulatory control are presented. The guide applies to conventional dental X-ray installations, by which an image is created on an X-ray film or other image receptor placed inside the mouth, and panorama tomography installations for dentition and the cephalostats associated with these. The guide does not apply to multitechnique tomography installations intended for the special imaging of the skull or jaws

  7. 18 CFR 367.13 - Accounting to be on accrual basis.

    Science.gov (United States)

    2010-04-01

    ... ACT General Instructions § 367.13 Accounting to be on accrual basis. (a) The service company is... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Accounting to be on accrual basis. 367.13 Section 367.13 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY...

  8. 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.

  9. 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

  10. Infrastructure of the Regulatory Authority and Performance Indexes

    International Nuclear Information System (INIS)

    Velasquez, Silvia

    2001-01-01

    This presentation overviews the following issues: elements of a control regulatory program, inspections program, procedures, indexes of users performance, priorities on: registration, criteria for practices of low risk, dose levels in medical exposures, dose constraints and training of personnel. These aspects are considered in the guides prepared within ARCAL XX framework

  11. Expert Guide

    DEFF Research Database (Denmark)

    Heiselberg, Per

    , their benefits and limitations, economical feasibility and impact on energy savings, company image, comfort, productivity, building functionality and flexibility and gives guidance on design of these concepts, including integration of responsive building elements and HVAC-systems and build examples......This guide summarizes the work of Subtask B of IEA-ECBCS Annex 44 “Integrating Environmentally Responsive Elements in Buildings” and is based on the contributions from the participating countries. The publication is an official Annex report. With a focus on innovative building concepts...

  12. Prevention as a main objective in the regulatory practices relating to research reactors

    International Nuclear Information System (INIS)

    Waldman, Ricardo M.

    2006-01-01

    In Argentina the use of research reactors and critical facilities are very diverse, varying since the production of radionuclides, to the investigation or the teaching. Also diverse are the licensing characteristics, going from the National Atomic Energy Commission-Argentina to national universities. The strategy utilized for the regulatory control is based especially in the prevention. The prevention covers: regulatory framework, to emit standards and regulatory guides, to licensing installations and the personnel. (author) [es

  13. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1990-10-01

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

  14. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1990-04-01

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

  15. Through the regulatory hoop

    International Nuclear Information System (INIS)

    Kirner, N.P.

    1985-01-01

    There are many regulatory hoops through which waste generators, brokers, and disposal site operators must jump to dispose of waste safely. As the proposed exclusionary date of January 1, 1986, approaches, these regulatory hoops have the distinct possibility of multiplying or at least changing shape. The state of Washington, in its role as an Agreement State with the US Nuclear Regulatory Commission, licenses and inspects the commercial operator of the Northwest Compact's low-level radioactive waste disposal site on the Hanford Reservation. Washington has received as much as 53%, or 1.4 million cubic feet per year, of the nation's total volume of waste disposed. To control such a large volume of waste, a regulatory program involving six agencies has developed over the years in Washington

  16. Regulatory requirements for desalination plant coupled with nuclear reactor plant

    International Nuclear Information System (INIS)

    Yune, Young Gill; Kim, Woong Sik; Jo, Jong Chull; Kim, Hho Jung; Song, Jae Myung

    2005-01-01

    A small-to-medium sized reactor has been developed for multi-purposes such as seawater desalination, ship propulsion, and district heating since early 1990s in Korea. Now, the construction of its scaled-down research reactor, equipped with a seawater desalination plant, is planned to demonstrate the safety and performance of the design of the multi-purpose reactor. And the licensing application of the research reactor is expected in the near future. Therefore, a development of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant is necessary for the preparation of the forthcoming licensing review of the research reactor. In this paper, the following contents are presented: the design of the desalination plant, domestic and foreign regulatory requirements relevant to desalination plants, and a draft of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant

  17. South African Regulatory Framework for Nuclear Power Plant Life Management

    International Nuclear Information System (INIS)

    Mbebe, B.Z.

    2012-01-01

    The paper presents the regulatory approach to plant life management (PLiM) adopted by the National Nuclear Regulator (NNR) in South Africa, the licensing basis and regulatory requirements for Koeberg Nuclear Power Station (KNPS),operational programmes ensuring continued safe operation, issues related to the ageing of the plant, and the requirements for spent fuel as well as radioactive waste management. The paper will further present insights from the Periodic Safety Review (PSR) and Long Term Asset Management. (author)

  18. The regulatory process for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this publication is to provide general guidance to Member States for regulating the decommissioning of nuclear facilities within the established nuclear regulatory framework. The Guide should also be useful to those responsible for, or interested in, the decommissioning of nuclear facilities. The Guide describes in general terms the process to be used in regulating decommissioning and the considerations to be applied in the development of decommissioning regulations and guides. It also delineates the responsibilities of the regulatory body and the licensee in decommissioning. The provisions of this Guide are intended to apply to all facilities within the nuclear fuel cycle and larger industrial installations using long lived radionuclides. For smaller installations, however, less extensive planning and less complex regulatory control systems should be acceptable. The Guide deals primarily with decommissioning after planned shutdown. Most provisions, however, are also applicable to decommissioning after an abnormal event, once cleanup operations have been terminated. The decommissioning planning in this case must take account of the abnormal event. 28 refs, 1 fig

  19. Projecting regulatory expectations for advanced reactor designs

    International Nuclear Information System (INIS)

    Viktorov, A.

    2011-01-01

    This paper explores the overarching safety principles that will likely guide the safety design of advanced reactor technologies. As will be shown, the already established safety framework provides a solid foundation for the safety design of future nuclear power plants. As a specific example, the principle of 'proven technology' is presented in greater detail and its implications for a novel technology are discussed. Research, modeling and prototyping are shown to be components in satisfying this principle. While the fundamental safety principles are in place, their interpretation may depend both on the considered technology as well as the national context. Thus, the regulatory authority will need to be engaged, at an appropriate stage of the technology development, in specifying the regulatory requirements that will have to be met for a specific reactor design. (author)

  20. REFORMASI SISTEM AKUNTANSI CASH BASIS MENUJU SISTEM AKUNTANSI ACCRUAL BASIS

    Directory of Open Access Journals (Sweden)

    Yuri Rahayu

    2016-03-01

    Full Text Available Abstract –  Accounting reform movement was born with the aim of structuring the direction of improvement . This movement is characterized by the enactment of the Act of 2003 and Act 1 of 2004, which became the basis of the birth of Government Regulation No.24 of 2005 on Government Accounting Standards ( SAP . The general,  accounting is based on two systems,  the cash basis  and the accrual basis. The facts speak far students still at problem with differences to the two methods that result in a lack of understanding on the treatment system for recording. The purpose method of research is particularly relevant to student references who are learning basic accounting so that it can provide information and more meaningful understanding of the accounting method cash basis and Accrual basis. This research was conducted through a normative approach, by tracing the document that references a study/library that combines source of reference that can be believed either from books and the internet are processed with a foundation of knowledge and experience of the author. The conclusion can be drawn that basically to be able to understand the difference of the system and the Cash Basis accrual student base treatment requires an understanding of both methods. To be able to have the ability and understanding of both systems required reading exercises and reference sources.   Keywords : Reform, cash basis, accrual basis   Abstrak - Gerakan reformasi akuntansi dilahirkan dengan tujuan penataan ke arah perbaikan. Gerakan ini  ditandai dengan dikeluarkannya  Undang-Undang tahun 2003 dan Undang-Undang No.1 Tahun 2004  yang menjadi dasar lahirnya Peraturan Pemerintah No.24 Tahun 2005 tentang Standar Akuntansi Pemerintah (SAP . Pada umumnya pencatatan akuntansi di dasarkan pada dua sistem yaitu basis kas (Cash Basis dan basis akrual  (Accrual Basis. Fakta berbicara Selama ini mahasiswa masih dibinggungkan dengan perbedaan ke dua metode itu sehingga

  1. Site-specific parameter values for the Nuclear Regulatory Commission's food pathway dose model

    International Nuclear Information System (INIS)

    Hamby, D.M.

    1992-01-01

    Routine operations at the Savannah River Site (SRS) in Western South Carolina result in radionuclide releases to the atmosphere and to the Savannah River. The resulting radiation doses to the off-site maximum individual and the off-site population within 80 km of the SRS are estimated on a yearly basis. These estimates are currently generated using dose models prescribed for the commercial nuclear power industry by the Nuclear Regulatory Commission (NRC). The NRC provides default values for dose-model parameters for facilities without resources to develop site-specific values. A survey of land- and water-use characteristics for the Savannah River area has been conducted to determine site-specific values for water recreation, consumption, and agricultural parameters used in the NRC Regulatory Guide 1.109 (1977) dosimetric models. These site parameters include local characteristics of meat, milk, and vegetable production; recreational and commercial activities on the Savannah River; and meat, milk, vegetable, and seafood consumption rates. This paper describes how parameter data were obtained at the Savannah River Site and the impacts of such data on off-site dose. Dose estimates using site-specific parameter values are compared to estimates using the NRC default values

  2. Neurobiological basis of parenting disturbance.

    Science.gov (United States)

    Newman, Louise K; Harris, Melissa; Allen, Joanne

    2011-02-01

    It has been proposed that early attachment relationships shape the structure and reactivity of social brain structures that underlie later social capacities. We provide a review of the literature surrounding the development of neurological regulatory systems during infancy and outline recent research suggesting these systems go on to underlie adaptive parental responses. We review evidence in the peer-reviewed psychiatric literature including (i) observational human literature on the neurobiological and social sequelae of early parenting experiences, (ii) experimental animal literature on the effects of early maternal care on neurological development, (iii) experimental animal literature on the neurobiological underpinnings of parenting behaviours, (iv) observational and fMRI evidence on the neurobiological correlates of parenting behaviours, (v) functional and volumetric imaging studies on adults affected by borderline personality disorder. The development of infant regulatory systems is influenced by early parenting experiences. These frontolimbic regulatory systems are also heavily implicated in normal parental responses to infant cues. These frontolimbic disturbances are also observed in studies of borderline personality disorder; a disorder associated with poor emotional regulation, early trauma and disturbed parenting. While the current literature is limited to animal models of abnormal care giving, existing disorders associated with deficits in regulatory capacity and abnormal frontolimbic functioning may yet provide a human model of the neurobiology of parenting disturbance.

  3. Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules.

  4. Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

  5. Manual on gamma radiography. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to gamma radiography: its application and procedures guides

  6. Manual on therapeutic uses of iodine-131. Incorporating: Applications guide, procedures guide, basics guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to therapeutic uses of Iodine-131: its application and procedures guides.

  7. Manual on high energy teletherapy. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to high energy radiotherapy: its application and procedures guides

  8. Manual on shielded enclosures. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to shielding enclosures: their application and procedures guides

  9. Manual on therapeutic uses of iodine-131. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to therapeutic uses of Iodine-131: its application and procedures guides

  10. Manual on nuclear gauges. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to nuclear gauges: their application and procedures guides

  11. The response of pile-guided floats subjected to dynamic loading : volume I final report.

    Science.gov (United States)

    2014-08-01

    Pile : - : Guided floats can be a desirable alternative to stationary berthing structures. Both floats and guide piles are subjected to dynamic : forces such as wind generated waves and impacts from vessels. This project developed a rational basis fo...

  12. Development of dose calculation program (DBADOSE) incorporating alternative source term due to design basis accident

    International Nuclear Information System (INIS)

    Bae, Young Jig; Nam, Ki Mun; Lee, Yu Jong; Chung, Chan Young

    2003-01-01

    Source terms presented in TID-14844 and Regulatory Guide 1.4 have been used for radiological analysis of design basis accidents for licensing existing pressurized water reactor (PWR). However, more realistic and physically-based source term based on results of study and experiments for about 30 years after the publication of TID-14844 was developed and presented in NUREG-1465 published by U.S NRC in 1995. In addition, ICRP has revised dose concepts and criteria through the publication of ICRP-9, 26, 60 and recommended effective dose concepts rather than critical organ concept since the publication of ICRP-26. Accordingly, multipurpose computer program called DBADOSE incorporating alternative source terms in NUREG-1465 and effective dose concepts in ICRP-60 was developed. Comparison of results of DBADOSE with those of POSTDBA and STARDOSE was performed and verified and no significant difference and inaccuracy were found. DBADOSE will be used to evaluate accidental doses for licensing application according to the domestic laws that are expected to be revised in the near future

  13. Tank characterization reference guide

    International Nuclear Information System (INIS)

    De Lorenzo, D.S.; DiCenso, A.T.; Hiller, D.B.; Johnson, K.W.; Rutherford, J.H.; Smith, D.J.; Simpson, B.C.

