WorldWideScience

Sample records for subject index nrc

  1. NRC comprehensive records disposition schedule

    International Nuclear Information System (INIS)

    1992-03-01

    Title 44 United States Code, ''Public Printing and Documents,'' regulations cited in the General Services Administration's (GSA) ''Federal Information Resources Management Regulations'' (FIRMR), Part 201-9, ''Creation, Maintenance, and Use of Records,'' and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

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

  3. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1994-03-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission staff and its contractors. There are four types of reports included: staff reports, conference reports, contractor reports, and international agreement reports. In addition to the main citations with abstracts, the following are also included: Secondary report number index; Personal author index; Subject index; NRC originating organization indices for staff reports and international agreement reports; NRC contract sponsor index; Contractor index; International organization index; and Licensed facility index

  4. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

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

  5. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index.

  6. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    International Nuclear Information System (INIS)

    1997-02-01

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

  7. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index

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

    International Nuclear Information System (INIS)

    1980-01-01

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

  9. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1992-11-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  10. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1990-03-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, international organization, and licensed facility

  11. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1993-02-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  12. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1991-12-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  13. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1991-06-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  14. Regulatory and technical reports (Abstract index journal)

    International Nuclear Information System (INIS)

    1990-12-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  15. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1991-03-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  16. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1993-08-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  17. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1989-11-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  18. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1990-05-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  19. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1992-06-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  20. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1993-05-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  1. Regulatory and technical reports (Abstract index journal)

    International Nuclear Information System (INIS)

    1989-08-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  2. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1991-11-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  3. Regulatory and technical reports (Abstract Index Journal)

    International Nuclear Information System (INIS)

    1989-07-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  4. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2018-05-01

    conducted the following activities in support of the subject contract: Outreach and Promotion The promotional schedule to advertise the NRC Research...Approved for Public Release; Distribution Unlimited 13. SUPPLEMENTARY NOTES 14. ABSTRACT During this reporting period, the NRC promoted research...Associateship Programs included the following: 1) attendance at meetings of major scientific and engineering professional societies; 2) advertising in

  5. Regulatory and technical reports (Abstract Index Journal): Annual compilation for 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  6. Regulatory and technical reports (abstract index journal): Annual compilation for 1986

    International Nuclear Information System (INIS)

    1987-03-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  7. Regulatory and technical reports (Abstract Index Journal): Compilation for third quarter 1986, July-September

    International Nuclear Information System (INIS)

    1986-11-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, as well as proceedings of conferences and workshops. The entries in the compilation are indexed for access by title and abstract, contractor report number, personal author, subject, NRC organization, contractor, and licensed facility

  8. Regulatory and technical reports (abstract index journal), Compilation for third quarter 1993, July--September

    International Nuclear Information System (INIS)

    1993-11-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  9. NRC study of control room habitability

    International Nuclear Information System (INIS)

    Hayes, J.J. Jr.; Muller, D.R.; Gammill, W.P.

    1985-01-01

    Since 1980, the Advisory Committee on Reactor Safeguards (ACRS) has held several meetings with the NRC staff to discuss the subject of control room habitability. Several meetings between the ACRS and the staff have resulted in ACRS letters that express specific concerns, and the staff has provided responses in reports and meetings. In June of 1983, the NRC Executive Director for Operations directed the Offices of Nuclear Reactor Regulation and Inspection and Enforcement to develop a plan to handle the issues raised by the ACRS and to report to him specific proposed courses of action to respond to the ACRS's concerns. The NRC control room habitability working group has reviewed the subject in such areas as NRR review process, transformation of control room habitability designs to as-built systems, and determination of testing protocol. The group has determined that many of the ACRS concerns and recommendations are well founded, and has recommended actions to be taken to address these as well as other concerns which were raised independent of the ACRS. The review has revealed significant areas where the approach presently utilized in reviews should be altered

  10. Subject/Author Index 1968-1992.

    Science.gov (United States)

    Kupidura, Eva, Ed.; Kupidura, Peter, Ed.

    1993-01-01

    This 25-year index contains annotations of feature articles by subject and by author. Representative subjects include basic education, development education, empowerment, human rights, lifelong education, peace education, popular education, rural development, social/political action, technological advancement, and transformative research. Articles…

  11. Regulatory and technical reports: Abstracts index journal: Compilation for second quarter, April-June 1987

    International Nuclear Information System (INIS)

    1987-08-01

    This journal includes all formal reports in the NUREG Series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstracts, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  12. Regulatory and technical reports (abstract index journal): Compilation for first quarter 1988, January-March

    International Nuclear Information System (INIS)

    1988-06-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  13. Regulatory and technical reports (Abstract Index Journal): Compilation for third quarter, July-September 1987

    International Nuclear Information System (INIS)

    1987-11-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  14. Regulatory and technical reports (Abstract index journal): Compilation for first quarter 1987, January-March

    International Nuclear Information System (INIS)

    1987-05-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  15. Reassessment of the NRC's program for protecting allegers against retaliation

    International Nuclear Information System (INIS)

    1994-01-01

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

  16. Regulatory and technical reports (Abstract Index Journal). Compilation for first quarter 1986, January-March. Volume 11, No. 1

    International Nuclear Information System (INIS)

    1986-04-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission staff and its contractors, as well as conference proceedings. Entries are indexed by contractor report number, personal author, subject, NRC originating organization, NRC contract sponsor, contractor, and licensed facility

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

    International Nuclear Information System (INIS)

    1998-01-01

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

  18. Regulatory and technical reports (abstract index journal): Annual compilation for 1997. Volume 22, Number 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

  19. Regulatory and technical reports (abstract index journal): Annual compilation for 1997. Volume 22, Number 4

    International Nuclear Information System (INIS)

    1998-04-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  20. Regulatory and technical reports (abstract index journal). Compilation for third quarter 1984, July-September. Volume 9, No. 3

    International Nuclear Information System (INIS)

    1984-11-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. These precede the following indexes: Contractor Report Number, Personal Author, Subject, NRC Originating Organization (Staff Reports), NRC Contract Sponsor (Contractor Reports), Contractor, and Licensed Facility

  1. Regulatory and technical reports (abstract index journal). Compilation for second quarter 1986, April-June, 1986. Volume 11, No. 2

    International Nuclear Information System (INIS)

    1986-07-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, as well as proceedings of conferences and workshops. The entries in the compilation are indexed for access by title and abstract, contractor report number, personal author, subject, NRC organization, contractor, and licensed facility

  2. Regulatory and technical reports (abstract index journal). Volume 20, No. 1: First quarterly January--March 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

  3. Regulatory and technical reports (abstract index journal). Volume 20, No. 1: First quarterly January--March 1995

    International Nuclear Information System (INIS)

    1995-07-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

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

  5. Regulatory and technical reports (abstract index journal): Compilation for first quarter 1996, January--March. Volume 21, Number 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

  6. Regulatory and technical reports (abstract index journal): Compilation for first quarter 1996, January--March. Volume 21, Number 1

    International Nuclear Information System (INIS)

    1996-06-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors, proceedings of conferences and workshops, grants, and international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  7. Regulatory and technical reports (abstract index journal): Compilation for second quarter 1997 April--June. Volume 22, Number 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

  8. Regulatory and technical reports: Abstract index journal. Volume 20, No. 3, Compilation for third quarter 1995, July--September

    International Nuclear Information System (INIS)

    1996-01-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  9. Regulatory and technical reports: Abstract index journal. Volume 20, No. 3, Compilation for third quarter 1995, July--September

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

  10. Regulatory and technical reports (abstract index journal): Compilation for second quarter 1997 April - June. Volume 22, Number 2

    International Nuclear Information System (INIS)

    1997-10-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility

  11. Subject-Author Index 989..1009

    Indian Academy of Sciences (India)

    Volume 38 2013. SUBJECT INDEX. 16S rRNA .... reticulum stress-induced neuronal death in rat brain after status ... of intestinal contraction and body size in rodents and rabbits. 391. Brain ...... Trans-generational immune memory. Plant innate ...

  12. Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, July--December 1976

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1977-03-01

    A bibliography of 148 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

  13. Bibliography of reports on research sponsored by the NRC office of nuclear regulatory research, July--December 1977

    International Nuclear Information System (INIS)

    Buchanan, J.R.

    1978-04-01

    A bibliography of 198 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1977 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are arranged first by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography

  14. Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, July--December 1976

    International Nuclear Information System (INIS)

    Buchanan, J.R.

    1977-01-01

    A bibliography of 148 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography

  15. Bibliography of reports on research sponsored by the NRC office of nuclear regulatory research, July--December 1977

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1978-04-01

    A bibliography of 198 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1977 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are arranged first by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

  16. Proceedings (Mathematical Sciences) SUBJECT INDEX

    Indian Academy of Sciences (India)

    R. Narasimhan (Krishtel eMaging) 1461 1996 Oct 15 13:05:22

    SUBJECT INDEX. Abel's summation formula. Analogues of Euler and Poisson summa- tion formulae. 213 ... theorems of Wiener and Lévy on absolutely convergent Fourier series. 179. Brownian motion. Probabilistic representations of solutions to the heat equation. 321. Cesáro matrix. Necessary and sufficient conditions for.

  17. 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

  18. 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

  19. 76 FR 57006 - Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX; NRC Regulation of...

    Science.gov (United States)

    2011-09-15

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Parts 30 and 150 [NRC-2011-0146] Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX; NRC Regulation of Military Operational Radium-226... published for public comment the proposed draft RIS 2011-XX; NRC Regulation of Military Operational Radium...

  20. Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, November 1975--June 1976

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1976-09-30

    A bibliography of 152 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period November 1975 through June 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

  1. Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, November 1975--June 1976

    International Nuclear Information System (INIS)

    Buchanan, J.R.

    1976-01-01

    A bibliography of 152 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period November 1975 through June 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography

  2. 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

  3. 20-Year Subject and Author Index, Volume 1, 1997-Volume 20, 1996; Subject and Author Index, Volume 21, 1997.

    Science.gov (United States)

    Weiler, Robert M.; Pealer, Lisa N.

    1997-01-01

    This index provides readers interested in health behavior, health education, and health promotion ordered access to materials published in Health Values and the American Journal of Health Behavior, 1977-1997. The index includes 115 subject headings and 5 department headings, classifying 918 entries by 1,319 authors and coauthors. (SM)

  4. NRC influences on nuclear training

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1987-01-01

    NRC influences on utility training programs through prescriptive requirements and evaluation of industry self-initiatives are discussed. NRC regulation and industry initiatives are complimentary and in some instances industry initiatives are replacing NRC requirements. Controls and feedback mechanisms designed to enhance positive NRC influences and minimize or eliminate negative influences are discussed. Industry and NRC efforts to reach an acceptable mix between regulator oversight and self-initiatives by the industry are recognized. Problem areas for continued cooperation to enhance training and minimize conflicting signals to industry are discussed. These areas include: requalification examination scope and content, depth of training and examination on emergency procedures; improved learning objectives as the basis for training and examination, and severe accident training

  5. NRC regulation of DOE facilities

    International Nuclear Information System (INIS)

    Buhl, A.R.; Edgar, G.; Silverman, D.; Murley, T.

    1997-01-01

    The US Department of Energy (DOE), its contractors, and the Nuclear Regulatory Commission (NRC) are in for major changes if the DOE follows through on its intentions announced December 20, 1996. The DOE is seeking legislation to establish the NRC as the regulatory agency with jurisdiction over nuclear health, safety, and security at a wide range of DOE facilities. At this stage, it appears that as many as 200 (though not all) DOE facilities would be affected. On March 28, 1997, the NRC officially endorsed taking over the responsibility for regulatory oversight of DOE nuclear facilities as the DOE had proposed, contingent upon adequate funding, staffing resources, and a clear delineation of NRC authority. This article first contrasts the ways in which the NRC and the DOE carry out their basic regulatory functions. Next, it describes the NRC's current authority over DOE facilities and the status of the DOE's initiative to expand that authority. Then, it discusses the basic changes and impacts that can be expected in the regulation of DOE facilities. The article next describes key lessons learned from the recent transition of the GDPs from DOE oversight to NRC regulation and the major regulatory issues that arose in that transition. Finally, some general strategies are suggested for resolving issues likely to arise as the NRC assumes regulatory authority over DOE facilities

  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. 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

  9. 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

  10. 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

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  12. 76 FR 54986 - NRC Enforcement Policy

    Science.gov (United States)

    2011-09-06

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Chapter I [NRC-2011-0209] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Proposed enforcement policy revision; request for comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is soliciting comments from interested...

  13. 76 FR 76192 - NRC Enforcement Policy

    Science.gov (United States)

    2011-12-06

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0273] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Proposed enforcement policy revision; request for comment. SUMMARY: The U.S. Nuclear... licensees, vendors, and contractors), on proposed revisions to the NRC's Enforcement Policy (the Policy) and...

  14. Better Renal Resistive Index Profile in Subjects with Beta Thalassemia Minor .

    Science.gov (United States)

    Basut, Fahrettin; Keşkek, Şakir Özgür; Gülek, Bozkurt

    2018-05-03

    Beta thalassaemia minor is a common genetic disorder without any characteristic symptoms except mild anemia. It is found to be associated with some cardiovascular risk factors such as insulin resistance and diabetes mellitus. The renal resistive index (RRI) is a measure of renal arterial resistance to blood flow. The aim of this study was to evaluate the renal resistive index in subjects with beta thalassaemia minor (BTM). A total of 253 subjects were included in this cross-sectional study. The study group consisted of 148 subjects with BTM and the control group consisted of 105 healthy subjects. Beta thalassaemia minor was diagnosed by complete blood count and hemoglobin electrophoresis. Blood pressure measurement and biochemical tests were performed. Renal resistive index of all subjects was measured using renal Doppler ultrasonography. Subjects with beta thalassemia minor had lower renal resistive indices compared to healthy subjects (0.58 ± 0.04 vs. 0.60 ± 0.06, p = 0.0016). Additionally, the RRI levels of subjects with BTM were correlated with systolic blood pressure (p = 0.017, r = 0.194). In this study, lower renal resistive index was found in subjects with BTM. This may be associated with decreased vascular resistance and blood viscosity in these subjects. ©2018The Author(s). Published by S. Karger AG, Basel.

  15. NRC nuclear waste geochemistry 1983

    International Nuclear Information System (INIS)

    Alexander, D.H.; Birchard, G.F.

    1984-05-01

    The purpose of the meeting was to present results from NRC-sponsored research and to identify regulatory research issues which need to be addressed prior to licensing a high-level waste repository. Important summaries of technical issues and recommendations are included with each paper. The issue reflect areas of technical uncertainty addressed by the NRC Research program in geochemistry. The objectives of the NRC Research Program in geochemistry are to provide a technical basis for waste management rulemaking, to provide the NRC Waste Management Licensing Office with information that can be used to support sound licensing decisions, and to identify investigations that need to be conducted by DOE to support a license application. Individual papers were processed for inclusion in the Energy Data Base

  16. NRC antitrust licensing actions, 1978--1996

    International Nuclear Information System (INIS)

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

    1997-09-01

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

  17. NRC/RSR Data Bank Program description

    International Nuclear Information System (INIS)

    Bankert, S.F.

    1979-01-01

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

  18. Reassessment of NRC's dollar per person-rem conversion factor policy

    International Nuclear Information System (INIS)

    1995-12-01

    The US Nuclear Regulatory Commission (NRC) has completed a review and analysis of its dollar per person-rem conversion factor policy. As a result of this review, the NRC has decided to adopt a $2000 per person-rem conversion factor, subject it to present worth considerations, and limit its scope solely to health effects. This is in contrast to the previous policy and staff practice of using an undiscounted $1000 per person-rem conversion factor that served as a surrogate for all offsite consequences (health and offsite property). The policy shift has been incorporated in ''Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission,'' NUREG/BR-0058, Revision 2, November 1995

  19. NRC Information No. 89-89: Event notification worksheets

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    The NRC ''Event Notification Worksheet,'' NRC Form 361, has been revised to assist the NRC Headquarters Operations Officers in obtaining adequate information for evaluation of significant events reported to the NRC Operations Center. The new forms more accurately reflect the event classifications and the 10 CFR 50.72 categories that must be reported. A copy of the new worksheet is enclosed for your reference. NRC Form 361 can be ordered from the NRC Information and Records Management Branch

  20. NRC antitrust licensing actions, 1978--1996

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-09-01

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

  1. 1996 NRC annual report. Volume 13

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

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

  2. 1996 NRC annual report. Volume 13

    International Nuclear Information System (INIS)

    1997-01-01

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

  3. NRC regulatory information conference: Proceedings

    International Nuclear Information System (INIS)

    1989-09-01

    This volume of the report provides the proceedings from the Nuclear Regulatory Commission (NRC) Regulatory Information Conference that was held at the Mayflower Hotel, Washington, DC, on April 18, 19, and 20, 1989. This conference was held by the NRC and chaired by Dr. Thomas E. Mosley, Director, Office of Nuclear Reactor Regulations (NRR) and coordinated by S. Singh Bajwa, Chief, Technical Assistance Management Section, NRR. There were approximately 550 participants from nine countries at the conference. The countries represented were Canada, England, Italy, Japan, Mexico, Spain, Taiwan, Yugoslavia, and the United States. The NRC staff discussed with nuclear industry its regulatory philosophy and approach and the bases on which they have been established. Furthermore, the NRC staff discussed several initiatives that have been implemented recently and their bases as well as NRC's expectations for new initiatives to further improve safety. The figures contained in Appendix A to the volume correspond to the slides that were shown during the presentations. Volume 2 of this report contains the formal papers that were distributed at the beginning of the Regulatory Information Conference and other information about the conference

  4. 75 FR 60485 - NRC Enforcement Policy Revision

    Science.gov (United States)

    2010-09-30

    ... NUCLEAR REGULATORY COMMISSION [NRC-2008-0497] NRC Enforcement Policy Revision AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement. SUMMARY: The Nuclear Regulatory Commission (NRC or Commission) is publishing a major revision to its Enforcement Policy (Enforcement Policy or Policy) to...

  5. Interactive Computerized Based Training, In Radiation Protection at NRC-Negev

    International Nuclear Information System (INIS)

    Sberlo, E.; Krumbein, H.; Ankri, D.; Ben-Shachar, B.; Laichter, Y.; Weizer, G.; Adorarn, D.

    1999-01-01

    According to the rules of safety at the working places in Israel, all radiation employees in Israel should receive once a year a refreshing course in several areas of safety. At the NRC-Negev there are two kinds of radiation employees: the ''hot area'' employees, who work in an environment of radioactive materials or radiation machines and the ''old area'' employees (all the other employees in the NRC-Negev). One of the main goals of the Department of Human Resources Development and Training at the NRC-Negev was to organize safety refresher courses. All ''hot area'' employees received a training program of two days in safety subjects, each year. The ''cold area'' employees received the same course, each second year. The former training program included several lectures in radiation protection, health physics, biological effects of ionizing radiation, etc., as well as same lectures in industrial safety, fast aid, fee fighting, emergency procedures, etc. The safety refresher courses were given by Rental lectures. There were a lot of disadvantages in these frontal lectures: The lecturers are employees of the NRCN who had to stop their routine work in order to lecture; the lecturers had to carry out identical training for each course for a large group of workers; there was a lack of testing methods or any other certification for the employees. Recently, seven safety courseware were developed by the NRC-Negev and the CET (Centre for Educational Technology), in order to perform these safety refresher courses. The courseware are based on an interactive computerized training including tutorials and quiz. The tutorial is an interactive course in each subject. The employee gets a simple and clear explanation (including pictures). After each Morial there is a quiz which includes 7 American style questions. The first two courseware are for all the employees, the next 4 courseware for the ''hot area'' employees, and the seventh for the ''cold area'' employees (the seventh is a

  6. Assessment of the NRC Enforcement Program

    International Nuclear Information System (INIS)

    Lieberman, J.; Coblentz, L.

    1995-04-01

    On May 12, 1994, the Executive Director for Operations (EDO) established a Review Team composed of senior NRC managers to re-examine the NRC enforcement program. A copy of the Review Team's charter is enclosed as Appendix A. This report presents the Team's assessment. The purpose of this review effort are: (1) to perform an assessment of the NRC's enforcement program to determine whether the defined purposes of the enforcement program are appropriate; (2) to determine whether the NRC's enforcement practices and procedures for issuing enforcement actions are consistent with those purposes; and (3) to provide recommendations on any changes the Review Team believes advisable. In accordance with its charter, the Review Team considered the following principal issues in conducting its assessment of the enforcement program: the balance between providing deterrence and incentives (both positive and negative) for the identification and correction of violations; the appropriateness of NRC sanctions; whether the commission should seek statutory authority to increase the amount of civil penalties; whether the NRC should use different enforcement policies and practices for different licensees (e.g., materials licensees in contrast to power reactors or large fuel facilities); and whether the commission should establish open enforcement conferences as the normal practice

  7. Impacts of NRC programs on state and local governments

    International Nuclear Information System (INIS)

    Nussbaumer, D.A.; Lubenau, J.O.

    1983-12-01

    This document reports the results of an NRC staff examination of the impacts of NRC regulatory programs on State and local governments. Twenty NRC programs are identified. For each, the source of the program (e.g., statutory requirement) and NRC funding availability are described and the impacts upon State and local governments are assessed. Recommendations for NRC monitoring and assessing impacts and for enhancing NRC staff awareness of the impacts are offered

  8. NRC inventory of dams

    International Nuclear Information System (INIS)

    Lear, G.E.; Thompson, O.O.

    1983-01-01

    The NRC Inventory of Dams has been prepared as required by the charter of the NRC Dam Safety Officer. The inventory lists 51 dams associated with nuclear power plant sites and 14 uranium mill tailings dams (licensed by NRC) in the US as of February 1, 1982. Of the 85 listed nuclear power plants (148 units), 26 plants obtain cooling water from impoundments formed by dams. The 51 dams associated with the plants are: located on a plant site (29 dams at 15 plant sites); located off site but provide plant cooling water (18 dams at 11 additional plant sites); and located upstream from a plant (4 dams) - they have been identified as dams whose failure, and ensuing plant flooding, could result in a radiological risk to the public health and safety. The dams that might be considered NRC's responsibility in terms of the federal dam safety program are identified. This group of dams (20 on nuclear power plant sites and 14 uranium mill tailings dams) was obtained by eliminating dams that do not pose a flooding hazard (e.g., submerged dams) and dams that are regulated by another federal agency. The report includes the principal design features of all dams and related useful information

  9. 10 CFR 2.709 - Discovery against NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Discovery against NRC staff. 2.709 Section 2.709 Energy... Rules for Formal Adjudications § 2.709 Discovery against NRC staff. (a)(1) In a proceeding in which the NRC staff is a party, the NRC staff will make available one or more witnesses, designated by the...

  10. Chemical evolution and the origin of life: cumulative keyword subject index 1970-1986

    Science.gov (United States)

    Roy, A. C.; Powers, J. V.; Rummel, J. D. (Principal Investigator)

    1990-01-01

    This cumulative subject index encompasses the subject indexes of the bibliographies on Chemical Evolution and the Origin of Life that were first published in 1970 and have continued through publication of the 1986 bibliography supplement. Early bibliographies focused on experimental and theoretical material dealing directly with the concepts of chemical evolution and the origin of life, excluding the broader areas of exobiology, biological evolution, and geochemistry. In recent years, these broader subject areas have also been incorporated as they appear in literature searches relating to chemical evolution and the origin of life, although direct attempts have not been made to compile all of the citations in these broad areas. The keyword subject indexes have also undergone an analogous change in scope. Compilers of earlier bibliographies used the most specific term available in producing the subject index. Compilers of recent bibliographies have used a number of broad terms relating to the overall subject content of each citation and specific terms where appropriate. The subject indexes of these 17 bibliographies have, in general, been cumulatively compiled exactly as they originally appeared. However, some changes have been made in an attempt to correct errors, combine terms, and provide more meaningful terms.

  11. Nuclear regulation. NRC's security clearance program can be strengthened

    International Nuclear Information System (INIS)

    Fultz, Keith O.; Kruslicky, Mary Ann; Bagnulo, John E.

    1988-12-01

    Because of the national security implications of its programs, the Nuclear Regulatory Commission (NRC) investigates the background of its employees and consultants as well as others to ensure that they are reliable and trustworthy. If the investigation indicates that an employee will not endanger national security, NRC grants a security clearance that allows access to classified information, material, and facilities. NRC also requires periodic checks for some clearance holders to ensure their continued clearance eligibility. The Chairman, Subcommittee on Environment, Energy, and Natural Resources, House Committee on Government Operations, asked GAO to review NRC's personnel security clearance program and assess the procedures that NRC uses to ensure that those who operate nuclear power plants do not pose a threat to the public. The Atomic Energy Act of 1954 requires NRC to conduct background investigations of its employees and consultants as well as others who have access to classified information, material, or facilities. To do this, NRC established a personnel security clearance program. Under NRC policies, a security clearance is granted after the Office of Personnel Management (OPM) or the Federal Bureau of Investigation checks the background of those applying for an NRC clearance. NRC also periodically reassesses the integrity of those holding the highest level clearance. NRC employees, consultants, contractors, and licensees as well as other federal employees hold approximately 10,600 NRC clearances. NRC does not grant clearances to commercial nuclear utility employees unless they require access to classified information or special nuclear material. However, the utilities have voluntarily established screening programs to ensure that their employees do not pose a threat to nuclear plants. NRC faces a dilemma when it hires new employees. Although its policy calls for new hires to be cleared before they start work, the security clearance process takes so long

  12. Research Studies Index. Authors and Subjects. Volume 1 through Volume 43 (1929-1975).

    Science.gov (United States)

    Drazan, Joseph, Comp.; Scott, Paula, Comp.