    1994-09-01

    Characterization of the Hanford Site high-level waste storage tanks supports safety issue resolution; operations and maintenance requirements; and retrieval, pretreatment, vitrification, and disposal technology development. Technical, historical, and programmatic information about the waste tanks is often scattered among many sources, if it is documented at all. This Tank Characterization Reference Guide, therefore, serves as a common location for much of the generic tank information that is otherwise contained in many documents. The report is intended to be an introduction to the issues and history surrounding the generation, storage, and management of the liquid process wastes, and a presentation of the sampling, analysis, and modeling activities that support the current waste characterization. This report should provide a basis upon which those unfamiliar with the Hanford Site tank farms can start their research

  14. Perceptions of regulatory approaches

    International Nuclear Information System (INIS)

    Halin, Magnus; Leinonen, Ruusaliisa

    2012-01-01

    Ms. Ruusaliisa Leinonen and Mr. Magnus Halin from Fortum gave a joint presentation on industry perceptions of regulatory oversight of LMfS/SC. It was concluded that an open culture of discussion exists between the regulator (STUK) and the licensee, based on the common goal of nuclear safety. An example was provided of on how regulatory interventions helped foster improvements to individual and collective dose rate trends, which had remained static. Regulatory interventions included discussions on the ALARA concept to reinforce the requirement to continuously strive for improvements in safety performance. Safety culture has also been built into regulatory inspections in recent years. Training days have also been organised by the regulatory body to help develop a shared understanding of safety culture between licensee and regulatory personnel. Fortum has also developed their own training for managers and supervisors. Training and ongoing discussion on LMfS/SC safety culture is considered particularly important because both Fortum and the regulatory body are experiencing an influx of new staff due to the demographic profile of their organisations. It was noted that further work is needed to reach a common understanding of safety culture on a practical level (e.g., for a mechanic setting to work), and in relation to the inspection criteria used by the regulator. The challenges associated with companies with a mix of energy types were also discussed. This can make it more difficult to understand responsibilities and decision making processes, including the role of the parent body organisation. It also makes communication more challenging due to increased complexity and a larger number of stakeholders

  15. 75 FR 39714 - Self-Regulatory Organizations; Notice of Filing and Immediate Effectiveness of Rule Change by...

    Science.gov (United States)

    2010-07-12

    ... have been prepared by the self-regulatory organization. The Commission is publishing this notice to....C. 78a. \\3\\ 17 CFR 240.19b-4. I. Self-Regulatory Organization's Statement of the Terms of the.... II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the Proposed...

  16. 76 FR 77877 - Self-Regulatory Organizations; EDGA Exchange, Inc.; Notice of Filing of Proposed Rule Change To...

    Science.gov (United States)

    2011-12-14

    .... \\1\\ 15 U.S.C. 78s(b)(1). \\2\\ 17 CFR 240.19b-4. I. Self-Regulatory Organization's Statement of the...). II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the Proposed... self-regulatory organization has prepared summaries, set forth in Sections A, B and C below, of the...

  17. 77 FR 74715 - Self-Regulatory Organizations; NASDAQ OMX PHLX LLC; Notice of Filing and Immediate Effectiveness...

    Science.gov (United States)

    2012-12-17

    .... Self-Regulatory Organization's Statement of the Terms of Substance of the Proposed Rule Change The... Room. II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the... significant aspects of such statements. A. Self-Regulatory Organization's Statement of the Purpose of, and...

  18. 75 FR 27609 - Self-Regulatory Organizations; NYSE Arca, Inc.; Notice of Filing and Immediate Effectiveness of...

    Science.gov (United States)

    2010-05-17

    ... have been prepared by the self-regulatory organization. The Commission is publishing this notice to....C. 78a. \\3\\ 17 CFR 240.19b-4. I. Self-Regulatory Organization's Statement of the Terms of Substance... Reference Room. II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the...

  19. 77 FR 31060 - Self-Regulatory Organizations; the Options Clearing Corporation; Notice of Filing and of Proposed...

    Science.gov (United States)

    2012-05-24

    ... SECURITIES AND EXCHANGE COMMISSION [Release No. 34-67021; File No. SR-OCC-2012-07] Self-Regulatory... from interested persons. \\1\\ 15 U.S.C. 78s(b)(1). \\2\\ 17 CFR 240.19b-4. I. Self-Regulatory Organization... equity options. II. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for...

  20. 77 FR 34420 - Self-Regulatory Organizations; NASDAQ OMX PHLX LLC; Notice of Filing and Immediate Effectiveness...

    Science.gov (United States)

    2012-06-11

    ... statements. A. Self-Regulatory Organization's Statement of the Purpose of, and Statutory Basis for, the... respect to marking Strategy Trades would be uniformly applied to members. B. Self-Regulatory Organization... the Act. C. Self-Regulatory Organization's Statement on Comments on the Proposed Rule Change Received...

  1. Ageing Management for Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  2. Ageing Management for Research Reactors. Specific Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  3. 75 FR 19665 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-04-15

    ... processes, including welding, heat treating, and nondestructive testing, are controlled and accomplished by... that when stressed under operating, maintenance, testing, and postulated accident conditions (1) the...

  4. 75 FR 1658 - Withdrawal of Regulatory Guide 7.5

    Science.gov (United States)

    2010-01-12

    ..., Washington, DC 20555-0001, telephone: 301-251-7447 or e-mail [email protected] . SUPPLEMENTARY..., e.g., Federal, State, or local government radioactive material shipments transported by government... 301- 415-3548, and by e-mail to [email protected] . Dated at Rockville, Maryland, this 5th day of...

  5. 76 FR 2726 - Withdrawal of Regulatory Guide 1.154

    Science.gov (United States)

    2011-01-14

    ... that it is possible to perform a plant-specific analysis to show that some conservatism could... much of the conservatism that was embedded in the more restrictive 10 CFR 50.61 RT screening criteria. This calls into question whether a strong case could be made to remove further conservatism in a plant...

  6. 75 FR 16516 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-04-01

    ...-7404 or e- mail [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear... license to operate a facility include in a final safety analysis report, along with other information, the..., the public can gain entry into ADAMS, which provides text and image files of NRC's public documents...

  7. 75 FR 41241 - Draft Regulatory Guide; Issuance, Availability

    Science.gov (United States)

    2010-07-15

    ...: (301) 251-7404 or e-mail [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The U.S... analysis and testing applicable to Emergency Core Cooling System (ECCS) strainer performance and debris... provides text and image files of NRC's public documents. If you do not have access to ADAMS or if there are...

  8. 76 FR 25725 - Final Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2011-05-05

    ...: [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear...-collections/ . From this page, the public can gain entry into ADAMS, which provides text and image files of... analysis may be found under ADAMS Accession Number ML102350474 and the staff's responses to the public...

  9. 75 FR 43208 - Withdrawal of Regulatory Guide 5.17

    Science.gov (United States)

    2010-07-23

    ... the vehicles under daylight conditions from the air in clear weather at 1,000 feet above ground level... Transportation (DOT) regulations 49 CFR parts 172 through 180. These DOT regulations specify the shape, color...

  10. 75 FR 35508 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-06-22

    ... Systems and Networks,'' requires licensees to develop cyber-security plans and programs to protect....71, ``Cyber Security Programs for Nuclear Facilities,'' provides guidance to meet the requirements of... address these issues, DG-1249: 1. Eliminates all reference to cyber security, malicious activity, or...

  11. Regulatory Guide on Conducting a Security Vulnerability Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Ek, David R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    This document will provide guidelines on conducting a security vulnerability assessment at a facility regulated by the Radiation Protection Centre. The guidelines provide a performance approach assess security effectiveness. The guidelines provide guidance for a review following the objectives outlined in IAEA NSS#11 for Category 1, 2, & 3 sources.

  12. 76 FR 26320 - Draft Regulatory Guide: Reissuance and Availability

    Science.gov (United States)

    2011-05-06

    ... of the Code of Federal Regulations (10 CFR) Part 50, ``Domestic Licensing of Production and... could occur in the large steam turbines of the main turbine- generator sets have the potential for... appropriate orientation and placement of the turbine-generator set, the management of the probability of...

  13. Nuclear installations safety in France. Compilation of regulatory guides

    International Nuclear Information System (INIS)

    1988-01-01

    General plan: 1. General organization of public officials. Procedures 1.1. Texts defining the general organization and the procedures 1.2. Interventing organisms; 2. Texts presenting a technical aspect other than basic safety rules and associated organization texts; 2.1. Dispositions relating to safety of nuclear installations 2.2. Dispositions relating to pressure vessels 2.3. Dispositions relating to quality 2.4. Dispositions relating to radioactive wastes release 2.5. Dispositions relating to activities depending of classified installations; 3. Basic Safety Rules (BSR) 3.1. BSR relating to PWR 3.2. BSR relating to nuclear installations other than PWR 3.3. Other BSR [fr

  14. Nuclear regulatory decision making

    International Nuclear Information System (INIS)

    Wieland, Patricia; Almeida, Ivan Pedro Salati de

    2011-01-01

    The scientific considerations upon which the nuclear regulations are based provide objective criteria for decisions on nuclear safety matters. However, the decisions that a regulatory agency takes go far beyond granting or not an operating license based on assessment of compliance. It may involve decisions about hiring experts or research, appeals, responses to other government agencies, international agreements, etc.. In all cases, top management of the regulatory agency should hear and decide the best balance between the benefits of regulatory action and undue risks and other associated impacts that may arise, including issues of credibility and reputation. The establishment of a decision framework based on well established principles and criteria ensures performance stability and consistency, preventing individual subjectivity. This article analyzes the challenges to the decision-making by regulatory agencies to ensure coherence and consistency in decisions, even in situations where there is uncertainty, lack of reliable information and even divergence of opinions among experts. The article explores the basic elements for a framework for regulatory decision-making. (author)

  15. Fast radial basis functions for engineering applications

    CERN Document Server

    Biancolini, Marco Evangelos

    2017-01-01

    This book presents the first “How To” guide to the use of radial basis functions (RBF). It provides a clear vision of their potential, an overview of ready-for-use computational tools and precise guidelines to implement new engineering applications of RBF. Radial basis functions (RBF) are a mathematical tool mature enough for useful engineering applications. Their mathematical foundation is well established and the tool has proven to be effective in many fields, as the mathematical framework can be adapted in several ways. A candidate application can be faced considering the features of RBF:  multidimensional space (including 2D and 3D), numerous radial functions available, global and compact support, interpolation/regression. This great flexibility makes RBF attractive – and their great potential has only been partially discovered. This is because of the difficulty in taking a first step toward RBF as they are not commonly part of engineers’ cultural background, but also due to the numerical complex...