    This volume contains author and subject indexes for volumes 1 through 43 (1929-1975) of "Research Studies," a scholarly, multi-disciplinary quarterly published at Washington State University. Each author index entry includes the title, volume, and inclusive pagination of the article. The subject index is a keyword-out-of-context…

  13. NRC comprehensive records disposition schedule

    International Nuclear Information System (INIS)

    1983-05-01

    Effective January 1, 1982, NRC will institute records retention and disposal practives in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 24 which apply to housekeeping or facilitative records. NRCS-I applies to records common to all or most NRC offices; NRCS-II applies to program records as found in the various offices of the Commission, Atomic Safety and Licensing Board Panel, and the Atomic Safety and Licensing Appeal Panel; NRCS-III applies to records accumulated by the Advisory Committee on Reactor Safeguards; and NRCS-IV applies to records accumulated in the various NRC offices under the Executive Director for Operations. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

  14. NRC/RSR data bank program

    International Nuclear Information System (INIS)

    Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) has established at the Idaho National Engineering Laboratory (INEL) the NRC/Reactor Safety Research (RSR) Data Bank Program. The program is under the direction of EG and G Idaho, Inc., and is intended to provide the means of collecting, processing, and making available experimental data from the many water reactor safety research programs. The NRC/RSR Data Bank Program collects qualified engineering data on a prioritized basis from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users. The NRC/RSR Data Bank specializes in water reactor safety experimental data, but it has a number of other scientific applications where large amounts of numeric data are or will be available. As an example of size, a single water reactor safety test may generate 10 million data words. Future examples of the use of a data bank might be in gathering data on low head hydraulics, solar projects, and liquid metal reactor safety data

  15. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1991-12-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facilities throughout the country for the third quarter of 1991

  16. 78 FR 5838 - NRC Enforcement Policy

    Science.gov (United States)

    2013-01-28

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0014] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Policy revision; issuance and request for comments. SUMMARY: The U.S. Nuclear Regulatory... Nuclear Regulatory Commission Enforcement Policy,'' December 30, 2009 (ADAMS Accession No. ML093200520);(2...

  17. NRC overview: Repository QA

    International Nuclear Information System (INIS)

    Kennedy, J.E.

    1988-01-01

    The US Department of Energy (DOE) is on the threshold of an extensive program for characterizing Yucca Mountain in Nevada to determine if it is a suitable site for the permanent disposal of high-level nuclear waste. Earlier this year, the DOE published the Consultation Draft Site Characterization Plan for the Nevada site, which describes in some detail the studies that need to be performed to determine if the site is acceptable. In the near future, the final site characterization plan (SCP) is expected to be issued and large-scale site characterization activities to begin. The data and analyses that will result from the execution of that plan are expected to be the primary basis for the license application to the US Nuclear Regulatory Commission (NRC). Because of the importance of these data and analyses in the assessment of the suitability of the site and in the demonstration of that suitability in the NRC licensing process, the NRC requires in 10CFR60 that site characterization be performed under a quality assurance (QA) program. The QA program is designed to provide confidence that data are valid, retrievable, and reproducible. The documentation produced by the program will form an important part of the record on which the suitability of the site is judged in licensing. In addition, because the NRC staff can review only a selected portion of the data collected, the staff will need to rely on the system of controls in the DOE QA program

  18. Proceedings of the 23rd DOE/NRC nuclear air cleaning conference

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-02-01

    The report contains the papers presented at the 23rd DOE/NRC Nuclear Air Cleaning Conference and the associated discussions. Major topics are: (1) nuclear air cleaning codes, (2) nuclear waste, (3) filters and filtration, (4) effluent stack monitoring, (5) gas processing, (6) adsorption, (7) air treatment systems, (8) source terms and accident analysis, and (9) fuel reprocessing. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  19. 10 CFR 51.40 - Consultation with NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Consultation with NRC staff. 51.40 Section 51.40 Energy....40 Consultation with NRC staff. (a) A prospective applicant or petitioner for rulemaking is encouraged to confer with NRC staff as early as possible in its planning process before submitting...

  20. S¯adhan¯a Vol. 28, 2003 Subject Index

    Indian Academy of Sciences (India)

    R. Narasimhan (Krishtel eMaging) 1461 1996 Oct 15 13:05:22

    Porous carbon. 335. Active-R ... Aluminium oxide. Controlled wear of vitrified abrasive materials .... Machining and metrology systems for free- form laser printer ... Subject Index. Flow and fracture ... Grain/interphase boundary sliding. Thermally ...

  1. ITAAC Development for APR1400 NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Jin Kwon; Kim, Myoung Ki

    2013-01-01

    ITAAC (Inspections, Tests, Analyses and Acceptance Criteria) is essential document for Design Certification, which is certified by NRC and ruled as the Appendix of the 10 CFR Part 52. Approximately 870 ITAAC items were selected for APR1400 Design Certification to be submitted to NRC. In this paper, the code and standard related to ITAAC and process of ITACC development are discussed to seek the way to complete the best ITAAC to get the Design Certification of APR1400 from NRC through the lessons learned from other competitive applicants. For saving the time and manpower to complete ITAAC of APR1400 NRC DC and reduction of the RAIs (Request Additional Information) from NRC, we took advantage of the lessons learned from the competitive designs like US-APWR and AP1000 based on KNGR ITAAC. Finally new and different ITAAC from ITAAC of KNGR was developed for APR1400 DC from NRC. RG 1.206 and SRPs were applied first in Korea to the APR1400 DCD preparation. For testability and acceptability check, ITAAC V and V table was completed by the system designers. APR1400 DCD will be submitted by the end of September this year and we hope that NRC issues lees RAIs on ITAAC document

  2. Proceedings of the 21st DOE/NRC nuclear air cleaning conference

    International Nuclear Information System (INIS)

    First, M.W.

    1991-02-01

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

  3. NRC/RSR Data Bank Program

    International Nuclear Information System (INIS)

    Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to provide a means of collecting, processing, and making available experimental data from the many domestic and foreign water reactor safety research programs. The NRC/RSR Data Bank Program collects qualified engineering data from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users. The program is designed to be user oriented to minimize the effort required to obtain and manipulate data of interest. The data bank concept and structure embodied in the data bank processing system are applicable to any program where large quantities of scientific (numeric) data are generated and require compiling, storage, and accessing in order to be collected and made available to multiple users. 3 figures

  4. Public meeting on radiation safety for industrial radiographerss: remarks, questions and answers at five NRC regional meetings

    International Nuclear Information System (INIS)

    1978-11-01

    Over the past several years thenumber of radiation overexposures experienced in the radiography industry has been higher than for any other single group of NRC licensees. To inform radiography licensees of NRC's concern fo these recurring overexposure incidents, NRC staff representatives met with licensees in a series of five regional meetings. At these meetings the staff presented prepared remarks and answered questions on NRC regulations and operations. The main purposes of the meetings were to express NRC's concern for the high incidence of overexposures, and to open a line of communication between the NRC and radiography licensees in an effort to achieve the common goal of improved radiation safety. The remarks presented by the staff and subjects discussed at these meetings included: the purpose, scope, findings and goals of the NRC inspection program; ways and means of incorporating safety into radiography operations; and case histories of overexposure incidents, with highlights of the causes and possible preventions. At each of the regional meetings the staff received a request for a copy of the prepared remarks and a consolidation of the questions and answers that were discussed. This document includes that information, and a copy is being provided to each organizaion or firm attending the regional meetings. Requests for other copies should be made in accordance with the directions printed inside the front cover of this document

  5. IRIS and the National Research Council (NRC)

    Science.gov (United States)

    Since the 2011 National Academies’ National Research Council (NRC) review of the IRIS Program's assessment of Formaldehyde, EPA and NRC have had an ongoing relationship into the improvements of developing the IRIS Assessments.

  6. Public citizen slams NRC on nuclear inspections

    International Nuclear Information System (INIS)

    Newman, P.

    1993-01-01

    Charging the Nuclear Regulatory Commission with open-quotes abandoning tough regulation of the nuclear power industry,close quotes Public Citizen's Critical Mass Energy Project on Wednesday released a report asserting that NRC is shielding sensitive internal nuclear industry self-evaluations from public scrutiny. Based on their review of 56 Institute of Nuclear Power Operations reports and evaluations and comparing these to the NRC's Systematic Assessment of Licensee Performance reports for the same plants, it was concluded that the NRC failed to address issues raised in all eight areas evaluated by the INPO reports

  7. The NRC perspective on low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    Thompson, H.L. Jr.; Knapp, M.R.

    1987-01-01

    This paper describes the Nuclear Regulatory Commission's (NRC) actions in response to the Low-Level Radioactive Waste Policy Amendments Act (the Act) and NRC's assistance to States and Compacts working to discharge their responsibilities under the Act. Three of NRC's accomplishments which respond explicitly to direction in the Act are highlighted. These are: development of the capability of expedited handling of petitions addressing wastes below regulatory concern (BRC); development of capability to review and process an application within fifteen months; and development of guidance on alternatives to shallow land burial. Certain NRC efforts concerning special topics related to the Act as well as NRC efforts to assist States and Compacts are summarized

  8. Safeguards at NRC licensed facilities: Are we doing enough

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

    Safeguards at the Nuclear Regulatory Commission (NRC) facilities are discussed in this paper. The NRC is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

  9. 10 CFR 2.1202 - Authority and role of NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of NRC staff. 2.1202 Section 2.1202... ORDERS Informal Hearing Procedures for NRC Adjudications § 2.1202 Authority and role of NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings in its...

  10. Directory of certificates of compliance for radioactive materials packages; Summary Report of NRC Approved Packages

    International Nuclear Information System (INIS)

    1980-12-01

    This directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material using these packagings must be in accordance with the provisions of 49 CFR 173.393a and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them--that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

  11. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.J.

    1980-07-01

    The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

  12. NRC perspectives on fuel cycle and safeguards

    International Nuclear Information System (INIS)

    Chapman, K.R.

    1976-01-01

    This paper discusses NRC's mandate in the field of safeguards and the thoughts of NRC on other newly emerging policy considerations. The status of some of the current issues facing the nuclear community and the regulatory staff in particular is touched on

  13. Regulatory and technical reports: compilation for third quarter 1982 July-September

    International Nuclear Information System (INIS)

    1982-11-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. This precede the following indexes: Contractor Report Number Index; Personal Author Index; Subject Index; NRC Originating Organization Index (Staff Reports); NRC Contract Sponsor Index (Contractor Reports); Contractor Index; and Licensed Facility Index

  14. NRC/RSR Data Bank Program

    International Nuclear Information System (INIS)

    Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program at the Idaho National Engineering Laboratory (INEL). The program provides the means of collecting, storing, and making available experimental data from the many water reactor safety research programs in the United States and other countries. The program collects qualified engineering data on a prioritized basis from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users

  15. NRC methods for evaluation of industry training

    International Nuclear Information System (INIS)

    Morisseau, D.S.; Koontz, J.L.; Persensky, J.J.

    1987-01-01

    On March 20, 1985, the Nuclear Regulatory Commission published the Policy Statement on Training and Qualification. The Policy Statement endorsed the INPO-managed Training Accreditation Program because it encompasses the five elements of performance-based training. This paper described the multiple methods that the NRC is using to monitor industry efforts to improve training and implement the NRC Policy Statement on Training and Qualification. The results of the evaluation of industry training improvement programs will be reviewed by the Commissioners in April 1987 to determine the nature of continuing NRC policy and programs for ensuring effective training for the US nuclear industry

  16. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2016-04-01

    8. Curcumin : A Prototype Anti-inflammatory Therapeutic for Burn Pain and Wound Healing. Burn and Trauma Research Workgroup. BAMMC Burn Center 2014 9...from Burkholderia infection in mice. 9) PUBLICATIONS AND PAPERS RESULTING FROM NRC ASSOCIATESHIP RESEARCH Provide complete citations: author(s), title...PUBLICATIONS AND PAPERS RESULTING FROM NRC ASSOCIATESHIP RESEARCH Provide complete citations: author(s), title, full name of journal, volume number, page

  17. Significant NRC Enforcement Actions

    Data.gov (United States)

    Nuclear Regulatory Commission — This dataset provides a list of Nuclear Regulartory Commission (NRC) issued significant enforcement actions. These actions, referred to as "escalated", are issued by...

  18. 10 CFR 2.1505 - Role of the NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Role of the NRC staff. 2.1505 Section 2.1505 Energy... Legislative Hearings § 2.1505 Role of the NRC staff. The NRC staff shall be available to answer any Commission or presiding officer's questions on staff-prepared documents, provide additional information or...

  19. NRC/DAE reactor safety research Data Bank

    International Nuclear Information System (INIS)

    Laats, E.T.

    1982-01-01

    In 1976, the United States Nuclear Regulatory Commission (NRC) established the NRC/Division of Accident Evaluation (DAE) Data Bank to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. This program has since grown from the conceptual stage to a useful, usable service for computer code development, code assessment, and experimentation groups in meeting the needs of the nuclear industry. Data from 20 facilities are now processed and permanently stored in the Data Bank, which utilizes the Control Data Corporation (CDC) CYBER 176 computer system located at the Idaho National Engineering Laboratory (INEL). New data and data sources are continually being added to the Data Bank. In addition to providing data storage and access software, the Data Bank program supplies data entry, documentation, and training and advisory services to users and the NRC. Management of the NRC/DAE Data Bank is provided by EG and G Idaho, Inc

  20. 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

  1. Development of the NRC's Human Performance Investigation Process (HPIP)

    International Nuclear Information System (INIS)

    Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

    1993-10-01

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

  2. NRC systematic evaluation program: seismic review

    International Nuclear Information System (INIS)

    Levin, H.A.

    1980-01-01

    The NRC Systematic Evaluation Program is currently making an assessment of the seismic design safety of 11 older nuclear power plant facilities. The general review philosophy and review criteria relative to seismic input, structural response, and equipment functionability are presented, including the rationale for the development of these guidelines considering the significant evolution of seismic design criteria since these plants were originally licensed. Technical approaches thought more realistic in light of current knowledge are utilized. Initial findings for plants designed to early seismic design procedures suggest that with minor exceptions, these plants possess adequate seismic design margins when evaluated against the intent of current criteria. However, seismic qualification of electrical equipment has been identified as a subject which requires more in-depth evaluation

  3. Comparisons of ANSI standards cited in the NRC standard review plan, NUREG-0800 and related documents

    International Nuclear Information System (INIS)

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

    1995-11-01

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

  4. Comparisons of ASTM standards cited in the NRC standard review plan, NUREG-0800 and related documents

    International Nuclear Information System (INIS)

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

    1995-10-01

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

  5. Insulin Secretion and Risk for Future Diabetes in Subjects with a Nonpositive Insulinogenic Index

    Directory of Open Access Journals (Sweden)

    Daisuke Aono

    2018-01-01

    Full Text Available Aim. To characterize subjects with a nonpositive insulinogenic index and longitudinally observe changes in their glucose tolerance. Subjects and Methods. A historical cohort study was conducted using data from the medical checkups of public school workers. Indices of insulin secretion and insulin sensitivity derived from oral glucose tolerance test (OGTT and the incidences of diabetes and impaired glucose tolerance (IGT were compared among subgroups of subjects with different insulinogenic index (change in insulin/change in glucose over the first 30 min on the OGTT. Results. Of the 1464 nondiabetic subjects at baseline, 72 (4.9% subjects had a nonpositive insulinogenic index: 42 of those subjects had a nonpositive glucose response (ΔGlu0–30 ≤ 0 and 30 had a nonpositive insulin response (ΔIns0–30 ≤ 0. Compared with subjects who had normal glucose tolerance (NGT with insulinogenic index ≥ 0.4, subjects with a nonpositive glucose response had a higher first-phase Stumvoll and lower incidences of diabetes and IGT based on a log-rank test (p<0.05, whereas subjects with a nonpositive insulin response had lower indices of insulin secretion and a higher incidence of diabetes (p<0.05. Conclusions. These results demonstrate that in the first 30 min on the OGTT, subjects with a nonpositive insulinogenic index due to a nonpositive glucose response (ΔGlu0–30 ≤ 0 had a lower risk for future diabetes and that subjects with nonpositive insulin response (ΔIns0–30 ≤ 0 had a higher risk for future one.

  6. Report to Congress on NRC emergency communications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-09-01

    The accident at Three Mile Island highlighted the need for improved communications among the NRC and other organizations which respond to such emergencies. This report summarizes the communication problems identified by several major review groups after the accident, the status of corrective actions, and NRC plans to improve communications still further. (author)

  7. NRC comprehensive records disposition schedule

    International Nuclear Information System (INIS)

    1982-07-01

    Effective January 1, 1982, NRC will institute records retention and disposal practices in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 22 which apply to housekeeping or facilitative records. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

  8. NRC perspective and experience on valve testing

    International Nuclear Information System (INIS)

    Eapen, P.K.

    1990-01-01

    Testing of safety related valves is one of the major activities at commercial nuclear power plants. In addition to Technical Specification, valve testing is required in 10 CFR 50.55a and 10 CFR 50 Appendix J. NRC inspectors (both resident and specialists) spend a considerable amount of time in following the valve test activities as part of their routine business. In the past, depending on a licensee's organizational structure, a valve could be tested more than three times to verify conformance with Technical Specifications, 10 CFR 50.55a, and 10 CFR 50 Appendix J. The regulatory reviewers were isolated from each other. Licensee test personnel were also not communicating among themselves. As a result, NRC inspectors found that certain valves in the IST program were inadequately tested. The typical licensee response was to say that this valve is exempted from testing under Appendix J. Others would say that the technical specification does not require fast closure of a valve in question. In addition to the above, the inspectors had to deal with exemption requests that were not dispositioned by the NRC. In the seventies there was a gentlemen's agreement to allow the licensee to do the testing in accordance with the exception, without waiting for the NRC approval. Needless to say when the new NRC inspection procedure was issued in March 1989 for implementation, the Regional inspectors had extremely difficult time to cope with the gray areas of valve testing. In August 1987, NRC Region I was reorganized and the special test program section was established to perform inspections in the IST area. This section was chartered to optimize resources and develop a meaningful inspection plan. The perspectives and insights used in the development of a detailed inspection plan is discussed below

  9. NRC comprehensive records disposition schedule. Revision 3

    International Nuclear Information System (INIS)

    1998-02-01

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

  10. NRC comprehensive records disposition schedule. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

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

  11. 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

  12. NRC's object-oriented simulator instructor station

    International Nuclear Information System (INIS)

    Griffin, J.I.; Griffin, J.P.

    1995-06-01

    As part of a comprehensive simulator upgrade program, the simulator computer systems associated with the Nuclear Regulatory Commission's (NRC) nuclear power plant simulators were replaced. Because the original instructor stations for two of the simulators were dependent on the original computer equipment, it was necessary to develop and implement new instructor stations. This report describes the Macintosh-based Instructor Stations developed by NRC engineers for the General Electric (GE) and Babcock and Wilcox (B and W) simulators

  13. NRC Regulatory Agenda: Quarterly report, October--December 1988

    International Nuclear Information System (INIS)

    1989-01-01

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

  14. Development of the NRC's Human Performance Investigation Process (HPIP)

    International Nuclear Information System (INIS)

    Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

    1993-10-01

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume I is a concise description of the need for the human performance investigation process, the process' components, the methods used to develop the process, the methods proposed to test the process, and conclusions on the process' usefulness

  15. Development of the NRC's Human Performance Investigation Process (HPIP)

    International Nuclear Information System (INIS)

    Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

    1993-10-01

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

  16. 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

  17. 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

  18. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.

    1982-02-01

    This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

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

    International Nuclear Information System (INIS)

    Walker, Stuart

    2008-01-01

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

  20. 10 CFR 2.1316 - Authority and role of NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of NRC staff. 2.1316 Section 2.1316... ORDERS Procedures for Hearings on License Transfer Applications § 2.1316 Authority and role of NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings...

  1. NRC performance assessment program

    International Nuclear Information System (INIS)

    Coplan, S.M.

    1986-01-01

    The U.S. Nuclear Regulatory Commission's (NRC) performance assessment program includes the development of guidance to the U.S. Department of Energy (DOE) on preparation of a license application and on conducting the studies to support a license application. The nature of the licensing requirements of 10 CFR Part 60 create a need for performance assessments by the DOE. The NRC and DOE staffs each have specific roles in assuring the adequacy of those assessments. Performance allocation is an approach for determining what testing and analysis will be needed during site characterization to assure that an adequate data base is available to support the necessary performance assessments. From the standpoint of establishing is implementable methodology, the most challenging performance assessment needed for licensing is the one that will be used to determine compliance with the U.S. Environmental Protection Agency's (EPA) containment requirement

  2. Recent NRC research activities addressing valve and pump issues

    Energy Technology Data Exchange (ETDEWEB)

    Morrison, D.L.

    1996-12-01

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

  3. NRC Regulatory Agenda: Quarterly report, July-September 1987

    International Nuclear Information System (INIS)

    1987-11-01

    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

  4. NRC regulatory agenda: Quarterly report, April--June 1988

    International Nuclear Information System (INIS)

    1988-08-01

    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

  5. Safety Second: the NRC and America's nuclear power plants

    International Nuclear Information System (INIS)

    Adato, M.; MacKenzie, J.; Pollard, R.; Weiss, E.

    1987-01-01

    In 1975, Congress created the Nuclear Regulatory Commission (NRC). Its primary responsibility was to be the regulation of the nuclear power industry in order to maintain public health and safety. On March 28, 1979, in the worst commercial nuclear accident in US history, the plant at Three Mile Island began to leak radioactive material. How was Three Mile Island possible? Where was the NRC? This analysis by the Union of Concerned Scientists (UCS) of the NRC's first decade, points specifically to the factors that contributed to the accident at Three Mile Island. The NRC, created as a watchdog of the nuclear power industry, suffers from problems of mindset, says the UCS. The commission's problems are political, not technical; it repeatedly ranks special interests above the interest of public safety. This book critiques the NRC's performance in four specific areas. It charges that the agency has avoided tackling the most pervasive safety issues; has limited public participation in decision making and power plant licensing; has failed to enforce safety standards or conduct adequate regulation investigations; and, finally, has maintained a fraternal relationship with the industry it was created to regulate, serving as its advocate rather than it adversary. The final chapter offers recommendations for agency improvement that must be met if the NRC is to fulfill its responsibility for safety first

  6. Status report on NRC's current below regulatory concern activities

    International Nuclear Information System (INIS)

    Dragonette, K.S.

    1988-01-01

    The concept of below regulatory concern (BRC) is not new to the Nuclear Regulatory Commission (NRC) or its predecessor agency, the Atomic Energy Commission. The regulations and licensing decisions have involved limited and de facto decisions on BRC since the beginning. For example, consumer products containing radioactive materials have been approved for distribution to persons exempt from licensing for some time and procedures for survey and release of equipment have traditionally been a part of many licensees' radiation safety programs. However, these actions have generally been ad hoc decisions in response to specific needs and have not been necessarily consistent. The need to deal with this regulatory matter has been receiving attention from both Congress and the NRC Commissioners. NRC response has grown from addressing specific waste streams, to generic rulemaking for wastes, and finally to efforts to develop a broad generic BRC policy. Section 10 of the Low-Level Radioactive Waste Policy Amendments Act of 1985 addressed NRC actions on specific waste streams. In response, NRC issued guidance on rulemaking petitions for specific wastes. NRC also issued an advance notice of proposed rulemaking indicating consideration of Commission initiated regulations to address BRC wastes in a generic manner. The Commissioners have directed staff to develop an umbrella policy for all agency decisions concerning levels of risk or dose that do not require government regulation

  7. On indexes and subject matter of “global competitiveness”

    Directory of Open Access Journals (Sweden)

    A. V. Korotkov

    2017-01-01

    Full Text Available The aim of the research is to analyze the subject matter of a country’s competitiveness and to characterize statistical indexes of competitiveness known in the international practice from the perspective of a more elaborated theory of market competition. This aim follows from the identified problems. First, there are no generally accepted interpretation and joint understanding of competition and competitiveness at country level. Even the international organizations giving estimations of global competitiveness disagree on definitions of competitiveness. Secondly, there is no relation to the theory of market competition in the available source materials on competitiveness of the country without original methodology. Thirdly, well-known statistical indexes of global competitiveness do not have enough theoretical justification and differ in sets of factors. All this highlights the incompleteness of the methodology and methodological support of studying competitiveness at country level.Materials and methods. The research is based on the methodology of statistics, economic theory and marketing. The authors followed the basic principle of statistical methodology – requirement of continuous combination of qualitative and quantitative analysis, when the research begins and ends with qualitative analysis. A most important section of statistical methodology is widely used – construction of statistical indexes. In the course of the analysis, a method of statistical classifications is applied. A significant role in the present research is given to the method of generalizing and analogue method, realizing that related terms should mean similar and almost similar contents. Modeling of competition and competitiveness is widely used in the present research, which made it possible to develop a logical model of competition following from the competition theory.Results. Based on the definitions’ survey the analysis of the subject matter of global

  8. REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

    International Nuclear Information System (INIS)

    Markman, D.W.

    1999-01-01

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

  9. NRC concerns about steam generator tube U-bend failures

    International Nuclear Information System (INIS)

    Dillon, R.L.

    1981-01-01

    This paper concerns itself with genralized NRC regulatory policy regarding SGT failures and staff reports and opinions which may tend to influence the developing policy specific to U-bend failures. The most significant analysis at hand in predicting NRC policy on SGT U-bend failures is Marsh's Evaluation of Steam Generator Tube Rupture Events. Marsh sets out to describe and analyze the five steam generator tube ruptures that are known to NRC. All have occurred in the period 1975 to 1980

  10. NRC - regulator of nuclear safety

    International Nuclear Information System (INIS)

    1997-01-01

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

  11. NRC closing remarks

    International Nuclear Information System (INIS)

    Coffman, F.