  16. Standard guide for digital detector array radiology

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This standard is a user guide, which is intended to serve as a tutorial for selection and use of various digital detector array systems nominally composed of the detector array and an imaging system to perform digital radiography. This guide also serves as an in-detail reference for the following standards: Practices E2597, , and E2737. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  17. Nuclear Regulatory Legislation

    International Nuclear Information System (INIS)

    1989-08-01

    This compilation of statutes and material pertaining to nuclear regulatory legislation through the 100th Congress, 2nd Session, has been prepared by the Office of the General Counsel, US Nuclear Regulatory Commission, with the assistance of staff, for use as an internal resource document. Persons using this document are placed on notice that it may not be used as an authoritative citation in lieu of the primary legislative sources. Furthermore, while every effort has been made to ensure the completeness and accuracy of this material, neither the United States Government, the Nuclear Regulatory Commission, nor any of their employees makes any expressed or implied warranty or assumes liability for the accuracy or completeness of the material presented in this compilation

  18. Regulatory and licensee surveys

    International Nuclear Information System (INIS)

    2009-01-01

    Prior to the workshop two CSNI/WGHOF surveys were distributed. One survey was directed at regulatory bodies and the other was directed at plant licensees. The surveys were: 1 - Regulatory Expectations of Licensees' Arrangements to Ensure Suitable Organisational Structure, Resources and Competencies to Manage Safety (sent to WGHOF regulatory members). The survey requested that the respondents provide a brief overview of the situation related to plant organisations in their country, their regulatory expectations and their formal requirements. The survey addressed three subjects: the demonstration and documentation of organisational structures, resources and competencies, organisational changes, issues for improvement (for both current and new plants). Responses were received from eleven regulatory bodies. 2 - Approaches to Justify Organisational Suitability (sent to selected licensees). The purpose of the survey to was to gain an understanding of how licensees ensure organisational suitability, resources and competencies. This information was used to assist in the development of the issues and subjects that were addressed at the group discussion sessions. Responses were received from over fifteen licensees from nine countries. The survey requested that the licensees provide information on how they ensure effective organisational structures at their plants. The survey grouped the questions into the following four categories: organisational safety functions, resource and competence, decision-making and communication, good examples and improvement needs. The findings from these surveys were used in conjunction with other factors to identify the key issues for the workshop discussion sessions. The responses from these two surveys are discussed briefly in Sections 4 and 5 of this report. More extensive reviews of the regulatory and licensee responses are provided in Appendix 1

  19. Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-08-15

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

  20. Preclosure Safety Analysis Guide

    International Nuclear Information System (INIS)

    D.D. Orvis

    2003-01-01

    A preclosure safety analysis (PSA) is a required element of the License Application (LA) for the high- level radioactive waste repository at Yucca Mountain. This guide provides analysts and other Yucca Mountain Repository Project (the Project) personnel with standardized methods for developing and documenting the PSA. The definition of the PSA is provided in 10 CFR 63.2, while more specific requirements for the PSA are provided in 10 CFR 63.112, as described in Sections 1.2 and 2. The PSA requirements described in 10 CFR Part 63 were developed as risk-informed performance-based regulations. These requirements must be met for the LA. The PSA addresses the safety of the Geologic Repository Operations Area (GROA) for the preclosure period (the time up to permanent closure) in accordance with the radiological performance objectives of 10 CFR 63.111. Performance objectives for the repository after permanent closure (described in 10 CFR 63.113) are not mentioned in the requirements for the PSA and they are not considered in this guide. The LA will be comprised of two phases: the LA for construction authorization (CA) and the LA amendment to receive and possess (R and P) high-level radioactive waste (HLW). PSA methods must support the safety analyses that will be based on the differing degrees of design detail in the two phases. The methods described herein combine elements of probabilistic risk assessment (PRA) and deterministic analyses that comprise a risk-informed performance-based safety analysis. This revision to the PSA guide was prepared for the following objectives: (1) To correct factual and typographical errors. (2) To provide additional material suggested from reviews by the Project, the U.S. Department of Energy (DOE), and U.S. Nuclear Regulatory Commission (NRC) Staffs. (3) To update material in accordance with approaches and/or strategies adopted by the Project. In addition, a principal objective for the planned revision was to ensure that the methods and

  1. Prediction of regulatory elements

    DEFF Research Database (Denmark)

    Sandelin, Albin

    2008-01-01

    Finding the regulatory mechanisms responsible for gene expression remains one of the most important challenges for biomedical research. A major focus in cellular biology is to find functional transcription factor binding sites (TFBS) responsible for the regulation of a downstream gene. As wet......-lab methods are time consuming and expensive, it is not realistic to identify TFBS for all uncharacterized genes in the genome by purely experimental means. Computational methods aimed at predicting potential regulatory regions can increase the efficiency of wet-lab experiments significantly. Here, methods...

  2. Nuclear energy - some regulatory aspects

    International Nuclear Information System (INIS)

    Jennekens, Jon.

    1980-03-01

    The nuclear industry is often perceived by the public as being uniquely hazardous. As a consequence, the demands placed upon a nuclear regulatory agency invariably include sorting out the valid from the invalid. As the public becomes better informed, more time should become available for regulating the industry. The Canadian nuclear safety philosophy relies upon fundamental principle and basic criteria which licensees must show they are meeting at all stages in the development of a nuclear facility. In reactors, the concept of defence in depth involves the use of well-qualified personnel, compliance with national and international engineering codes and standards, the separation of process and safety systems, frequent testing of safety systems, redundancy in monitoring, control and initiation systems, multiple barriers against fission product release, and strict enforcement of compliance measurements. The Atomic Energy Control Board is writing a set of licensing guides to cover the whole nuclear fuel cycle; however, these will not lead to the impsition of a 'design by regulation' approach in Canada. (LL)

  3. Design reviews from a regulatory perspective

    International Nuclear Information System (INIS)

    Foster, B.D.

    1991-01-01

    This paper presents views on the role of the licensing engineer in the design process with specific emphasis on design reviews and the automated information management tools that support design reviews. The licensing engineer is seen as an important member of a design review team. The initial focus of the licensing engineer during design reviews is shown to be on ensuring that applicable regulatory requirements are addressed by the design. The utility of an automated tool, such as a commitments management system, to support regulatory requirements identification is discussed. The next responsibility of the licensing engineer is seen as verifying that regulatory requirements are transformed into measurable performance requirements. Performance requirements are shown to provide the basis for developing detailed design review criteria. Licensing engineer input during design reviews is discussed. This input is shown to be especially critical in cases where review findings may impact application of regulatory requirements. The use of automated tools in supporting design reviews is discussed. An information structure is proposed to support design reviews in a regulated environment. This information structure is shown to be useful to activities beyond design reviews. Incorporation of the proposed information structure into the Licensing Support System is proposed

  4. COATING ALTERNATIVES GUIDE (CAGE) USER'S GUIDE

    Science.gov (United States)

    The guide provides instructions for using the Coating Alternatives GuidE (CAGE) software program, version 1.0. It assumes that the user is familiar with the fundamentals of operating an IBM-compatible personal computer (PC) under the Microsoft disk operating system (MS-DOS). CAGE...

  5. Technical guide to criticality alarm system design

    International Nuclear Information System (INIS)

    Greenfield, B.

    2009-01-01

    An instructional manual was created to guide criticality safety engineers through the technical aspects of designing a criticality alarm system (CAS) for Dept. of Energy (DOE) hazard class 1 and 2 facilities. The manual was structured such that it can be used by engineers designing completely new systems and by those who are working with existing facilities. Major design tasks are thoroughly analyzed to provide concise direction for how to complete the analysis. Regulatory and technical performance requirements were both addressed. (authors)

  6. Annual Report 2007. Nuclear Regulatory Authority; Informe Anual 2007. Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across tree parts and seven annexes the activities developed by the organism during 2007. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  7. Annual Report 2008. Nuclear Regulatory Authority; Informe Anual 2008. Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2008. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  8. Annual Report 2009. Nuclear Regulatory Authority; Informe Anual 2009. Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2009. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the environmental monitoring; the occupational surveillance; the training and the public information; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  9. Developing regulatory approaches

    International Nuclear Information System (INIS)

    Axelsson, Lars

    2012-01-01

    Lars Axelsson presented SSM progress on oversight of LMfS/SC since the Chester 1 Workshop in 2007. Current SSM approaches for safety culture oversight include targeted safety management and safety culture inspections, compliance inspections which cover aspects of safety management/safety culture and multi-disciplinary team inspections. Examples of themes for targeted inspections include management of ambiguous operational situations or other weak signals, understanding of and attitudes to Human Performance tools, the Safety Department's role and authority and Leadership for safety. All regulatory activities provide inputs for the SSM yearly safety evaluation of each licensee. A form has been developed to capture safety culture observations from inspections and other interactions with licensees. Analysis will be performed to identify patterns and provide information to support planning of specific Safety Culture activities. Training has been developed for regulatory staff to enhance the quality of regulatory interventions on safety culture. This includes a half-day seminar to provide an overview of safety culture, and a workshop which provides more in-depth discussion on cultural issues and how to capture those during regulatory activities. Future plans include guidance for inspectors, and informal seminars on safety culture with licensees

  10. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1992-07-01

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

  11. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1993-02-01

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

  12. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1989-07-01

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

  13. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1992-11-01

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

  14. Comments on regulatory reform

    International Nuclear Information System (INIS)

    Hendrie, J.M.

    1982-01-01

    Nuclear regulatory reform is divided into two parts. The first part contains all those matters for which new legislation is required. The second part concerns all those matters that are within the power of the Commission under existing statutes. Recommendations are presented

  15. Comments on regulatory reform

    Energy Technology Data Exchange (ETDEWEB)

    Hendrie, J.M.

    1982-01-01

    Nuclear regulatory reform is divided into two parts. The first part contains all those matters for which new legislation is required. The second part concerns all those matters that are within the power of the Commission under existing statutes. Recommendations are presented.

  16. 3 CFR - Regulatory Review

    Science.gov (United States)

    2010-01-01

    ... as a means of promoting regulatory goals. The fundamental principles and structures governing... review. In this time of fundamental transformation, that process—and the principles governing regulation... the Office of Management and Budget (OMB) has reviewed Federal regulations. The purposes of such...

  17. Considering public confidence in developing regulatory programs

    International Nuclear Information System (INIS)

    Collins, S.J.

    2001-01-01

    In the area of public trust and in any investment, planning and strategy are important. While it is accepted in the United States that an essential part of our mission is to leverage our resources to improving Public Confidence this performance goal must be planned for, managed and measured. Similar to our premier performance goal of Maintaining Safety, a strategy must be developed and integrated with our external stake holders but with internal regulatory staff as well. In order to do that, business is to be conducted in an open environment, the basis for regulatory decisions has to be available through public documents and public meetings, communication must be done in clear and consistent terms. (N.C.)

  18. Needs of research for regulatory purposes

    International Nuclear Information System (INIS)

    Wanner, H.

    2010-01-01

    question whether or not it is the duty of the regulator to carry out such complementary work is the subject of controversial discussions. A further issue is the source of the budget from which research for regulatory purposes should be funded since frequent sources of funding are the waste producers and the national budgets. The question of how much regulatory research is needed is difficult to answer on a general basis. It appears obvious that the regulator must achieve the objectives of competence and independence. The research needed for this purpose is the least the regulator must undertake. The verification of key safety issues and the investigation of issues not addressed by the implementer may be considered as optional

  19. Environmental conditions using thermal-hydraulics computer code GOTHIC for beyond design basis external events

    International Nuclear Information System (INIS)

    Pleskunas, R.J.

    2015-01-01

    In response to the Fukushima Dai-ichi beyond design basis accident in March 2011, the Nuclear Regulatory Commission (NRC) issued Order EA-12-049, 'Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies Beyond-Design-Basis-External-Events'. To outline the process to be used by individual licensees to define and implement site-specific diverse and flexible mitigation strategies (FLEX) that reduce the risks associated with beyond design basis conditions, Nuclear Energy Institute document NEI 12-06, 'Diverse and Flexible Coping Strategies (FLEX) Implementation Guide', was issued. A beyond design basis external event (BDBEE) is postulated to cause an Extended Loss of AC Power (ELAP), which will result in a loss of ventilation which has the potential to impact room habitability and equipment operability. During the ELAP, portable FLEX equipment will be used to achieve and maintain safe shutdown, and only a minimal set of instruments and controls will be available. Given these circumstances, analysis is required to determine the environmental conditions in several vital areas of the Nuclear Power Plant. The BDBEE mitigating strategies require certain room environments to be maintained such that they can support the occupancy of personnel and the functionality of equipment located therein, which is required to support the strategies associated with compliance to NRC Order EA-12-049. Three thermal-hydraulic analyses of vital areas during an extended loss of AC power using the GOTHIC computer code will be presented: 1) Safety-related pump and instrument room transient analysis; 2) Control Room transient analysis; and 3) Auxiliary/Control Building transient analysis. GOTHIC (Generation of Thermal-Hydraulic Information for Containment) is a general purpose thermal-hydraulics software package for the analysis of nuclear power plant containments, confinement buildings, and system components. It is a volume/path/heat sink

  20. Nuclear Experts Complete IAEA Follow-up Review of German Regulatory System

    International Nuclear Information System (INIS)

    2011-01-01

    such manner that its safety related activities are not diverted by other ministerial responsibilities, pressures or constraints; The development of regulations and guides should be considered a key function of BMU; BMU should publish Safety Requirements for Nuclear Power Plant document in a timely manner to establish a common and harmonized set of safety requirements and criteria for use by the Laender; and Additional efforts are necessary in the development of the Federal Oversight Manual which provides the basis for the regulatory oversight in Germany. Jim Lyons, IAEA Director for Nuclear Installations Safety, said, ''The IRRS has become an internationally accepted tool for strengthening regulatory activities in IAEA Member States. Germany, in calling for an IRRS Follow-up Mission, has demonstrated their openness and transparency in their commitment to continuous improvement.'' 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, high-level governmental officials, BMU Parliamentary State Secretary, Ms. Ursula Heinen-Esser, and UM BW Minister, Franz Untersteller. Other organisations such as the Reactor Safety Commission (RSK) and the technical support organisation ''Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)'' were also involved. About IRRS Missions IRRS missions are designed to strengthen and enhance the effectiveness of the national nuclear regulatory infrastructure of States, whilst recognizing the ultimate responsibility of each State to ensure safety in this area. This is done through consideration of both regulatory, technical and policy issues, with comparisons against IAEA safety standards and, where appropriate, good practices elsewhere. (IAEA)

  1. External man-induced events in relation to nuclear power plant design. A Safety Guide. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1996-01-01

    In order to take account of lessons learned since the first publication of the NUSS programme was issued, it was decided in 1986 to revise and reissue the Codes and Safety Guides. During the original development of these publications, as well as during the revision process, care was taken to ensure that all Member States, in particular those with active nuclear power programmes, could provide their input. Several independent reviews took place including a final one by the Nuclear Safety Standards Advisory Group (NUSSAG). The revised Codes were approved by the Board of Governors in June 1988. In the revision process new developments in technology and methods of analysis have been incorporated on the basis of international consensus. It is hoped that the revised Codes will be used, and that they will be accepted and respected by Member States as a basis for regulation of the safety of power reactors within the national legal and regulatory framework. 28 refs, 9 figs, 1 tab

  2. Below regulatory concern - or simply exempt?

    International Nuclear Information System (INIS)

    Brodsky, A.

    1991-01-01

    The US Nuclear Regulatory Commission published a policy statement last summer on ''below regulatory concern'' (BRC), which exempted small quantities of radioactive material from regulatory control and would allow the deregulated disposal of some low level waste. The policy drew opposition from several groups. NRC is not planning to revise its BRC policy statement, but wants to develop a concensus on how to implement the policy. Although the Commission's publication of a long needed policy framework for guiding exemption decisions should be welcomed by those of us who have been concerned with making such decisions, there is an urgent need for further consensus building. The policy statement offers only broad guidelines, some of which could be confusing and seem contradictory. The policy statement by itself could further erode public confidence in the NRC's commitment to specific limits of risk, and the ability of its staff to independently evaluate the risks. Another reason why it is appropriate and urgent to embark upon consensus building involving all parties and the public, is that the risks of low level radioactive waste disposal as practiced and proposed in the United States have long been exaggerated in biased reports that receive most media attention. A consensus process needs to be established so that the public can have confidence that its concerns have been properly addressed. (author)

  3. Comparative analysis of regulatory elements in different germin-like ...

    African Journals Online (AJOL)

    It was observed that these promoters have important regulatory elements, which are involved in various important functions. These elements have been compared on the basis of location, copy number, and distributed on positive and negative strands. It was also observed that some of these elements are common and ...

  4. 29 CFR 1990.111 - General statement of regulatory policy.

    Science.gov (United States)

    2010-07-01

    ... CARCINOGENS The Osha Cancer Policy § 1990.111 General statement of regulatory policy. (a) This part establishes the criteria and procedures under which substances will be regulated by OSHA as potential... case-by-case basis in the rulemaking proceedings on individual substances. Any permissible exposure...

  5. Advancing towards commonsense regulation of mixed waste: Regulatory update

    International Nuclear Information System (INIS)

    Porter, C.L.

    1996-01-01

    The author previously presented the basis for regulating mixed waste according to the primary hazard (either chemical or radiological) in order to avoid the inefficient practice of open-quotes dual regulationclose quotes of mixed waste. In addition to covering the technical basis, recommendations were made on how to capitalize upon a window of opportunity for implementation of a open-quotes primary hazards approachclose quotes. Some of those recommendations have been pursued and the resulting advances on the regulatory front are exciting. This paper chronicles those pursuits, presents in capsule form the massive amount of data assembled, and summarizes the changing regulatory framework. The data supports the premise that disposal of stabilized mixed waste in a low-level radioactive waste (LLW) disposal facility is protective of human health and the environment. Based on that premise, proposed regulatory changes, if finalized, will eliminate much of the open-quotes dual regulationclose quotes of mixed waste

  6. User Guide for Automated Wetland Determination Data Sheets

    Science.gov (United States)

    2017-07-25

    are not visible to the user . As a result, it is important that users open a fresh copy of the Excel® file for every use and ensure that macros are...input on the ADS and this user guide. REFERENCES Berkowitz, J. F. 2011a. Regionalizing the Corps of Engineers wetland delineation manual : Process...Wetlands Regulatory Assistance Program ERDC/TN WRAP-17-1 July 2017 Approved for public release; distribution is unlimited. User Guide for

  7. 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

  8. Magnetic Field Analysis of Plasma Guide in Galathea Trimyx

    Directory of Open Access Journals (Sweden)

    Jin Xianji

    2016-01-01

    Full Text Available You Galathea Trimyx is a kind of small size, multipole magnetic confinement devices in controlled thermonuclear fusion. Plasma guide is one of important part in Galathea Trimyx which is responsible for transporting fast and slow plasma bunches ejected from plasma gun. The distribution and uniformity of magnetic field in completed plasma guide is analyzed in detail, including in x -axis direction and in z-axis direction. On the basis, the motion of plasma in the guide is discussed.

  9. Marketing and Distributive Education. Food Marketing Curriculum Guide

    Science.gov (United States)

    Northern Illinois Univ., DeKalb. Dept. of Business Education and Administration Services.

    This document is one of four curriculum guides designed to provide the curriculum coordinator with a basis for planning a comprehensive program in the field of marketing as well as to provide marketing and distributive education teachers with maximum flexibility. Introductory information provides directions for using the guide and information on…

  10. Finance and Credit. Curriculum Guide. Marketing and Distributive Education.

    Science.gov (United States)

    Northern Illinois Univ., DeKalb. Dept. of Business Education and Administration Services.

    Designed to be used with the General Marketing Curriculum Guide (ED 156 860), this guide is intended to provide the curriculum coordinator with a basis for planning a comprehensive program in the field of marketing and to allow marketing and distributive education teacher-coordinators maximum flexibility. It contains job competency sheets in ten…

  11. Genetic basis of chronic pancreatitis

    NARCIS (Netherlands)

    Jansen, JBMJ; Morsche, RT; van Goor, Harry; Drenth, JPH

    2002-01-01

    Background: Pancreatitis has a proven genetic basis in a minority of patients. Methods: Review of the literature on genetics of pancreatitis. Results: Ever since the discovery that in most patients with hereditary pancreatitis a mutation in the gene encoding for cationic trypsinogen (R122H) was

  12. Ellipsoidal basis for isotropic oscillator

    International Nuclear Information System (INIS)

    Kallies, W.; Lukac, I.; Pogosyan, G.S.; Sisakyan, A.N.

    1994-01-01

    The solutions of the Schroedinger equation are derived for the isotropic oscillator potential in the ellipsoidal coordinate system. The explicit expression is obtained for the ellipsoidal integrals of motion through the components of the orbital moment and Demkov's tensor. The explicit form of the ellipsoidal basis is given for the lowest quantum numbers. 10 refs.; 1 tab. (author)

  13. Molecular basis of familial hypercholesterolemia

    NARCIS (Netherlands)

    Bruikman, Caroline S.; Hovingh, Gerard K.; Kastelein, John J. P.

    2017-01-01

    Purpose of review To provide an overview about the molecular basis of familial hypercholesterolemia. Recent findings Familial hypercholesterolemia is a common hereditary cause of premature coronary heart disease. It has been estimated that 1 in every 250 individuals has heterozygous familial

  14. Basis reduction for layered lattices

    NARCIS (Netherlands)

    E.L. Torreão Dassen (Erwin)

    2011-01-01

    htmlabstractWe develop the theory of layered Euclidean spaces and layered lattices. With this new theory certain problems that usually are solved by using classical lattices with a "weighting" gain a new, more natural form. Using the layered lattice basis reduction algorithms introduced here these

  15. Mixtures of truncated basis functions

    DEFF Research Database (Denmark)

    Langseth, Helge; Nielsen, Thomas Dyhre; Rumí, Rafael

    2012-01-01

    In this paper we propose a framework, called mixtures of truncated basis functions (MoTBFs), for representing general hybrid Bayesian networks. The proposed framework generalizes both the mixture of truncated exponentials (MTEs) framework and the mixture of polynomials (MoPs) framework. Similar t...

  16. Marketing and Distributive Education Curriculum Planning Guide.

    Science.gov (United States)

    Northern Illinois Univ., DeKalb. Dept. of Business Education and Administration Services.

    This planning guide in marketing and distributive education is designed to provide the curriculum coordinator and instructor with a basis for planning a comprehensive program in the career field of marketing. Such programs require competencies in sales, sales promotion, buying, transporting, storing, financing, marketing research, and management.…

  17. Structural basis for recognition of S-adenosylhomocysteine by riboswitches

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, A.L.; Heroux, A.; Reyes, F. E.; Batey, R. T.

    2010-11-01

    S-adenosyl-(L)-homocysteine (SAH) riboswitches are regulatory elements found in bacterial mRNAs that up-regulate genes involved in the S-adenosyl-(L)-methionine (SAM) regeneration cycle. To understand the structural basis of SAH-dependent regulation by RNA, we have solved the structure of its metabolite-binding domain in complex with SAH. This structure reveals an unusual pseudoknot topology that creates a shallow groove on the surface of the RNA that binds SAH primarily through interactions with the adenine ring and methionine main chain atoms and discriminates against SAM through a steric mechanism. Chemical probing and calorimetric analysis indicate that the unliganded RNA can access bound-like conformations that are significantly stabilized by SAH to direct folding of the downstream regulatory switch. Strikingly, we find that metabolites bearing an adenine ring, including ATP, bind this aptamer with sufficiently high affinity such that normal intracellular concentrations of these compounds may influence regulation of the riboswitch.

  18. Structural Basis for Recognition of S-adenosylhomocysteine by Riboswitches

    Energy Technology Data Exchange (ETDEWEB)

    A Edwards; F Reyes; A Heroux; R Batey

    2011-12-31

    S-adenosyl-(L)-homocysteine (SAH) riboswitches are regulatory elements found in bacterial mRNAs that up-regulate genes involved in the S-adenosyl-(L)-methionine (SAM) regeneration cycle. To understand the structural basis of SAH-dependent regulation by RNA, we have solved the structure of its metabolite-binding domain in complex with SAH. This structure reveals an unusual pseudoknot topology that creates a shallow groove on the surface of the RNA that binds SAH primarily through interactions with the adenine ring and methionine main chain atoms and discriminates against SAM through a steric mechanism. Chemical probing and calorimetric analysis indicate that the unliganded RNA can access bound-like conformations that are significantly stabilized by SAH to direct folding of the downstream regulatory switch. Strikingly, we find that metabolites bearing an adenine ring, including ATP, bind this aptamer with sufficiently high affinity such that normal intracellular concentrations of these compounds may influence regulation of the riboswitch.

  19. 13 CFR 120.463 - Regulatory accounting-What are SBA's regulatory accounting requirements for SBA Supervised Lenders?

    Science.gov (United States)

    2010-01-01

    ... basis in accordance with Generally Accepted Accounting Principles (GAAP) as promulgated by the Financial Accounting Standards Board (FASB), supplemented by Regulatory Accounting Principles (RAP) as identified by... set forth in FASB Statement of Financial Accounting Standards No. 15, Accounting by Debtors and...