    1994-01-01

    This section contains the edited transcript of the NRC closing remarks made by Mr. Franklin Coffman (Chief, Human Factors Branch, Office of Nuclear Regulatory Research) and Dr. Cecil Thomas (Deputy Director, Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation). This editing consisted of minimal editing to correct grammar and remove extraneous references to microphone volume, etc

  12. Overview of the NRC performance monitoring program

    International Nuclear Information System (INIS)

    Jordan, E.L.

    1987-01-01

    In response to the accident at Three Mile Island, the NRC developed the Systematic Assessment of Licensee Performance (SALP) Program to aid in the identification of those licensees that were more likely than others to have safety problems and to provide a rational basis for allocation of inspection resources. The NRC also has an ongoing program of screening and evaluating operating reactor event reports on a daily basis for promptly identifying safety problems. Although the SALP and event report evaluation programs have been successful in identifying potential performance problems, a concern developed recently about the adequacy and timeliness of NRC programs to detect poor or declining performance. The performance indicator program as approved by the commission is in the implementation phase. The program is expected to undergo refinements as new indicators are developed and experience is gained in the use of indicators

  13. NRC Regulatory Agenda quarterly report, July--September 1993

    International Nuclear Information System (INIS)

    1993-10-01

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

  14. U.S. NRC training for research and training reactor inspectors

    International Nuclear Information System (INIS)

    Sandquist, G.M.; Kunze, J.F.

    2011-01-01

    Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

  15. Staged licensing: An essential element of the NRC's revised regulations

    International Nuclear Information System (INIS)

    Echols, F.S.

    1997-01-01

    Over the past several years, Congress has directed the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and the Environmental Protection Agency (EPA) to abandon their efforts to assess an array of potential candidate geologic repository sites for the permanent disposal of spent nuclear reactor fuel and high level radioactive waste, to develop generally applicable requirements for licensing geologic repositories, and to develop generally applicable radiation protection standards for geologic repositories, and instead to focus their efforts to determine whether a single site located at Yucca Mountain, Nevada can be developed as a geologic repository which providing reasonable assurance that public health and safety and the environment will be adequately protected. If the Yucca Mountain site is found to be suitable for development as a geologic repository, then at each stage of development DOE will have to provide the NRC with progressively more detailed information regarding repository design and long-term performance. NRC regulations reflect the fact that it will not be until the repository has been operated for a number of years that the NRC will be able to make a final determination as to long-term repository performance. Nevertheless, the NRC will be able to allow DOE to construct and operate a repository, provided that the NRC believes that the documented results of existing studies, together with the anticipated results from continuing and future studies, will enable the NRC to make a final determination that it has reasonable assurance that the repository system's long-term performance will not cause undue risk to the public. Thus, in its efforts to revise its current regulations to assure that the technical criteria are specifically applicable to the Yucca Mountain site, the NRC should also make sure that it preserves and clarifies the concept of staged repository development

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

    International Nuclear Information System (INIS)

    1998-02-01

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

  17. US NRC research on the integrity of piping in nuclear reactor primary systems

    International Nuclear Information System (INIS)

    Serpan, C.Z. Jr.

    1983-01-01

    This paper has attempted to provide a ''snapshot'' of the activities underway in NRC on the subject of LWR piping integrity as of the summer and fall of 1983. The paper is necessarily vague on certain topics of policy because they are either under review or are under development and the outcome cannot be accurately forecast at this time. Particularly in the area of BWR pipe cracking, events are very rapid so that positions and actions described in this paper may well be obsolete by the time it is published. Nevertheless, the activities and positions are as accurate as possible at the time of writing. Certainly the longer-range aspects of the research program represent the current direction and intent of NRC; nevertheless, as results come in and actions occur in the licensing and regulation arena of operating reactors, the emphasis of the research programs will necessarily shift to accommodate them so as to remain as relevant as possible. Thus, this paper is useful to show the intentions of NRC in the area of research for LWR piping, and it is also useful to document the status of the regulations on piping for which the research is being performed. (orig.)

  18. Initial experience with the NRC significance determination process

    International Nuclear Information System (INIS)

    Madison, A.L.

    2001-01-01

    The U.S. Nuclear Regulatory Commission (NRC) has revamped its inspection, assessment, and enforcement programs for commercial nuclear power plants. The new oversight process uses more objective, timely, and safety-significant criteria in assessing performance, while seeking to more effectively and efficiently regulate the industry. The NRC tested the new process at thirteen reactors at nine sites across the country on a pilot basis in 1999 to identify what things worked well and what improvements were called for before beginning Initial Implementation at all US nuclear power plants on April 2, 2000. After a year of experience has been gained with the new oversight process at all US plants, the NRC anticipates making further improvements based on this wider experience. (author)

  19. Initial experience with the NRC significance determination process

    Energy Technology Data Exchange (ETDEWEB)

    Madison, A.L. [Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission (United States)

    2001-07-01

    The U.S. Nuclear Regulatory Commission (NRC) has revamped its inspection, assessment, and enforcement programs for commercial nuclear power plants. The new oversight process uses more objective, timely, and safety-significant criteria in assessing performance, while seeking to more effectively and efficiently regulate the industry. The NRC tested the new process at thirteen reactors at nine sites across the country on a pilot basis in 1999 to identify what things worked well and what improvements were called for before beginning Initial Implementation at all US nuclear power plants on April 2, 2000. After a year of experience has been gained with the new oversight process at all US plants, the NRC anticipates making further improvements based on this wider experience. (author)

  20. Coupled processes in NRC high-level waste research

    International Nuclear Information System (INIS)

    Costanzi, F.A.

    1987-01-01

    The author discusses NRC research effort in support of evaluating license applications for disposal of nuclear waste and for promulgating regulations and issuing guidance documents on nuclear waste management. In order to do this they fund research activities at a number of laboratories, academic institutions, and commercial organizations. One of our research efforts is the coupled processes study. This paper discusses interest in coupled processes and describes the target areas of research efforts over the next few years. The specific research activities relate to the performance objectives of NRC's high-level waste (HLW) regulation and the U.S. Environmental Protection Agency (EPA) HLW standard. The general objective of the research program is to ensure the NRC has a sufficient independent technical base to make sound regulatory decisions

  1. Proceedings of the 24. DOE/NRC nuclear air cleaning and treatment conference

    International Nuclear Information System (INIS)

    First, M.W.

    1997-08-01

    This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC, (9) decommissioning, (10) computer modeling applications, (11) adsorption, (12) iodine treatment, (13) filters, and (14) codes and standards for filters and adsorbers. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

  2. Proceedings of the 24. DOE/NRC nuclear air cleaning and treatment conference

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-08-01

    This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC, (9) decommissioning, (10) computer modeling applications, (11) adsorption, (12) iodine treatment, (13) filters, and (14) codes and standards for filters and adsorbers. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  3. Safeguards at NRC licensed facilities: Are we doing enough

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

    The Nuclear Regulatory Commission is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

  4. 10 CFR 2.1403 - Authority and role of the NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of the NRC staff. 2.1403 Section 2.1403... ORDERS Expedited Proceedings with Oral Hearings § 2.1403 Authority and role of the NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings in its own...

  5. NRC Information Notice No. 93-25: Electrical penetration assembly degradation

    International Nuclear Information System (INIS)

    Grimes, B.K.

    1993-01-01

    In July 1987 and in October 1989, the licensee for the Trojan Nuclear Plant, the Portland and General Electric Company, reported problems with containment air leakage through its Bunker-Ramo electrical penetration assembly seals. In July and August 1991, the NRC inspected the use of containment electrical penetration assembly seals at Trojan and concluded that the licensee had not established an effective program for trending and evaluating electrical penetration assembly seal leakage. On October 28, 1991, while the plant was in a refueling outage, the licensee reported to the NRC that in the originally installed electrical penetration assemblies, the seal (polyurethane) and lubricant (Celvacen or Glycerin) materials were inappropriate for the application. The licensee concluded that these materials may cause seal degradation and that the seals may become degraded if subjected to design basis accident conditions for moisture or temperature. The licensee replaced the electrical penetration assembly seal with an environmentally qualified ethylene propylene rubber seal and added a silicone rubber backup O-ring to the outer face of each electrical penetration assembly module. The licensee subsequently replaced all the Bunker-Ramo electrical penetration assemblies with Conax assemblies

  6. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1992-06-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated by the NRC in cooperation with participating states to provide continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. Ambient radiation levels result from naturally occurring radionuclides present in the soil, cosmic radiation constantly bombarding the earth from outer space, and the contribution, if any, from the monitored facilities and other man-made sources. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the first quarter of 1992. All radiation measurements are made using small, passive detectors called thermoluminescent dosimeters (TLDs), which provide a quantitative measurement of the radiation levels in the area in which they are placed. Each site is monitored by arranging approximately 40 to 50 TLD stations in two concentric rings extending to about five miles from the facility. All TLD stations are outside the site boundary of the facility

  7. Overview of NRC PRA research program

    International Nuclear Information System (INIS)

    Cunningham, M.A.; Drouin, M.T.; Ramey-Smith, A.M.; VanderMolen, M.T.

    1997-01-01

    The NRC's research program in probabilistic risk analysis includes a set of closely-related elements, from basic research to regulatory applications. The elements of this program are as follows: (1) Development and demonstration of methods and advanced models and tools for use by the NRC staff and others performing risk assessments; (2) Support to agency staff on risk analysis and statistics issues; (3) Reviews of risk assessments submitted by licensees in support of regulatory applications, including the IPEs and IPEEEs. Each of these elements is discussed in the paper, providing highlights of work within an element, and, where appropriate, describing important support and feedback mechanisms among elements

  8. NRC perspectives on the digital system review process

    International Nuclear Information System (INIS)

    Mauck, J.L.

    1998-01-01

    Since about 1988, the USNRC has been involved in the review of digital retrofits to instrumentation and control (I and C) systems in nuclear power plants. Initially, this involvement was limited but with the advent of the 1990s, NRC involvement has become greater because of increased interest in and application of digital systems as existing analog systems become obsolete. Criteria for the design of such systems to ensure safety has been promulgated over the years and the USNRC has been actively involved both nationally and internationally with this effort. With the publication of the Zion Eagle 21 Safety Evaluation Report in 1992, Generic Letter 95-02 in April 1995 which endorses EPRI guidance document TR-102348 on digital upgrades and the latest revision to Regulatory Guide 1.152 which endorses IEEE 7.4.3.2-1993; a basic digital system review process was established. The NRC supplemented this review process with recently issued inspection procedures for use by NRC inspectors when conducting onsite reviews of digital modifications. In addition, the NRC undertook a major effort to codify the above guidance and the experience gained from digital system reviews of both operating plant modifications and advanced reactor designs, over these years into a revision to Standard Review Plan, (SRP), NUREG-0800, Chapter 7, Instrumentation and Control. This SRP revision was published in June, 1997, and included new SRP sections, branch technical positions and six new regulatory guides endorsing IEEE standards on software quality. The NRC staff believes that a stable digital system review process is now in place. (author)

  9. SUBJECT AND AUTHOR INDEXS

    Directory of Open Access Journals (Sweden)

    IJBE Volume 1

    2015-09-01

    Full Text Available SUBJECT INDEX IJBE VOLUME 1EPA, 1Agrotourism, 148AHP, 148balance scorecard, 63batik tulis Rolla Junior, 23Broiler, 90business model canvas, 137business performance,32capital structure, 81cashew industry,158CHAID,106CLI,42coal transportation service,63company’s characteristics, 81competitive advantage, 12competitive strategy, 127consumer satisfaction, 51CSI, 42customer loyalty, 42customer satisfaction,42decision of visitors, 72development strategy, 23development,158entrepreneurship, 32Feasibility studies, 90FEM, 81gap analysis, 1Indonesia Stock Exchange, 177Indosat, 137investor,177Kawah Putih, 72kedai sop durian lodaya (KSDL,51klassen typology, 96leading sector, 96less cash society, 137liquidity ratio, 165location quotient, 96logistic regression, 115market, 177marketing development strategy, 148Marketing mix, 72mobile payment, 137modern and Traditional cage, 90multiple regression analyse,165multiple regression, 177net working capital, 165organic tofu product, 115Padang, 106paired comparison, 63partnership, 1, 32Pecking Order Theory, 81PLS, 81Portfolio, 96power, 32product quality, 51profitability ratio, 165Prol Tape Primadona, 127purchase decision, 115purchase intention, 51purchasing interest,115QSPM, 23, 127refilled drinking water, 106seed,1segmentation, 106SEM, 42, 51service quality, 51SMEs, 96specialty coffee, 12stock,177strategic diagnosis,137strategy, 158Sukorambi Botanic Garden, 148SWOT, 23, 127, 148, 158SWOT-AHP, 12tourists,72UD. Primadona, 127value chain, 12VRIO,12 AUTHOR INDEX IJBE VOLUME 1Adiningsih, Kartika Puspitasari,42Aknesia, Vharessa,12Amalia, Firda Rachma,90Andati, Trias, 177Anggraeni, Lukytawati,23Asriani,158Daryanto, Arief,12, 90Djamaludin, MD., 42Djohar, Setiadi,96Fachrodji, Achmad,72Fahmi, Idqan,1, 63, 127Fasyni, Awisal,106Hubeis, Musa,148Iskandar, Dodi,51Juanda, Bambang, 165Kirbrandoko, 12, 106, 115Lumbantoruan, Dewi Margareth,96Maulana, TB Nur Ahmad,81Muksin, 148Mukti Soleh, Cecep,63Najib, Mukhamad,106Noor, Tajudin,81

  10. NRC performance indicator program

    International Nuclear Information System (INIS)

    Singh, R.N.