  20. Characteristics of regulatory regimes

    Directory of Open Access Journals (Sweden)

    Noralv Veggeland

    2013-03-01

    Full Text Available The overarching theme of this paper is institutional analysis of basic characteristics of regulatory regimes. The concepts of path dependence and administrative traditions are used throughout. Self-reinforcing or positive feedback processes in political systems represent a basic framework. The empirical point of departure is the EU public procurement directive linked to OECD data concerning use of outsourcing among member states. The question is asked: What has caused the Nordic countries, traditionally not belonging to the Anglo-Saxon market-centred administrative tradition, to be placed so high on the ranking as users of the Market-Type Mechanism (MTM of outsourcing in the public sector vs. in-house provision of services? A thesis is that the reason may be complex, but might be found in an innovative Scandinavian regulatory approach rooted in the Nordic model.

  1. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1993-07-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter. The rules on which final action has been taken since March 31, 1993 are: Repeal of NRC standards of conduct; Fitness-for-duty requirements for licensees who possess, use, or transport Category I material; Training and qualification of nuclear power plant personnel; Monitoring the effectiveness of maintenance at nuclear power plants; Licensing requirements for land disposal of radioactive wastes; and Licensees' announcements of safeguards inspections

  2. Level of evidence for reasonable assurance guides to prediction

    International Nuclear Information System (INIS)

    Schweitzer, D.G.; Sastre, C.

    1987-04-01

    Over the past years, the DOE Contractors have produced a great deal of work that has been extensively reviewed and criticized by the Nuclear Regulatory Commission (NRC), the Materials Review Board (MRB) of the DOE, the Advisory Committee on Reactor Safeguards (ACRS), and the technical support group at Brookhaven National Laboratory (BNL). Common aspects of the reviews and criticisms have provided information on the level of evidence required by the scientific community to defend performance claims. Important indicators of the type of evidence that the NRC will require for favorable decisions of reasonable assurance also can be obtained from 10 CFR 60 and its rationale, from NRC guides and Technical Position papers, from past reviews of the DOE programs by NRC Contractors, and from the use of reasonable assurance by the NRC in its 1984 Waste Confidence Decision. This report describes general concepts related to the acceptability and unacceptability of the level of evidence needed to defend claims with reasonable assurance. The concepts were formulated on the basis of analyses of the NRC position papers, and of common aspects of the reviews and criticisms dealing with compliance demonstration

  3. A flexible regulatory framework

    International Nuclear Information System (INIS)

    Silvennoinen, T.

    2000-01-01

    Regulatory reform of the Finnish electricity market meant opening up potentially competitive parts of the electricity sector to competition and eliminating all unnecessary forms of regulation covering generation, wholesale supply, retail supply, and foreign trade in electricity. New types of control and regulatory mechanisms and institutions were set up for those parts of the electricity industry that were excluded from competition, such as network operations. Network activities now have to be licensed, whereas no licence is needed for generation or supply. A new sector-specific regulatory authority was established in 1995 to coincide with the implementation of the Electricity Market Act, known as the Electricity Market Authority. This is responsible for regulating network activities and retail supply to captive customers. The core function of the authority, which employs some 14 people, is to promote the smooth operation of the Finnish electricity market and to oversee the implementation of the Electricity Market Act and its provisions. Its most important duties are linked to overseeing the process by which network companies price their electricity. As price regulation no longer exists, all the companies in the electricity sector set their tariffs independently, even network companies. The job of controlling the pricing of network services is handed by the Electricity Market Authority, following the principles of competition control. Pricing control takes place ex post - after a pricing system has been adopted by a company and concentrates on individual cases and companies. There is no ex ante system of setting or approving prices and tariffs by the regulator. The tariffs and pricing of network services can be evaluated, however, by both the Electricity Market Authority and the Finnish Competition Authority, which have overlapping powers as regards the pricing of network activities. The Finnish regulatory framework can be described as a system of light

  4. Impact of regulatory science on global public health

    Directory of Open Access Journals (Sweden)

    Meghal Patel

    2012-07-01

    Full Text Available Regulatory science plays a vital role in protecting and promoting global public health by providing the scientific basis for ensuring that food and medical products are safe, properly labeled, and effective. Regulatory science research was first developed for the determination of product safety in the early part of the 20th Century, and continues to support innovation of the processes needed for regulatory policy decisions. Historically, public health laws and regulations were enacted following public health tragedies, and often the research tools and techniques required to execute these laws lagged behind the public health needs. Throughout history, similar public health problems relating to food and pharmaceutical products have occurred in countries around the world, and have usually led to the development of equivalent solutions. For example, most countries require a demonstration of pharmaceutical safety and efficacy prior to marketing these products using approaches that are similar to those initiated in the United States. The globalization of food and medical products has created a shift in regulatory compliance such that gaps in food and medical product safety can generate international problems. Improvements in regulatory research can advance the regulatory paradigm toward a more preventative, proactive framework. These improvements will advance at a greater pace with international collaboration by providing additional resources and new perspectives for approaching and anticipating public health problems. The following is a review of how past public health disasters have shaped the current regulatory landscape, and where innovation can facilitate the shift from reactive policies to proactive policies.

  5. 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”.

  6. The changing regulatory environment

    International Nuclear Information System (INIS)

    Caron, G.

    1999-01-01

    The role and value of regulation in the energy sector was discussed, demonstrating how, despite common perception, regulation is an essential part of Canada's strategy to find and develop new opportunities. The future vision of regulation for industry participants was presented with particular focus on issues related to streamlining the regulatory process. As far as pipelines are concerned, regulatory actions are necessary to facilitate capacity increases and to ensure the line's integrity, safety and environmental record. Furthermore, regulation provides economic solutions where market forces cannot provide them, as for example where business has elements of monopoly. It arbitrates interests of landowners, business, consumers, and environmental groups. It looks for ways to ensure conditions under which competition can flourish. It acts as the guardian of citizens' rights in a democratic society by providing citizens with an opportunity to be heard on the building or expansion of pipelines and associated facilities. As citizens become more and more concerned about their property and the land that surrounds them, citizen involvement in decision making about how industry activity affects their quality of life will become correspondingly more important. Regulatory agencies are committed to facilitate this engagement by flexible hearing procedures and by making use of evolving communication and information technology

  7. Regulatory review of probabilistic safety assessment (PSA) Level 2

    International Nuclear Information System (INIS)

    2001-07-01

    Probabilistic safety assessment (PSA) is increasingly being used as part of the decision making process to assess the level of safety of nuclear power plants. The methodologies in use are maturing and the insights gained from the PSAs are being used along with those from deterministic analysis. Many regulatory authorities consider the current state of the art in PSA to be sufficiently well developed for results to be used centrally in the regulatory decision making process-referred to as risk informed regulation. For these applications to be successful, it will be necessary for the regulatory authority to have a high degree of confidence in the PSA. However, at the 1994 IAEA Technical Committee Meeting on Use of PSA in the Regulatory Process and at the OECD Nuclear Energy Agency Committee for Nuclear Regulatory Activities (CNRA) 'Special Issues' meeting in 1997 on Review Procedures and Criteria for Different Regulatory Applications of PSA, it was recognized that formal regulatory review guidance for PSA did not exist. The senior regulators noted that there was a need to produce some international guidance for reviewing PSAs to establish an agreed basis for assessing whether important technological and methodological issues in PSAs are treated adequately and to verify that conclusions reached are appropriate. In 1997, the IAEA and OECD Nuclear Energy Agency agreed to produce, in cooperation, guidance on Regulatory Review of PSA. This led to the publication of IAEA-TECDOC-1135 on the Regulatory Review of Probabilistic Safety Assessment (PSA) Level 1, which gives advice for the review of Level 1 PSA for initiating events occurring at power plants. This TECDOC extends the coverage to address the regulatory review of Level 2 PSA.These publications are intended to provide guidance to regulatory authorities on how to review the PSA for a nuclear power plant to gain confidence that it has been carried out to an acceptable level of quality so that it can be used as the

  8. A Process Perspective on Regulation: A Grounded Theory Study into Regulatory Practice in Newly Liberalized Network-Based Markets

    NARCIS (Netherlands)

    Ubacht, J.

    The transition from a former monopolistic towards a more competitive market in
    newly liberalized network-based markets raises regulatory issues. National Regulatory Authorities (NRA) face the challenge to deal with these issues in order to guide the transition process. Although this transition

  9. RAF/9/049: Enhancing and Sustaining the National Regulatory Bodies for safety

    International Nuclear Information System (INIS)

    Keter, C.J.

    2017-01-01

    The main objective of this project is to enhance regulatory infrastructure, sustainability and cooperation among national regulatory bodies. This will support strengthening of the existing regulatory framework and capacity building in the region. Self-Assessment using the Self-Assessment Regulatory Infrastructure for Safety (SARIS) was completed on 26th May 2016. Changes made to the legislation is ongoing. The Nuclear Regulatory Bill 2017 is at an advanced stage and about to be tabled to Cabinet. The project objectives shall be addressed under a new project, RAF/9/058 – Improving the Regulatory Framework for the Control of Radiation Sources in Member States. Two major tasks for Kenya to focus include Review of regulations on waste safety, radiation sources and on safety of NPP and advising on drafting of radiation safety guides

  10. Establishment of regulatory framework for the development reactor licensing

    International Nuclear Information System (INIS)

    Jo, Jong C.; Yune, Young G.; Kim, Woong S.; Ahn, Sang K.; Kim, In G.; Kim, Hho J.

    2003-01-01

    With a trend that various types of advanced reactor designs are currently under development worldwide, the Korea Atomic Energy Research Institute has been developing an advanced reactor called ' System-integrated Modular Advanced Reactor (SMART)', which is a small sized integral type pressurized water reactor with a rated thermal power of 330 MW. To demonstrate the safety and the performance of the SMART reactor design, the SMART Research and Development Center has embarked to build a scaled-down pilot plant of SMART, called 'SMART-P' with a rated thermal power of 65 MW. In preparation for the forthcoming applications for both construction permit and operating license of SMART-P in the near future, the Korea Institute of Nuclear Safety is developing a new regulatory framework for licensing review of such a development reactor, which covers establishment of licensing process, identification and resolution of technical and safety issues, development of regulatory evaluation or verification-purpose computer codes and analytical methods, and establishment of design-specific, general design and operating criteria, regulations, and associated regulatory guides. This paper presents the current activities for establishing a regulatory framework for the licensing of a research and development reactor. Discussions are made on the SMART-P development program, the current Korean regulatory framework for reactor licensing, the SMART-P licensing-related issues, and the approach and strategy for developing an effective regulatory framework for the SMART-P licensing

  11. Probing community nurses' professional basis

    DEFF Research Database (Denmark)

    Schaarup, Clara; Pape-Haugaard, Louise; Jensen, Merete Hartun

    2017-01-01

    Complicated and long-lasting wound care of diabetic foot ulcers are moving from specialists in wound care at hospitals towards community nurses without specialist diabetic foot ulcer wound care knowledge. The aim of the study is to elucidate community nurses' professional basis for treating...... diabetic foot ulcers. A situational case study design was adopted in an archetypical Danish community nursing setting. Experience is a crucial component in the community nurses' professional basis for treating diabetic foot ulcers. Peer-to-peer training is the prevailing way to learn about diabetic foot...... ulcer, however, this contributes to the risk of low evidence-based practice. Finally, a frequent behaviour among the community nurses is to consult colleagues before treating the diabetic foot ulcers....

  12. Authorization basis requirements comparison report

    Energy Technology Data Exchange (ETDEWEB)

    Brantley, W.M.

    1997-08-18

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation.

  13. Authorization basis requirements comparison report

    International Nuclear Information System (INIS)

    Brantley, W.M.

    1997-01-01

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation

  14. 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

  15. Hanford Generic Interim Safety Basis

    Energy Technology Data Exchange (ETDEWEB)

    Lavender, J.C.

    1994-09-09

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  16. Hanford Generic Interim Safety Basis

    International Nuclear Information System (INIS)

    Lavender, J.C.

    1994-01-01

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports

  17. Intracellular recovery - basis of hyperfractionation

    International Nuclear Information System (INIS)

    Hagen, U.; Guttenberger, R.; Kummermehr, J.