    1987-01-01

    The performance indicator development work of the US Nuclear Regulatory Commission (NRC) interoffice task group involved several major activities that included selection of candidate indicators for a trial program, data collection and review, validation of the trial indicators, display method development, interactions with the industry, and selection of an optimum set of indicators for the program. After evaluating 27 potential indicators against certain ideal attributes, the task group selected 17 for the trial program. The pertinent data for these indicators were then collected from 50 plants at 30 sites. The validation of the indicators consisted of two primary processes: logical validity and statistical analysis. The six indicators currently in the program are scrams, safety system actuations, significant events, safety system failures, forced outage rate, and equipment forced outages per 100 critical hours. A report containing data on the six performance indicators and some supplemental information is issued on a quarterly basis. The NRC staff is also working on refinements of existing indicators and development of additional indicators as directed by the commission

  11. Current NRC activities related to MQA

    Energy Technology Data Exchange (ETDEWEB)

    Trottier, C.A.; Nellis, D.O. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-12-31

    The U.S. Nuclear Regulatory Commission`s (NRC`s) interest in measurement quality assurance (MQA) goes back to before 1963, when the Atomic Energy Commission (AEC) published a notice in the Federal Register concerning the need for establishing a Film Dosimetry Calibration Laboratory, and also provided a set of minimum performance criteria to be used by the laboratory in evaluating film dosimetry services used by licensees. The proposed laboratory was not established, but in 1967 the AEC contracted with Battelle`s Pacific Northwest Laboratory (PNL) to evaluate film dosimeter performance criteria and provide a basis for establishing a Film Dosimetry Calibration Laboratory if the study showed that it was needed. Then, in 1973, the Conference of Radiation Control Program Directors (CRCPD), concerned with the state of dosimetry processing and the lack of adequate standards, recommended that the National Bureau of Standards (NBS) direct a performance testing program for personnel dosimetry processing services. Later, in 1976, NRC asked PNL to conduct a study to evaluate the four existing performance standards for personnel dosimetry processing. One result of this study was that the HPSSC standard, which later became ANSI N13.11, was recommended as the standard for use in a national dosimetry processing program. The rest is common knowledge. With the support of numerous other federal agencies and the CRCPD, NRC published a regulation, effective in 1988, that required all processors of personnel dosimeters be accredited under the National Voluntary Laboratory Accreditation Program (NVLAP), operated by the NBS, which is now called the National Institute of Standards and Technology (NIST). At present, there are 75 dosimetry processing laboratories accredited under NVLAP. NRC has also been involved in extremity dosimeters, health physics survey instruments, bioassay measurements, electronic personnel dosimeters, and environmental monitoring around nuclear power plants.

  12. NRC program of inspection and enforcement

    International Nuclear Information System (INIS)

    LeDoux, J.C.; Rehfuss, C.

    1978-01-01

    The Nuclear Regulatory Commission (NRC) regulates civilian uses of nuclear materials to ensure the protection of the public health and safety and the environment. The Office of Inspection and Enforcement (IE) develops and implements the inspection, investigation, and enforcement programs for the NRC. The IE conducts inspection programs for reactors under construction and in operation, nuclear industry vendors, fuel facilities and users of nuclear materials, and all aspects of the safeguarding of facilities and materials. Recently the IE began implementing a program that will place inspectors on site at nuclear power reactors and will provide for national appraisal of licensee performance and for an evaluation of the effectiveness of the inspection programs

  13. NRC perspective on alternative disposal methods

    International Nuclear Information System (INIS)

    Pittiglio, C.L.; Tokar, M.

    1987-01-01

    In this paper is discussed an NRC staff strategy for the development of technical criteria and procedures for the licensing of various alternatives for disposal of low-level radioactive waste. Steps taken by the staff to identify viable alternative disposal methods and to comply with the requirements of the Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 are also discussed. The strategy proposed by the NRC staff is to focus efforts in FY 87 on alternative concepts that incorporate concrete materials with soil or rock cover (e.g., below ground vaults and earth-mounded concrete bunkers), which several State and State Compacts have identified as preferred disposal options. While the NRC staff believes that other options, such as above ground vaults and mined cavities, are workable and licensable, the staff also believes, for reasons addressed in the paper, that it is in the best interest of the industry and the public to encourage standardization and to focus limited resources on a manageable number of alternative options. Therefore, guidance on above ground vaults, which are susceptible to long-term materials degradation due to climatological effects, and mined cavities, which represent a significant departure from the current experience base for low-level radioactive waste disposal, will receive minimal attention. 6 references

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

    International Nuclear Information System (INIS)

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

    1995-11-01

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

  15. Performance testing of dosimetry processors, status of NRC rulemaking for improved personnel dosimetry processing, and some beta dosimetry and instrumentation problems observed by NRC regional inspectors

    International Nuclear Information System (INIS)

    Dennis, N.A.; Kinneman, J.D.; Costello, F.M.; White, J.R.; Nimitz, R.L.

    1983-01-01

    Early dosimetry processor performance studies conducted between 1967 and 1979 by several different investigators indicated that a significant percentage of personnel dosimetry processors may not be performing with a reasonable degree of accuracy. Results of voluntary performance testing of US personnel dosimetry processors against the final Health Physics Society Standard, Criteria for Testing Personnel Dosimetry Performance by the University of Michigan for the Nuclear Regulatory Commission (NRC) will be summarized with emphasis on processor performance in radiation categories involving beta particles and beta particles and photon mixtures. The current status of the NRC's regulatory program for improved personnel dosimetry processing will be reviewed. The NRC is proposing amendments to its regulations, 10 CFR Part 20, that would require its licensees to utilize specified personnel dosimetry services from processors accredited by the National Voluntary Laboratory Accreditation Program of the National Bureau of Standards. Details of the development and schedule for implementation of the program will be highlighted. Finally, selected beta dosimetry and beta instrumentation problems observed by NRC Regional Staff during inspections of NRC licensed facilities will be discussed

  16. The NRC measurement verification program

    International Nuclear Information System (INIS)

    Pham, T.N.; Ong, L.D.Y.

    1995-01-01

    A perspective is presented on the US Nuclear Regulatory Commission (NRC) approach for effectively monitoring the measurement methods and directly testing the capability and performance of licensee measurement systems. A main objective in material control and accounting (MC and A) inspection activities is to assure the accuracy and precision of the accounting system and the absence of potential process anomalies through overall accountability. The primary means of verification remains the NRC random sampling during routine safeguards inspections. This involves the independent testing of licensee measurement performance with statistical sampling plans for physical inventories, item control, and auditing. A prospective cost-effective alternative overcheck is also discussed in terms of an externally coordinated sample exchange or ''round robin'' program among participating fuel cycle facilities in order to verify the quality of measurement systems, i.e., to assure that analytical measurement results are free of bias

  17. The roles of NRC research in risk-informed, performance-based regulation

    International Nuclear Information System (INIS)

    Morrison, D.L.; Murphy, J.A.; Hodges, M.W.; Cunningham, M.A.; Drouin, M.T.; Ramey-Smith, A.M.; VanderMolen, H.

    1997-01-01

    The NRC is expanding the use of probabilistic risk analysis (PRA) throughout the spectrum of its regulatory activities. The NRC's research program in PRA supports this expansion in a number of ways, from performing basic research to developing guidance for regulatory applications. The author provides an overview of the NRC's PRA research program, then focuses on two key activities - the review of individual plant examinations, and the development of guidance for use of PRA in reactor regulation

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

    International Nuclear Information System (INIS)

    Ultroska, D.

    1984-01-01

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

  19. NRC as referee (reactor licensing following the Three Mile Island accident)

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1984-01-01

    In this article, the NRC's licensing director reports on the progress made by US utilities in complying with the key regulations stemming from the Three Mile Island accident. Over 130 items must be improved at more than 65 reactors. The actions taken by France in response to its own analysis of the accident are discussed. New NRC requirements with regard to operational safety, design, and emergency-response capability are outlined. Nearly all the training, or software, items in Nureg-0737 (''Clarification of TMI Action Plan Requirements'') and more than half of the mechanical, or hardware, items have been completed at plants with operating reactors. The Committee to Review Generic Requirements was created to develop means for controlling the number and nature of NRC requirements placed on licensees. Probabilistic risk-assessment techniques were not widely used by the NRC until after the Three Mile Island accident. The NRC has directed licensees and applicants for operating licenses to conduct control-room design reviews to identify and correct human-engineering discrepancies. Includes 2 tables

  20. Risk-informed inservice test activities at the NRC

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  1. Risk-informed inservice test activities at the NRC

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-01

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

  2. Arterial stiffness evaluation by cardio-ankle vascular index in hypertension and diabetes mellitus subjects.

    Science.gov (United States)

    Wang, Hongyu; Liu, Jinbo; Zhao, Hongwei; Fu, Xiaobao; Shang, Guangyun; Zhou, Yingyan; Yu, Xiaolan; Zhao, Xujing; Wang, Guang; Shi, Hongyan

    2013-01-01

    Arterial stiffness is an independent predictor for vascular diseases. Cardio-ankle vascular index (CAVI) is a new index of arterial stiffness. In the present study, we investigated the possible risk factors involving CAVI in hypertension and diabetes mellitus (DM) subjects. One thousand sixty-three subjects (M/F 533/530) from Shougang Corporation Examination Center were divided into four groups: healthy group (n = 639); hypertension group (n = 312); DM group (n = 58); and hypertension with DM group (n = 54). CAVI was measured by VS-1000 apparatus. Our results showed that CAVI was significantly higher in hypertension subjects with DM than in healthy and hypertension group, respectively (8.59 ± 1.08 vs 7.23 ± 1.10; 8.59 ± 1.08 vs 7.94 ± 1.33; both P hypertension subjects with DM compared with healthy and hypertension groups. Copyright © 2013 American Society of Hypertension. Published by Elsevier Inc. All rights reserved.

  3. Spent nuclear fuel project multi-canister overpack, additional NRC requirements

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1998-01-01

    The US Department of Energy (DOE), established in the K Basin Spent Nuclear Fuel Project Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel (SNF) Project facilities to achieve nuclear safety equivalency to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Cold Vacuum Drying (CVD) facility or Hot Conditioning System, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNF Project facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO. The background, basic safety issues and general comparison of NRC and DOE requirements for the SNF Project are presented in WHC-SD-SNF-DB-002

  4. NRC Response to an Act or Threat of Terrorism at an NRC-Licensed Facility

    International Nuclear Information System (INIS)

    Frank Congel

    2000-01-01

    The mandated response to a threat or act of terrorism at a U.S. Nuclear Regulatory Commission (NRC)-licensed facility was examined through a tabletop exercise in May 2000 and a limited field exercise in August 2000. This paper describes some of the new issues addressed and lessons learned from those exercises

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

    Energy Technology Data Exchange (ETDEWEB)

    McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.; Mohseni, Aby [U.S. Nuclear Regulatory Commission, Mail Stop T8F5, 11545 Rockville Pike, Rockville, MD 20852 (United States)

    2013-07-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but

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

    International Nuclear Information System (INIS)

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

    2013-01-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but largely

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-02-01

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

  8. NRC/UBC Node

    Energy Technology Data Exchange (ETDEWEB)

    Ellis-Perry, B. [Univ. of British Columbia, Vancouver, British Columbia (Canada); Yogendran, Y. [NRC Inst. for Fuel Cell Innovation, Vancouver, British Columbia (Canada)

    2004-07-01

    'Full text:' In the search for cleaner, more sustainable energy sources, many of the most promising breakthroughs have been in hydrogen technology. However, this promise will remain unfulfilled without public interest and enthusiasm, and without the infrastructure to support the technology. In order to get there, we have to test, perfect, and demonstrate technology that is safe and affordable, and we must do so in practical, familiar settings. Ideally, such settings should be easily accessible to the engineers, planners, and architects of tomorrow while providing a showcase for hydrogen technology that will attract the general public. This place is the NRC/UBC Hydrogen Node. The UBC campus in Point Grey is home to leading edge, internationally recognized researchers in a range of disciplines, both within the University and at the NRC Institute for Fuel Cell Innovation. On average, 40,000 students, faculty, and staff use the campus every day; UBC graduates go on to leadership positions in communities around the globe. Its spectacular setting makes UBC a popular destination for thousands of visitors from around the world. In 2006 UBC will host the World Urban Forum, and in 2010 it will be one of the sites for the Vancouver-Whistler Olympic Games. UBC and its South Campus neighbourhoods are developing as a model sustainable community, offering an excellent opportunity to develop and showcase hydrogen infrastructure and technology in a real-life, attractive setting that will be seen by thousands of people around the world. UBC's facilities, location, and Trek 2010 commitment to excellence in learning, research, and sustainability make it an ideal location for such a project. The H2 Village at UBC will be an integrated hydrogen demonstration project, linked to the hydrogen highway. This project is bringing together leading companies, researchers, and government agencies committed to making the refinement and early adoption of safe hydrogen technology a

  9. NRC/UBC Node

    International Nuclear Information System (INIS)

    Ellis-Perry, B.; Yogendran, Y.