    1988-01-01

    The radiobiological basis fo a hyperfractionated radiation therapy versus conventional fractionation with respect to therapeutic gain, i.e., improved normal tissue sparing for the same level of tumour cell inactivation, will be presented. Data on the recovery potential of various tissues as well as the kinetics of repair will be given. The problem of incomplete repair with short irradiation intervals will be discussed. (orig.) [de

  18. Defining meridians: a modern basis of understanding.

    Science.gov (United States)

    Longhurst, John C

    2010-06-01

    Acupuncture, one of the primary methods of treatment in traditional Oriental medicine, is based on a system of meridians. Along the meridians lie acupuncture points or acupoints, which are stimulated by needling, pressure or heat to resolve a clinical problem. A number of methods have been used to identify meridians and to explain them anatomically. Thus, tendinomuscular structures, primo-vessels (Bonghan ducts), regions of increased temperature and low skin resistance have been suggested to represent meridians or as methods to identify them. However, none of these methods have met the criteria for a meridian, an entity that, when stimulated by acupuncture can result in clinical improvement. More recently, modern physiologists have put forward the "neural hypothesis" stating that the clinical influence of acupuncture is transmitted primarily through stimulation of sensory nerves that provide signals to the brain, which processes this information and then causes clinical changes associated with treatment. Although additional research is warranted to investigate the role of some of the structures identified, it seems clear that the peripheral and central nervous system can now be considered to be the most rational basis for defining meridians. The meridian maps and associated acupoints located along them are best viewed as road maps that can guide practitioners towards applying acupuncture to achieve optimal clinical results. Copyright 2010 Korean Pharmacopuncture Institute. Published by .. All rights reserved.

  19. Neuronal basis of amblyopia: A review

    Directory of Open Access Journals (Sweden)

    Grigg John

    1996-01-01

    Full Text Available Amblyopia is an acquired defect in vision due to an abnormal visual experience during a sensitive period of visual development. The neuronal basis of amblyopia is the study of the effects of "abnormal" environmental influences on the genetically programmed development of the visual processing system. Visual pathway development commences with ganglion cells forming the optic nerve. The process that guides these neurones initially to the lateral geniculate nucleus (LGN and then onto the visual cortex is genetically programmed. Initially this process is influenced by spontaneously generated impulses and neurotrophic factors. Following birth, visual stimuli modify and refine the genetically programmed process. Exposure to the visual environment includes the risk of abnormal inputs. Abnormal stimuli disrupt the formation of patterned inputs allowing alteration of visual cortical wiring with reduction in ocular dominance columns driven by the abnormal eye. Correction of the abnormal visual input and penalisation of the "normal" input is the mainstay of therapy for amblyopia. Further understanding of the mechanisms involved in the development of a normal visual processing system will allow trialing therapies for amblyopia not responding to occlusion therapy. Levodopa is one agent providing insights into recovery of visual function for short periods in apparently mature visual systems.

  20. Genetic basis of atrial fibrillation

    Directory of Open Access Journals (Sweden)

    Oscar Campuzano

    2016-12-01

    Full Text Available Atrial fibrillation is the most common sustained arrhythmia and remains as one of main challenges in current clinical practice. The disease may be induced secondary to other diseases such as hypertension, valvular heart disease, and heart failure, conferring an increased risk of stroke and sudden death. Epidemiological studies have provided evidence that genetic factors play an important role and up to 30% of clinically diagnosed patients may have a family history of atrial fibrillation. To date, several rare variants have been identified in a wide range of genes associated with ionic channels, calcium handling protein, fibrosis, conduction and inflammation. Important advances in clinical, genetic and molecular basis have been performed over the last decade, improving diagnosis and treatment. However, the genetics of atrial fibrillation is complex and pathophysiological data remains still unraveling. A better understanding of the genetic basis will induce accurate risk stratification and personalized clinical treatment. In this review, we have focused on current genetics basis of atrial fibrillation.

  1. Design basis event consequence analyses for the Yucca Mountain project

    International Nuclear Information System (INIS)

    Orvis, D.D.; Haas, M.N.; Martin, J.H.

    1997-01-01

    Design basis event (DBE) definition and analysis is an ongoing and integrated activity among the design and analysis groups of the Yucca Mountain Project (YMP). DBE's are those that potentially lead to breach of the waste package and waste form (e.g., spent fuel rods) with consequent release of radionuclides to the environment. A Preliminary Hazards Analysis (PHA) provided a systematic screening of external and internal events that were candidate DBE's that will be subjected to analyses for radiological consequences. As preparation, pilot consequence analyses for the repository subsurface and surface facilities have been performed to define the methodology, data requirements, and applicable regulatory limits

  2. ENSI’s regulatory framework strategy; Regelwerksstrategie des ENSI -- Stratégie réglementaire de l’IFSN -- ENSI’s regulatory framework strategy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-03-15

    This short brochure issued by the Swiss Federal Nuclear Safety Inspectorate ENSI defines the organisation’s regulatory framework strategy. Six guiding principles are declared and discussed: Comprehensive harmonisation with relevant international requirements, basing the regulatory framework on existing, tried-and-tested regulations, issuing of its own guidelines only when it is necessary to do so, guidelines to be drawn up transparently and with the involvement of all stakeholders and basing the level of detail of its regulatory framework on hazard potential and risk.

  3. Safety design guides for containment extension for CANDU 9

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

    1996-03-01

    This safety design guide for containment extension describes the containment isolation philosophy and containment extension requirements. The metal extensions and components falling within the scope of ASME Section III are classified in accordance with the CAN/CSA-N285.0 and CAN/CSA-N285.3. The special consideration for the leak monitoring capability, seismic qualification and inspection requirements for containment extensions, etc., are defined in this design guide. In addition, the containment isolation systems are defined and summarized schematically in appendix A. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. (Author) .new

  4. Regulatory experience in nuclear power station decommissioning

    International Nuclear Information System (INIS)

    Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.

    1995-01-01

    In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

  5. CHANGE DETECTION VIA SELECTIVE GUIDED CONTRASTING FILTERS

    Directory of Open Access Journals (Sweden)

    Y. V. Vizilter

    2017-05-01

    Full Text Available Change detection scheme based on guided contrasting was previously proposed. Guided contrasting filter takes two images (test and sample as input and forms the output as filtered version of test image. Such filter preserves the similar details and smooths the non-similar details of test image with respect to sample image. Due to this the difference between test image and its filtered version (difference map could be a basis for robust change detection. Guided contrasting is performed in two steps: at the first step some smoothing operator (SO is applied for elimination of test image details; at the second step all matched details are restored with local contrast proportional to the value of some local similarity coefficient (LSC. The guided contrasting filter was proposed based on local average smoothing as SO and local linear correlation as LSC. In this paper we propose and implement new set of selective guided contrasting filters based on different combinations of various SO and thresholded LSC. Linear average and Gaussian smoothing, nonlinear median filtering, morphological opening and closing are considered as SO. Local linear correlation coefficient, morphological correlation coefficient (MCC, mutual information, mean square MCC and geometrical correlation coefficients are applied as LSC. Thresholding of LSC allows operating with non-normalized LSC and enhancing the selective properties of guided contrasting filters: details are either totally recovered or not recovered at all after the smoothing. These different guided contrasting filters are tested as a part of previously proposed change detection pipeline, which contains following stages: guided contrasting filtering on image pyramid, calculation of difference map, binarization, extraction of change proposals and testing change proposals using local MCC. Experiments on real and simulated image bases demonstrate the applicability of all proposed selective guided contrasting filters. All

  6. Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education safety guide

    CERN Document Server

    2005-01-01

    This Safety Guide provides recommendations and guidance on the > fulfilment of the safety requirements established in Safety Standards > Series No. WS-R-2, Predisposal Management of Radioactive Waste, > Including Decommissioning. It covers the roles and responsibilities of > different bodies involved in the predisposal management of radioactive > waste and in the handling and processing of radioactive material. It > is intended for organizations generating and handling radioactive > waste or handling such waste on a centralized basis for and the > regulatory body responsible for regulating such activities.  > Contents: 1. Introduction; 2. Protection of human health and the > environment; 3. Roles and responsibilities; 4. General safety > considerations; 5. Predisposal management of radioactive waste; 6. > Acceptance of radioactive waste in disposal facilities; 7. Record > keeping and reporting; 8. Management systems; Appendix I: Fault > schedule for safety assessment and environmental impact assessment; > Ap...

  7. Design basis flood for nuclear power plants on river sites

    International Nuclear Information System (INIS)

    1983-01-01

    The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

  8. PARFUME User's Guide

    International Nuclear Information System (INIS)

    Hamman, Kurt

    2010-01-01

    PARFUME, a fuel performance analysis and modeling code, is being developed at the Idaho National Laboratory for evaluating gas reactor coated particle fuel assemblies for prismatic, pebble bed, and plate type fuel geometries. The code is an integrated mechanistic analysis tool that evaluates the thermal, mechanical, and physico-chemical behavior of coated fuel particles (TRISO) and the probability for fuel failure given the particle-to-particle statistical variations in physical dimensions and material properties that arise during the fuel fabrication process. Using a robust finite difference numerical scheme, PARFUME is capable of performing steady state and transient heat transfer and fission product diffusion analyses for the fuel. Written in FORTRAN 90, PARFUME is easy to read, maintain, and modify. Currently, PARFUME is supported only on MS Windows platforms. This document represents the initial version of the PARFUME User Guide, a supplement to the PARFUME Theory and Model Basis Report which describes the theoretical aspects of the code. User information is provided including: (1) code development, (2) capabilities and limitations, (3) installation and execution, (4) user input and output, (5) sample problems, and (6) error messages. In the near future, the INL plans to release a fully benchmarked and validated beta version of PARFUME.

  9. Inspection and enforcement by the regulatory body for nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Code of Practice on Governmental Organization for the Regulation of Nuclear Power Plants, IAEA Safety Series No.50-C-G and should be used in conjunction with that document. The purpose of this Guide is to provide information, guidance and recommendations to assist Member States in (1) establishing and conducting a regulatory inspection programme for nuclear power plants, (2) establishing requirements for the applicant/licensee in regard to regulatory inspection, (3) establishing a system for enforcing compliance with the requirements and decisions of the regulatory body

  10. Schedules for Regulatory Regimes

    International Nuclear Information System (INIS)

    Austvik, Ole Gunnar

    2003-01-01

    The idea of regulating transporters' terms of operations is that if the market itself does not produce optimal outcomes, then it can be mimicked to do so through regulatory and other public instruments. The first-best solution could be a subsidized (publicly owned) enterprise that sets tariffs according to marginal costs. This has been the tradition in many European countries in the aftermath of WW2. Due to lack of innovative pressure on and x-inefficiency in these companies, this solution is today viewed as inferior to the system of regulating independent (privately owned) firms. When the European gas market becomes liberalized, part of the process in many countries is to (partially) privatise the transport utilities. Privatised or not, in a liberalized market, the transport utilities should face an independent authority that overviews their operations not only in technical, but also in economic terms. Under regulation, a ''visible hand'' is introduced to correct the imperfect market's ''invisible hand''. By regulating the framework and conditions for how firms may operate, public authorities seek to achieve what is considered optimal for the society. The incentives and disincentives given for pricing and production should create mechanisms leading to an efficient allocation of resources and ''acceptable'' distribution of income. As part of intervening into firms' behavior, regulation may be introduced to direct the firm to behave in certain ways. The framework and regulatory mechanisms for the market must then be constructed in a way that companies voluntarily produce an amount at a price that gives maximal profits and simultaneously satisfies social goals. The regulations should lead to consistency between the company's desire to maximize profits and the society's desire for maximizing welfare, as in a perfectly competitive market. This is the core of regulatory economics

  11. COLLABORATIVE GUIDE: A REEF MANAGER'S GUIDE TO ...

    Science.gov (United States)

    Innovative strategies to conserve the world's coral reefs are included in a new guide released today by NOAA, and the Australian Great Barrier Reef Marine Park Authority, with author contributions from a variety of international partners from government agencies, non-governmental organizations, and academic institutions. Referred to as A Reef Manager's Guide to Coral Bleaching, the guide will provide coral reef managers with the latest scientific information on the causes of coral bleaching and new management strategies for responding to this significant threat to coral reef ecosystems. Innovative strategies to conserve the world's coral reefs are included in a new guide released today by NOAA, and the Australian Great Barrier Reef Marine Park Authority, with author contributions from a variety of international partners from government agencies, non-governmental organizations, and academic institutions. Dr. Jordan West, of the National Center for Environmental Assessment, was a major contributor to the guide. Referred to as

  12. International regulatory activities

    International Nuclear Information System (INIS)

    Anon.

    2009-01-01

    In this last part is reviewed international regulatory activities and bilateral agreements including two parts: concerning European atomic energy community with European commission proposal for a council directive setting up a community framework for nuclear safety, update of the nuclear illustrative programme in the context of the second strategic energy review, european commission recommendation on criteria for the export of radioactive waste and spent fuel to third countries and a communication on nuclear non-proliferation and the second part in relation with international atomic energy agency with a joint convention on the safety of spent fuel management and on safety of radioactive waste management (third review meeting). (N.C.)

  13. International regulatory activities

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    Different international regulatory activities are presented: recommendation on the protection of the public against exposure to radon in drinking water supplies, amendment to the legislation implementing the regulation on imports of agricultural products originating in third countries following the Chernobyl accident, resolution on the commission green paper towards a European strategy for the security of energy supply, declaration of mandatory nature of the international code for the safe carriage of packaged irradiated nuclear fuel, plutonium and high level radioactive wastes on board ships, adoption of action plan against nuclear terrorism. (N.C.)

  14. Manual on brachytherapy. Incorporating: Applications guide, procedures guide, basics guide

    International Nuclear Information System (INIS)

    1992-01-01

    In addition to a basic guide to the principles of the production of ionizing radiation and to methods of radiation protection and dosimetry, this booklet includes information about radiation protection procedures for brachytherapy

  15. The core to regulatory reform

    International Nuclear Information System (INIS)

    Partridge, J.W. Jr.

    1993-01-01

    Federal Energy Regulatory Commission (FERC) Orders 436, 500, and 636, the Clean Air Act Amendments of 1990, Public Utility Holding Company Act reform, and the 1992 Energy Policy Act all can have significant effects on an LDC's operations. Such changes in an LDC's environments must be balanced by changes within the utility, its marketplace, and its state regulatory environment. The question is where to start. For Columbia Gas Distribution Cos., based in Columbus, OH, the new operating foundation begins with each employee. Internal strength is critical in designing initiatives that meet the needs of the marketplace and are well-received by regulators. Employees must understand not only the regulatory environment in which the LDC operates, but also how their work contributes to a positive regulatory relationship. To achieve this, Columbia initiated the COntinuing Regulatory Education program, or CORE, in 1991. CORE is a regulatory-focused, information-initiative program coordinated by Columbia's Regulatory Policy, Planning, and Government Affairs Department. The CORE programs can take many forms, such as emerging issue discussions, dialogues with regulators and key parties, updates on regulatory fillings, regulatory policy meetings, and formal training classes. The speakers and discussion facilitators can range from human resource department trainers to senior officers, from regulatory department staff members to external experts, or from state commissioners to executives from other LDCs. The goals of CORE initiatives are to: Support a professional level of regulatory expertise through employee participation in well-developed regulatory programs presented by credible experts. Encourage a constructive state regulatory environment founded on communication and cooperation. CORE achieves these goals via five program levels: introductory basics, advanced learning, professional expertise, crossfunctional dialogues, and external idea exchanges

  16. Politically Induced Regulatory Risk and Independent Regulatory Agencies

    OpenAIRE

    Strausz, Roland

    2015-01-01

    Uncertainty in election outcomes generates politically induced regulatory risk. Political parties' risk attitudes towards such risk depend on a fluctuation effect that hurts both parties and an output--expansion effect that benefits at least one party. Notwithstanding the parties' risk attitudes, political parties have incentives to negotiate away all regulatory risk by pre-electoral bargaining. Efficient pre-electoral bargaining outcomes fully eliminate politically induced regulatory risk. P...

  17. Regulatory networks, legal federalism, and multi-level regulatory systems

    OpenAIRE

    Kerber, Wolfgang; Wendel, Julia

    2016-01-01

    Transnational regulatory networks play important roles in multi-level regulatory regimes, as e.g, the European Union. In this paper we analyze the role of regulatory networks from the perspective of the economic theory of legal federalism. Often sophisticated intermediate institutional solutions between pure centralisation and pure decentralisation can help to solve complex tradeoff problems between the benefits and problems of centralised and decentralised solutions. Drawing upon the insight...

  18. Thermodynamic basis for cluster kinetics

    DEFF Research Database (Denmark)

    Hu, Lina; Bian, Xiufang; Qin, Xubo

    2006-01-01

    Due to the inaccessibility of the supercooled region of marginal metallic glasses (MMGs) within the experimental time window, we study the cluster kinetics above the liquidus temperature, Tl, to acquire information on the fragility of the MMG systems. Thermodynamic basis for the stability...... of locally ordered structure in the MMG liquids is discussed in terms of the two-order-parameter model. It is found that the Arrhenius activation energy of clusters, h, is proportional to the chemical mixing enthalpy of alloys, Hchem. Fragility of the MMG forming liquids can be described by the ratio...

  19. OSR encapsulation basis -- 100-KW

    International Nuclear Information System (INIS)

    Meichle, R.H.

    1995-01-01

    The purpose of this report is to provide the basis for a change in the Operations Safety Requirement (OSR) encapsulated fuel storage requirements in the 105 KW fuel storage basin which will permit the handling and storing of encapsulated fuel in canisters which no longer have a water-free space in the top of the canister. The scope of this report is limited to providing the change from the perspective of the safety envelope (bases) of the Safety Analysis Report (SAR) and Operations Safety Requirements (OSR). It does not change the encapsulation process itself

  20. The physical basis of chemistry

    CERN Document Server

    Warren, Warren S

    2000-01-01

    If the text you're using for general chemistry seems to lack sufficient mathematics and physics in its presentation of classical mechanics, molecular structure, and statistics, this complementary science series title may be just what you're looking for. Written for the advanced lower-division undergraduate chemistry course, The Physical Basis of Chemistry, Second Edition, offers students an opportunity to understand and enrich the understanding of physical chemistry with some quantum mechanics, the Boltzmann distribution, and spectroscopy. Posed and answered are questions concerning eve

  1. Assessment of regulatory effectiveness. Peer discussions on regulatory practices

    International Nuclear Information System (INIS)

    1999-09-01

    This report arises from the seventh series of peer discussions on regulatory practices entitled 'Assessment of Regulatory Effectiveness'. The term 'regulatory effectiveness' covers the quality of the work and level of performance of a regulatory body. In this sense, regulatory effectiveness applies to regulatory body activities aimed at preventing safety degradation and ensuring that an acceptable level of safety is being maintained by the regulated operating organizations. In addition, regulatory effectiveness encompasses the promotion of safety improvements, the timely and cost effective performance of regulatory functions in a manner which ensures the confidence of the operating organizations, the general public and the government, and striving for continuous improvements to performance. Senior regulators from 22 Member States participated in two peer group discussions during March and May 1999. The discussions were focused on the elements of an effective regulatory body, possible indicators of regulatory effectiveness and its assessment. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the organizations they belong to, or the International Atomic Energy Agency. In order to protect people and the environment from hazards associated with nuclear facilities, the main objective of a nuclear regulatory body is to ensure that a high level of safety in the nuclear activities under its jurisdiction is achieved, maintained and within the control of operating organizations. Even if it is possible to directly judge objective safety levels at nuclear facilities, such safety levels would not provide an exclusive indicator of regulatory effectiveness. The way the regulatory body ensures the safety of workers and the public and the way it discharges its responsibilities also determine its effectiveness. Hence the

  2. Visualizing guided tours

    DEFF Research Database (Denmark)

    Poulsen, Signe Herbers; Fjord-Larsen, Mads; Hansen, Frank Allan

    This paper identifies several problems with navigating and visualizing guided tours in traditional hypermedia systems. We discuss solutions to these problems, including the representation of guided tours as 3D metro maps with content preview. Issues regarding navigation and disorientation...

  3. Electromagnetic ultrasonic guided waves

    CERN Document Server

    Huang, Songling; Li, Weibin; Wang, Qing

    2016-01-01

    This book introduces the fundamental theory of electromagnetic ultrasonic guided waves, together with its applications. It includes the dispersion characteristics and matching theory of guided waves; the mechanism of production and theoretical model of electromagnetic ultrasonic guided waves; the effect mechanism between guided waves and defects; the simulation method for the entire process of electromagnetic ultrasonic guided wave propagation; electromagnetic ultrasonic thickness measurement; pipeline axial guided wave defect detection; and electromagnetic ultrasonic guided wave detection of gas pipeline cracks. This theory and findings on applications draw on the author’s intensive research over the past eight years. The book can be used for nondestructive testing technology and as an engineering reference work. The specific implementation of the electromagnetic ultrasonic guided wave system presented here will also be of value for other nondestructive test developers.

  4. Apparatus for guiding workpieces

    International Nuclear Information System (INIS)

    Misty, G.C.

    1984-01-01

    Workpieces are guided to the tool by a resiliently mounted support guide which accommodates irregularities in the profiles of the workpieces to maintain the axes of the workpieces in alignment with the centre line of the tool. (author)

  5. Standard Guide for Radiation Protection Program for Decommissioning Operations

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of...

  6. Regulatory good practices relating to monitoring and assessment of ageing nuclear power plants. A compilation of the 1991/92 Peer Group discussion considerations as they relate to operational plants. Working material

    International Nuclear Information System (INIS)

    1993-01-01

    In 1974 the IAEA established a Nuclear Safety Standards (NUSS) programme within which 5 Codes and 55 Safety Guides have been produced in the areas of Governmental Organization, Siting, Design, Operation and Quality Assurance. The NUSS Codes and Guides are a collection of basic and derived requirements for the safety of nuclear power plants with thermal neutron reactors. They have been developed in such a manner as to ensure the broadest international consensus. This broad consensus is one of the reasons for the relatively general wording of the main principles and sometimes causes problems when these principles are applied in the design of nuclear power plants. The requirements, particularly those of the Codes, often need interpretation in specific cases. In many areas national regulations and technical standards are available, but often these leave some questions unanswered and their practical application on a case-by-case basis is necessary. To assist in the application and interpretation of the NUSS Safety Standards and Safety Guides, the preparation of a number of Safety Practices publications has been commenced. Ibis publication is intended to assist regulators and also operating organizations. It is a compilation of the reports of the 1991/92 Peer Group discussions which considered regulatory good practices relating to monitoring and assessment of the ageing of nuclear power plants. Therefore names of participated countries in this documents are those at time of 1991/92 Peer Group discussions. It identifies those common regulatory features which require continuous reinforcement and examples of good regulatory practices that were recommended by senior regulators in the Peer Group discussions. The purpose of this publication is to provide a compilation of the 1991/92 Peer Group discussions relating to operational plant. This document the covers practices in the 20 countries participating in this round of Peer Group discussions. The document is a synopsis of

  7. Regulatory good practices relating to monitoring and assessment of ageing nuclear power plants. A compilation of the 1991/92 Peer Group discussion considerations as they relate to operational plants. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-07-01

    In 1974 the IAEA established a Nuclear Safety Standards (NUSS) programme within which 5 Codes and 55 Safety Guides have been produced in the areas of Governmental Organization, Siting, Design, Operation and Quality Assurance. The NUSS Codes and Guides are a collection of basic and derived requirements for the safety of nuclear power plants with thermal neutron reactors. They have been developed in such a manner as to ensure the broadest international consensus. This broad consensus is one of the reasons for the relatively general wording of the main principles and sometimes causes problems when these principles are applied in the design of nuclear power plants. The requirements, particularly those of the Codes, often need interpretation in specific cases. In many areas national regulations and technical standards are available, but often these leave some questions unanswered and their practical application on a case-by-case basis is necessary. To assist in the application and interpretation of the NUSS Safety Standards and Safety Guides, the preparation of a number of Safety Practices publications has been commenced. Ibis publication is intended to assist regulators and also operating organizations. It is a compilation of the reports of the 1991/92 Peer Group discussions which considered regulatory good practices relating to monitoring and assessment of the ageing of nuclear power plants. Therefore names of participated countries in this documents are those at time of 1991/92 Peer Group discussions. It identifies those common regulatory features which require continuous reinforcement and examples of good regulatory practices that were recommended by senior regulators in the Peer Group discussions. The purpose of this publication is to provide a compilation of the 1991/92 Peer Group discussions relating to operational plant. This document the covers practices in the 20 countries participating in this round of Peer Group discussions. The document is a synopsis of

  8. Upgrading nuclear regulatory infrastructure in Armenia

    International Nuclear Information System (INIS)

    Martirosyan, A.; Amirjanyan, A.; Kacenelenbogen, S.