    2004-01-01

    'Full text:' In the search for cleaner, more sustainable energy sources, many of the most promising breakthroughs have been in hydrogen technology. However, this promise will remain unfulfilled without public interest and enthusiasm, and without the infrastructure to support the technology. In order to get there, we have to test, perfect, and demonstrate technology that is safe and affordable, and we must do so in practical, familiar settings. Ideally, such settings should be easily accessible to the engineers, planners, and architects of tomorrow while providing a showcase for hydrogen technology that will attract the general public. This place is the NRC/UBC Hydrogen Node. The UBC campus in Point Grey is home to leading edge, internationally recognized researchers in a range of disciplines, both within the University and at the NRC Institute for Fuel Cell Innovation. On average, 40,000 students, faculty, and staff use the campus every day; UBC graduates go on to leadership positions in communities around the globe. Its spectacular setting makes UBC a popular destination for thousands of visitors from around the world. In 2006 UBC will host the World Urban Forum, and in 2010 it will be one of the sites for the Vancouver-Whistler Olympic Games. UBC and its South Campus neighbourhoods are developing as a model sustainable community, offering an excellent opportunity to develop and showcase hydrogen infrastructure and technology in a real-life, attractive setting that will be seen by thousands of people around the world. UBC's facilities, location, and Trek 2010 commitment to excellence in learning, research, and sustainability make it an ideal location for such a project. The H2 Village at UBC will be an integrated hydrogen demonstration project, linked to the hydrogen highway. This project is bringing together leading companies, researchers, and government agencies committed to making the refinement and early adoption of safe hydrogen technology a reality

  10. NRC licensing criteria for portable radwaste systems

    International Nuclear Information System (INIS)

    Hayes, J.J. Jr.

    1983-01-01

    The shortcomings of various components of the liquid and solid radwaste systems at nuclear power reactors has resulted in the contracting of the functions performed by these systems to various contractors who utilize portable equipment. In addition, some streams, for which treatment was not originally anticipated, have been processed by portable equipment. The NRC criteria applicable to portable liquid and solid radwaste systems is presented along with discussion on what is required to provide an adequate 10 CFR Part 50.59 review for those situations where changes are made to an existing system. The criteria the NRC is considering for facilities which may intend to utilize portable incinerators is also presented

  11. Fatty Liver Index and Lipid Accumulation Product Can Predict Metabolic Syndrome in Subjects without Fatty Liver Disease

    Directory of Open Access Journals (Sweden)

    Yuan-Lung Cheng

    2017-01-01

    Full Text Available Background. Fatty liver index (FLI and lipid accumulation product (LAP are indexes originally designed to assess the risk of fatty liver and cardiovascular disease, respectively. Both indexes have been proven to be reliable markers of subsequent metabolic syndrome; however, their ability to predict metabolic syndrome in subjects without fatty liver disease has not been clarified. Methods. We enrolled consecutive subjects who received health check-up services at Taipei Veterans General Hospital from 2002 to 2009. Fatty liver disease was diagnosed by abdominal ultrasonography. The ability of the FLI and LAP to predict metabolic syndrome was assessed by analyzing the area under the receiver operating characteristic (AUROC curve. Results. Male sex was strongly associated with metabolic syndrome, and the LAP and FLI were better than other variables to predict metabolic syndrome among the 29,797 subjects. Both indexes were also better than other variables to detect metabolic syndrome in subjects without fatty liver disease (AUROC: 0.871 and 0.879, resp., and the predictive power was greater among women. Conclusion. Metabolic syndrome increases the cardiovascular disease risk. The FLI and LAP could be used to recognize the syndrome in both subjects with and without fatty liver disease who require lifestyle modifications and counseling.

  12. Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages

    International Nuclear Information System (INIS)

    1979-10-01

    This directory contains a Summary Report of NRC Approved Packages for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

  13. Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-10-01

    This directory contains a Summary Report of NRC Approved Packages for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory.

  14. Regulatory decision with EPA/NRC/DOE/State Session (Panel)

    Energy Technology Data Exchange (ETDEWEB)

    O`Donnell, E.

    1995-12-31

    This panel will cover the Nuclear Regulatory Commission`s (NRC) proposed radiation limits in the Branch Technical Position on Low-Level Radioactive Waste Performance Assessment and the Environmental Protection Agency`s (EPA) draft regulation in Part 193. Representatives from NRC and EPA will discuss the inconsistencies in these two regulations. DOE and state representatives will discuss their perspective on how these regulations will affect low-level radioactive waste performance assessments.

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

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, P.M.

    1985-07-01

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

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

    International Nuclear Information System (INIS)

    Lewis, P.M.

    1985-07-01

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

  17. SUBJECT AND AUTHOR INDEXS

    Directory of Open Access Journals (Sweden)

    IJBE Volume 2

    2016-09-01

    Full Text Available SUBJECT INDEX IJBE VOLUME 2access credit, 93acquisition, 177AHP, 61, 82, 165arena simulation,43BMC, 69Bojonegoro, 69brand choice, 208brand image, 208brand positioning, 208bullwhip effect, 43burger buns, 1business synergy and financial reports, 177capital structure, 130cluster, 151coal reserves, 130coffee plantation, 93competitiveness, 82consumer behaviour, 33consumer complaint behavior, 101cooking spices, 1crackers, 1cross sectional analytical, 139crosstab, 101CSI, 12direct selling, 122discriminant analysis, 33economic value added, 130, 187employee motivation, 112employee performance, 112employees, 139EOQ, 23farmer decisions, 93farmer group, 52financial performance evaluation, 187financial performance, 52, 177financial ratio, 187financial report, 187fiva food, 23food crops, 151horticulture, 151imports, 151improved capital structure, 177IPA, 12leading sector, 151life insurance, 165LotteMart, 43main product, 61marketing mix, 33, 165matrix SWOT, 69MPE, 61multiple linear regression, 122muslim clothing, 197Ogun, 139Pangasius fillet, 82Pati, 93pearson correlation, 101perceived value, 208performance suppy chain, 23PLS, 208POQ, 23portfolio analyzing, 1product, 101PT SKP, 122pulp and papers, 187purchase decision, 165purchase intention, 33remuneration, 112re-purchasing decisions, 197sales performance, 122sawmill, 52SCOR, 23sekolah peternakan rakyat, 69SEM, 112SERVQUAL, 12Sido Makmur farmer groups, 93SI-PUHH Online, 12small and medium industries (IKM, 61socio-demographic, 139sport drink, 208stress, 139supply chain, 43SWOT, 82the mix marketing, 197Tobin’s Q, 130trade partnership, 52uleg chili sauce, 1 AUTHOR INDEX IJBE VOLUME 2Achsani, Noer Azam, 177Andati, Trias, 52, 177Andihka, Galih, 208Arkeman, Yandra, 43Baga, Lukman M, 69Cahyanugroho, Aldi, 112Daryanto, Arief, 12David, Ajibade, 139Djoni, 122Fahmi, Idqan, 1Fattah, Muhammad Unggul Abdul, 61Hakim, Dedi Budiman, 187Harianto, 93Hartoyo, 101Homisah, 1Hubeis, Musa, 112Hutagaol, M. Parulian, 93Jaya, Stevana

  18. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center. Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Trubey, D.K.; Roussin, R.W.; Gustin, A.B.

    1983-08-01

    An indexed bibliography of open literature selected by the Radiation Shielding Information Center since the previous volume was published in 1980 is presented in the area of radiation transport and shielding against radiation from nuclear reactors (fission and fusion), x-ray machines, radioisotopes, nuclear weapons (including fallout, and low energy accelerators (e.g., neutron generators). The bibliography was typeset from computer files constituting the RSIC Storage and Retrieval Information System. In addition to lists of literature titles by subject categories (accessions 6201-10156), an author index is given. Most of the literature selected for Volume VII was published in the years 1977 to 1981.

  19. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center. Volume 7

    International Nuclear Information System (INIS)

    Trubey, D.K.; Roussin, R.W.; Gustin, A.B.

    1983-08-01

    An indexed bibliography of open literature selected by the Radiation Shielding Information Center since the previous volume was published in 1980 is presented in the area of radiation transport and shielding against radiation from nuclear reactors (fission and fusion), x-ray machines, radioisotopes, nuclear weapons (including fallout, and low energy accelerators (e.g., neutron generators). The bibliography was typeset from computer files constituting the RSIC Storage and Retrieval Information System. In addition to lists of literature titles by subject categories (accessions 6201-10156), an author index is given. Most of the literature selected for Volume VII was published in the years 1977 to 1981

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

    International Nuclear Information System (INIS)

    1996-01-01

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

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  2. NRC regulatory agenda. Seminnual progress report, January 1996--June 1996

    International Nuclear Information System (INIS)

    1996-08-01

    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 rule making which have been received by the Commission and are pending disposition by the Commission. The regulatory Agenda is updated and issued semiannually

  3. NRC [Nuclear Regulatory Commission] TLD [thermoluminescent dosimeter] direct radiation monitoring network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1989-09-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1989

  4. NRC TLD direct radiation monitoring network: Progress report, April--June 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1988-09-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1988

  5. Triglyceride glucose-body mass index is effective in identifying nonalcoholic fatty liver disease in nonobese subjects.

    Science.gov (United States)

    Zhang, Shujun; Du, Tingting; Li, Mengni; Jia, Jing; Lu, Huiming; Lin, Xuan; Yu, Xuefeng

    2017-06-01

    Nonalcoholic fatty liver disease (NAFLD) is an increasingly common condition that is highly correlated with obesity; however, it is not uncommon among nonobese individuals. Triglyceride (TG) and glucose index combined with body mass index (TyG-BMI) has been proposed as a favorable marker of insulin resistance. We sought to investigate the effectiveness of TyG-BMI in identifying NAFLD in nonobese subjects.We conducted a cross-sectional study in a nonobese (BMI glucose, for identifying nonobese subjects at risk for NAFLD.In this study, the prevalence of NAFLD was over one-fifth in the nonobese population. TyG-BMI was an effective marker to detect NAFLD in nonobese subjects.

  6. nRC: non-coding RNA Classifier based on structural features.

    Science.gov (United States)

    Fiannaca, Antonino; La Rosa, Massimo; La Paglia, Laura; Rizzo, Riccardo; Urso, Alfonso

    2017-01-01

    Non-coding RNA (ncRNA) are small non-coding sequences involved in gene expression regulation of many biological processes and diseases. The recent discovery of a large set of different ncRNAs with biologically relevant roles has opened the way to develop methods able to discriminate between the different ncRNA classes. Moreover, the lack of knowledge about the complete mechanisms in regulative processes, together with the development of high-throughput technologies, has required the help of bioinformatics tools in addressing biologists and clinicians with a deeper comprehension of the functional roles of ncRNAs. In this work, we introduce a new ncRNA classification tool, nRC (non-coding RNA Classifier). Our approach is based on features extraction from the ncRNA secondary structure together with a supervised classification algorithm implementing a deep learning architecture based on convolutional neural networks. We tested our approach for the classification of 13 different ncRNA classes. We obtained classification scores, using the most common statistical measures. In particular, we reach an accuracy and sensitivity score of about 74%. The proposed method outperforms other similar classification methods based on secondary structure features and machine learning algorithms, including the RNAcon tool that, to date, is the reference classifier. nRC tool is freely available as a docker image at https://hub.docker.com/r/tblab/nrc/. The source code of nRC tool is also available at https://github.com/IcarPA-TBlab/nrc.

  7. Directory of certificates of compliance for radioactive materials packages. Volume 3, revision 1. Summary report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1981-12-01

    The directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

  8. The NRC weighs public input on plant cleanup standards

    International Nuclear Information System (INIS)

    Simpson, J.