    2010-01-01

    Armenia is contemplating an upgrade to its national power generation capacity to meet replacement and future energy needs. Unit 2 of ANPP is scheduled for shutdown after replacement power generation capacities are in place. A recent alternative energy study indicates viability of the nuclear option to replace this capacity. Some technology-specific proposals are being considered by the Ministry of Energy of Armenia. It is likely that the reactor technology decision will be made in the not too distant future. The existing reactor continues to be operated in the regulatory framework developed in the Soviet Union and adopted in Armenia. Given the interest in the new reactor, Armenia launched a project to review the existing system of regulation and to bring it into harmony with modern practice in preparation for the new reactor project development. The new regulatory framework will be needed as a basis for any potential tendering process. The US NRC and ANRA have agreed to perform a review and update nuclear legislation and the system of regulation in this area. The first step in this process was to develop an action plan for such program. The action plan describes the overall strategy of ANRA to modify existing or develop new processes and requirements, identifies the major Laws that need to be reviewed given practical legal considerations to construct and operate the reactor and Armenia's international obligations under various conventions. This work included review of existing models of regulation in different countries with 'small' nuclear program, including IAEA recommendations as well as existing legislation in Armenia in this area and development of a strategy for the regulatory model development. In addition, the plan to develop requirements for ANRA staffing and training needs to meet its regulatory obligations under the new reactor development process was developed

  9. Visions of regulatory renewal

    International Nuclear Information System (INIS)

    Edgeworth, A.

    1998-01-01

    The economic contribution of the CEPA (Canadian Energy Pipeline Association) member companies to Canada's trade balance was discussed. CEPA member companies transport 95 per cent of the crude oil and natural gas produced in Canada to domestic and export markets. This represents a total of 5.6 Tcf of gas annually. Half of Canada's natural gas and oil production is exported to U.S. markets. All of these exports are transported by pipeline. CEPA member companies operate 90,000 km of pipeline from British Columbia to Quebec. Expansions are needed as a result of a significant increase in demand for natural gas and crude oil since 1990. Several issues exist for regulatory renewal. They include the need to create a level playing field, the overseeing of tolls and contract renewal terms, changing risk/reward trade-offs, the right to confidentiality of information and price discovery mechanism. The drivers for regulatory reform at Westcoast Energy are the need for pricing flexibility, customers desire for toll certainty, decontracting and opposition to rolled-in expansions for gathering and processing. An overview of Westcoast Energy's negotiated toll settlement, its implications, and the components of Westcoast Energy's 'light handed regulation' (LHR) was presented

  10. The regulatory dynamic

    International Nuclear Information System (INIS)

    Dybwad, C.

    2001-01-01

    An outline of the activities and efforts expanded by the National Energy Board to adjust to the changing natural gas market was provided in this presentation. The author began by defining the role of the National Energy Board in energy markets. It must ensure the adoption of rules and procedures that result in a more competitive and efficient market. Light-handed regulatory techniques are the norm, and the National Energy Board is now committed to facilitating the availability and flow of information so that all parties know where opportunities exist, the terms offered to buy or sell goods and services, their quality and costs. It will specialize in providing new participants with information on the workings of the market, who the players are, the regulatory processes in place, and how, when and where the market can be accessed. The manner in which the Board deals with information was reviewed, providing examples along the way to clarify some points. Some of the documents produced by the National Energy Board are being reviewed with the intent of making them easier to read and understand. Audio streaming over the Internet is another avenue being pursued to ensure individuals can listen in real time to hearings without having to be present in the room. The National Energy Board is also exploring alternative dispute resolution techniques. Consultation with energy market participants represents another facet of these efforts to be more accessible and responsive

  11. The regulatory requirements, design bases, researches and assessments in the field of Ukrainian NPP's seismic safety

    International Nuclear Information System (INIS)

    Mykolaychuk, O.; Mayboroda, O.; Krytskyy, V.; Karnaukhov, O.

    2001-01-01

    State Nuclear Regulatory Authority of Ukraine (SNRA) pays large attention to problem of nuclear installations seismic stability. As a result the seismic design regulatory guides is revised, additional seismic researches of NPP sites are conducted, seismic reassessment of NPP designs were begun. The experts involved address all seismic related factors under close contact with the staff of NPP, design institutes and research organizations. This document takes stock on the situation and the research programs. (author)

  12. Methodology used by the spanish nuclear regulatory body in the radiological impact assessment

    International Nuclear Information System (INIS)

    Diaz de la Cruz, F.

    1979-01-01

    The radiological risk assessment derived from the operation of a nuclear power plant is done in Spain with methods taken basically from the U.S.N.R.C. regulatory guides. This report presents the way followed by the Spanish Regulatory Body in order to arrive to an official decision on the acceptability of a nuclear plant in the different steps of the licensing. (author)

  13. Current products and future plan of regulatory research for risk-informed regulation in Korea

    International Nuclear Information System (INIS)

    Sung, Key Yong; Lee, Chang Ju; Kim, Woong Sik; Kim, Hho Jung

    2003-01-01

    The first phase of a regulatory research project for risk-informed regulation (RIR) and applications (RIA) was finished in March of 2002. Various results that could be useful for preparing Korean RIR system have been developed. One of the remarkable outputs is development of reactor safety goals and acceptance criteria for RIR and RIA in Korea. The Safety Goal has a 4-tier hierarchical structure and each tier has specified goals classified for their usage. Regulatory review guides for probabilistic safety assessment (PSA) including level-1, level-2 and low power and shutdown PSA have been updated by reflecting new information obtained from not only the overseas documents but also experience and insights from regulatory review in Korea. In addition, draft regulatory guides for risk-informed in-service inspection, in-service testing, importance ranking of motor-operated valves, and AOT/STI change of Technical Specifications have been developed for preparing ongoing and future licensing work. Risk-based inspection guides with inspection items selected from a viewpoint of risk importance have been suggested for Korean standard NPPs as well. In the second phase of a research project (April of 2002 to March of 2005), two regulatory research projects on RIR were initiated. One is a study on institutionalization of risk-informed and performance-based regulation. Main topics of this project are evaluation of benefit and characteristics of RIR, development of optimized Korean RIR model, impact analysis for the change of current regulation framework, and suggestion of RIR-related laws and rules. The other is focusing on the development in the areas of a regulatory audit PSA model and regulatory guides for risk monitoring, and application techniques of risk information to the significance determination of plant performance indicators and inspection findings. It is expected that a concrete scheme and detailed regulatory techniques for embodiment of RIR system in Korea will be

  14. Quadratic Hedging of Basis Risk

    Directory of Open Access Journals (Sweden)

    Hardy Hulley

    2015-02-01

    Full Text Available This paper examines a simple basis risk model based on correlated geometric Brownian motions. We apply quadratic criteria to minimize basis risk and hedge in an optimal manner. Initially, we derive the Föllmer–Schweizer decomposition for a European claim. This allows pricing and hedging under the minimal martingale measure, corresponding to the local risk-minimizing strategy. Furthermore, since the mean-variance tradeoff process is deterministic in our setup, the minimal martingale- and variance-optimal martingale measures coincide. Consequently, the mean-variance optimal strategy is easily constructed. Simple pricing and hedging formulae for put and call options are derived in terms of the Black–Scholes formula. Due to market incompleteness, these formulae depend on the drift parameters of the processes. By making a further equilibrium assumption, we derive an approximate hedging formula, which does not require knowledge of these parameters. The hedging strategies are tested using Monte Carlo experiments, and are compared with results achieved using a utility maximization approach.

  15. Pocket Spending Guide

    OpenAIRE

    Poff, Karen

    2015-01-01

    Provides an example for how to set up a pocket spending guide. By filling out the guide and keeping it with you, you can easily see at any time how much money you have available to spend in each category. A pocket spending guide will help you adjust your spending plan to make your money go where you really want it to go.

  16. Managerial Accounting. Study Guide.

    Science.gov (United States)

    Plachta, Leonard E.

    This self-instructional study guide is part of the materials for a college-level programmed course in managerial accounting. The study guide is intended for use by students in conjuction with a separate textbook, Horngren's "Accounting for Management Control: An Introduction," and a workbook, Curry's "Student Guide to Accounting for Management…

  17. Regulatory inspection of BARC facilities

    International Nuclear Information System (INIS)

    Rajdeep; Jayarajan, K.

    2017-01-01

    Nuclear and radiation facilities are sited, constructed, commissioned, operated and decommissioned, in conformity with the current safety standards and codes. Regulatory bodies follow different means to ensure compliance of the standards for the safety of the personnel, the public and the environment. Regulatory Inspection (RI) is one of the important measures employed by regulatory bodies to obtain the safety status of a facility or project and to verify the fulfilment of the conditions stipulated in the consent

  18. [Guided bone regeneration: general survey].

    Science.gov (United States)

    Cosyn, Jan; De Bruyn, Hugo

    2009-01-01

    The principle of 'guided bone regeneration' was first described in 1988 on the basis of animal-experimental data. Six weeks after transmandibular defects had been created and protected by non-resorbable teflonmembranes, complete bone regeneration was found. The technique was based on the selective repopulation of the wound: every infiltration of cells outside the neighbouring bone tissue was prevented by the application of the membrane. Additional animal experiments showed that guided bone regeneration was a viable treatment option for local bone defects surrounding dental implants. Clinical practice, however, showed that premature membrane exposure was a common complication, which was responsible for a tremendous reduction in regenerated bone volume. In addition, a second surgical intervention was always necessary to remove the membrane. As a result, resorbable alternatives were developed. Since these are less rigid, bone fillers are usually used simultaneously. These comprise autogenous bone chips and bone substitutes from allogenic or xenogenic origine. Also alloplastic materials could be used for this purpose. Based on their characteristics this article provides an overview of the biomaterials that could be considered for guided bone regeneration. Specific attention goes to their application in clinical practice.

  19. Electricity and telecommunications regulatory institutions in small and developing countries

    Energy Technology Data Exchange (ETDEWEB)

    Stern, J. [London Business School, London (United Kingdom)

    2000-09-01

    The spread of utility liberalisation and privatisation to middle and low income developing countries raises the problem of whether and how they can establish an effective regulatory capability of whether the supply of regulatory services is likely to be insufficient. The paper presents evidence on the size of electricity regulatory agencies in 24 mainly middle and lower income countries as well as the number of high-level, specialist regulatory staff and the potential resource pool from post-school education. The paper also discusses how far the problem can be alleviated and/or avoided by the use of regulation by contract, regulation by multi-national regulatory agency or contracting-out. The paper concludes that such solutions are unlikely to be generally effective but that informal exchanges of information and pooling of resources between national regulators on a market-driven basis, as seen in Southern Africa and the EU, is a promising option. The paper concludes by pointing to the need to ascertain the minimum required regulatory capability in developing countries as perceived by Governments and potential investors. (author)

  20. National legislative and regulatory activities

    International Nuclear Information System (INIS)

    2012-01-01

    This section gathers the following national legislative and regulatory activities sorted by country: Bulgaria: General legislation; Czech Republic: General legislation; France: General legislation, Regulatory infrastructure and activity; Germany: General legislation; India: Liability and compensation, Organisation and structure; Ireland: Radiation protection, General legislation; Korea (Republic of): Organisation and structure; Lithuania: Regulatory infrastructure and activity, Radioactive waste management, Radiation protection, international cooperation, Nuclear safety; Poland: General legislation; Romania: Environmental protection; Russian Federation: Radioactive waste management; Slovenia: Nuclear safety; Spain: Liability and compensation, Nuclear security; Sweden: Nuclear safety; Turkey: Radiation protection, Regulatory infrastructure and activity, Nuclear safety, Liability and compensation; United States: General legislation