    1993-01-01

    In the wake of seven public open-quotes work-shopsclose quotes held around the country over the past several months, the Nuclear Regulatory Commission (NRC) is preparing to develop radiological criteria for decommissioning nuclear power plants. The criteria will apply to plants that operate for their normal lifespan, those that shut down prematurely, as well as a range of other NRC-licensed facilities, including materials licensees, fuel reprocessing and fabrication plants, and independent spent fuel storage installations. The criteria have been years in the making, and their progress is being monitored closely by the Environmental Protection Agency (EPA), which shares with the NRC the authority to regulate radiological hazards. Both agencies have made abortive attempts to promulgate standards in the past. The EPA's most recent proposal, dating from 1986, has yet to reach the final rule stage. The NCRC's 1990 policy statement, open-quotes Below Regulatory Concern,close quotes was overturned by the Energy Policy Act of 1992, a setback that prompted the Commission's call for open-quotes enhanced participatory rulemakingclose quotes-a.k.a., public meetings-last December. In its Rulemaking Issues Paper, the NRC outlined for discussion four open-quotes fundamentalclose quotes objectives as a basis for developing decommissioning criteria: (1) establishing limits above which the risks to the public are deemed open-quotes unacceptableclose quotes; (2) establishing open-quotes goalsclose quotes below which the risks to the public are deemed open-quotes trivialclose quotes; (3) establishing criteria for what is achievable using the open-quotes best availableclose quotes cleanup technology; and (4) removing all radioactivity attributable to plant activity. The NRC expects to publish a proposed rule and a draft generic environmental impact statement in April 1994; the final rule is scheduled for May 1995

  9. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-03-01

    Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  10. 48 CFR 2009.100 - NRC policy.

    Science.gov (United States)

    2010-10-01

    ... noncompetitive award of contracts to organizations where former NRC employees have dominant management interests...) Contracts awarded noncompetitively under the Small Business Administration's 8(a) Program; (2) Individual... consulting with the Executive Director for Operations. This is in addition to any justification and approvals...

  11. Typical NRC inspection procedures for model plant

    International Nuclear Information System (INIS)

    Blaylock, J.

    1984-01-01

    A summary of NRC inspection procedures for a model LEU fuel fabrication plant is presented. Procedures and methods for combining inventory data, seals, measurement techniques, and statistical analysis are emphasized

  12. Safeguards Summary Event List (SSEL), pre-NRC through December 31, 1989

    International Nuclear Information System (INIS)

    1992-07-01

    The Safeguards Summary Event List (SSEL), Vol. 1, provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC) which occurred and were reported from pre-NRC through December 31, 1989. Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  13. Status of U. S. NRC Actions for the Events of Fukushima Dacha NPP

    International Nuclear Information System (INIS)

    Kim, Donghak; Lee, Jaeyong; Kim, Myungki

    2013-01-01

    In this study, status of U. S. NRC actions for the events of Fukushima is studied by reviewing commission papers, orders, request for information (RFI), Interim Staff Guidance (ISG) issued by NRC, etc. In order to acquire design certification of the APR1400, status of U. S. NRC actions for the events of Fukushima Dacha NTT is reviewed. The NRC has determined and conducted the 38 recommendations for action including 31 NTTF recommendations and seven additional recommendations. The recommendations are divided into Tier 1, Tier 2 and Tier 3. Tier 1 and Tier 2 recommendations are implemented by three Orders, one request for information and two rule makings. To comply with three orders and one request for information, the NRC issued six ISGs and NEI issued three technical reports. The final rule on strengthening and integrating onsite emergency response capabilities will be issued in February 2016. Station blackout mitigating strategies rulemaking on SBO mitigation capability and on spent fuel pool instrumentation and makeup capability will proceed

  14. Recent developments in NRC guidelines for atmosphere cleanup systems

    International Nuclear Information System (INIS)

    Bellamy, R.R.

    1976-01-01

    The Nuclear Regulatory Commission (NRC) maintains the policy of updating when necessary, its published guidance for the design of engineered safety feature (ESF) and normal ventilation systems. The guidance is disseminated by means of issuing new, or revisions to, existing Regulatory Guides, Standard Review Plans, Branch Technical Positions and Technical Specifications. A revised Regulatory Guide, new Technical Specifications and new Standard Review Plans with Branch Technical Positions for atmosphere cleanup systems are discussed. Regulatory Guide 1.52, ''Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants,'' was issued in July 1973. The major comments received from the nuclear industry since the guide was issued, NRC's experience in implementing the guide in recent license applications, status of operating plants in meeting the guidelines and NRC's continuing assessment of operating data and laboratory tests to assure that the guide reflects the latest technology are discussed

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    International Nuclear Information System (INIS)

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D.

    2013-01-01

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

  17. 76 FR 48919 - NRC Enforcement Policy

    Science.gov (United States)

    2011-08-09

    .... In all such cases when a licensee determines that an unplanned change during construction associated..., States, members of the public, and the regulated industry (i.e., reactor and materials licensees, vendors, and contractors), on construction-related topics addressed in this notice that the NRC staff is...

  18. Current perspectives on performance assessment at the NRC

    International Nuclear Information System (INIS)

    Coplan, S.M.; Eisenberg, N.A.; Federline, M.V.; Randall, J.D.

    1992-01-01

    The Nuclear Regulatory Commission (NRC) staff is engaging in a number of activities involving performance assessment in order to support NRC's program in high-level waste management. Broad areas of activity include: (1) reactive work responding to products and activities of the Department of Energy (DOE), (2) proactive work, including development of an independent performance assessment capability, development of guidance for DOE, support for technical and programmatic integration, (3) a program of regulatory research, and (4) participation in a number of international activities. As the U.S. high-level waste program continues to mature, performance assessment is seen as playing a more prominent role in evaluating safety and focussing technical activities

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

    International Nuclear Information System (INIS)

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

    1987-02-01

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

  20. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center (Reactor and Weapons Radiation Shielding)

    International Nuclear Information System (INIS)

    1978-01-01

    An indexed bibliography is presented of literature selected by the Radiation Shielding Information Center since the previous volume was published in 1974 in the area of radiation transport and shielding against radiation from nuclear reactors, x-ray machines, radioisotopes, nuclear weapons (including fallout), and low-energy accelerators (e.g., neutron generators). In addition to lists of literature titles by subject categories (accessions 3501-4950), author and keyword indexes are given. Most of the literature selected for Vol. V was published in the years 1973 to 1976

  1. Presentation on NRC Regulatory Positions and guidelines

    International Nuclear Information System (INIS)

    Russell, W.T.

    1994-01-01

    The NRC staff recognizes the potential for enhanced safety and reliability that digital systems bring to the nuclear industry. The staff also recognizes the challenges to safety that are unique to digital systems implementation

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-10-01

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

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

    International Nuclear Information System (INIS)

    1995-06-01

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

  4. NRC Information No. 90-01: Importance of proper response to self-identified violations by licensees

    International Nuclear Information System (INIS)

    Cunningham, R.E.

    1992-01-01

    NRC expects a high standard of compliance by its licensees and requires that licensees provide NRC accurate and complete information and that required records will also be complete and accurate in all material respects. Licensees should be aware of the importance placed by NRC on licensee programs for self detection, correction and reporting of violations or errors related to regulatory requirements. The General Statement of Policy and Procedures for NRC Enforcement Actions in Appendix C to 10 CFR Part 2 underscores the importance of licensees responding promptly and properly to self-identified violations in two ways. It is suggested that when a licensee identifies a violation involving an NRC-required record, the licensee should make a dated notation indicating identification, either on the record itself or other appropriate documentation retrievable for NRC review. The record with the self-identified violation noted should not be altered in any way to mask the correction. The licensee should determine the cause of the violation, correct the root cause of the violation, and document such findings in an appropriate manner. Licensees should also assure that if a report of the violation is required, the report is submitted to NRC in a timely manner. These actions will be considered by NRC in making any enforcement decision, and generally lead to lesser or no civil penalty

  5. Abstracts: NRC Waste Management Program reports

    Energy Technology Data Exchange (ETDEWEB)

    Heckman, R.A.; Minichino, C.

    1979-11-01

    This document consists of abstracts of all reports published by the Nuclear Regulatory Commission (NRC) Waste Management Program at Lawrence Livermore Laboratory (LLL). It will be updated at regular intervals. Reports are arranged in numerical order, within each category. Unless otherwise specified, authors are LLL scientists and engineers.

  6. Abstracts: NRC Waste Management Program reports

    International Nuclear Information System (INIS)

    Heckman, R.A.; Minichino, C.

    1979-11-01

    This document consists of abstracts of all reports published by the Nuclear Regulatory Commission (NRC) Waste Management Program at Lawrence Livermore Laboratory (LLL). It will be updated at regular intervals. Reports are arranged in numerical order, within each category. Unless otherwise specified, authors are LLL scientists and engineers

  7. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2015-05-01

    maintaining a presence on social media sites such as Facebook . The NRC attended a number of minority focused events in which we maintained exhibit booths...PROPOSAL The Use of Glial Inhibitors to Increase the Efficacy of Opioid Analgesics while Eliminating the Propensity for Addiction 7) SUMMARY OF RESEARCH

  8. Agency procedures for the NRC incident response plan. Final report

    International Nuclear Information System (INIS)

    1983-02-01

    The NRC Incident Response Plan, NUREG-0728/MC 0502 describes the functions of the NRC during an incident and the kinds of actions that comprise an NRC response. The NRC response plan will be activated in accordance with threshold criteria described in the plan for incidents occurring at nuclear reactors and fuel facilities involving materials licensees; during transportation of licensed material, and for threats against facilities or licensed material. In contrast to the general overview provided by the Plan, the purpose of these agency procedures is to delineate the manner in which each planned response function is performed; the criteria for making those response decisions which can be preplanned; and the information and other resources needed during a response. An inexperienced but qualified person should be able to perform functions assigned by the Plan and make necessary decisions, given the specified information, by becoming familiar with these procedures. This rule of thumb has been used to determine the amount of detail in which the agency procedures are described. These procedures form a foundation for the training of response personnel both in their normal working environment and during planned emergency exercises. These procedures also form a ready reference or reminder checklist for technical team members and managers during a response

  9. Generic communications index. Listings of communications 1971-1989

    Energy Technology Data Exchange (ETDEWEB)

    Hagemeyer, D; Towle, H

    1991-05-01

    As part of its program to feed back information on operating experience to industry, the U.S. Nuclear Regulatory Commission (NRC) issues generic communications called bulletins (about 5/yr), circulars (now discontinued), generic letters (about 20/yr), and information notices (about 100/yr). The report presents an updated Generic Communications Index (GCI; previously published in NUREG/CR-4690, Vol. 1, December 1987) of all such communications from 1971, when such documentation started, to 1989. The GCI consists of records, one for each communication, containing fields for identification number, title, NRC technical contact, general system or topic, specific component or topic, cause or defect, potential effect, remarks, and vendors involved. To facilitate information retrieval, the report also contains topical listings of generic communications numbers. (author)

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

    International Nuclear Information System (INIS)

    1997-08-01

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

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

    International Nuclear Information System (INIS)

    1995-09-01

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

  12. NRC TLD Direct Radiation Monitoring Network. Progress report, January-June 1981

    International Nuclear Information System (INIS)

    1982-04-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of 55 NRC-licensed facility sites throughout the country for the first half of 1981. The program objectives, scope, and methodology are given. The TLD system, dosimeter location, data processing scheme, and quality assurance program are outlined

  13. Status of ECCS Acceptance Criteria Revision in U. S. NRC and Perspective

    International Nuclear Information System (INIS)

    Lee, Joosuk; Woo, Swengwoong

    2013-01-01

    Subsequently the NRC had conducted a fuel cladding research program to investigate the behavior of high burnup fuel cladding under LOCA conditions. This research program conducted at Argonne National Laboratory (ANL), as well as conducted as jointly-funded programs at the Kurchatov Institute and the Halden Reactor. From these programs, several important technical findings, listed in following section, for rule revision were obtained. On March 14, 2000, the Nuclear Energy Institute (NEI) submitted a petition for rulemaking (PRM) requesting that the NRC amend its regulations in 50.44 and 50.46 (PRM 50-71). The NEI petition stated that these regulations apply to only two specific zirconium-alloy fuel cladding materials (zircaloy and ZIRLO TM ). The NRC resolved PRM-50-71 by deciding that it should be considered in the following rulemaking process. Meanwhile, on March 15, 2007, Mark Leyse submitted a PRM to the NRC (PRM 50-84). The petitioner requests that the NRC conduct rulemaking in the following areas: Establish regulations that require licensees to operate light-water power reactors under conditions that are effective in limiting the thickness of crud and/or oxide layers. Amend Appendix K to Part 50 to explicitly require that steady-state temperature distribution and stored energy in the reactor fuel at the onset of a postulated LOCA be calculated by factoring in the role of the thermal resistance of crud and oxide layers. Amend 50.46 to specify a maximum allowable percentage of hydrogen content in the cladding. The NRC resolved PRM-50-84 by deciding that the petitioner's issues should be considered in the rulemaking process. On August 13, 2009, the NRC published an Advance Notice of Proposed Rulemaking (ANPR) to obtain stakeholder views on issues associated with amending 50.46. On March 1, 2012, and subsequently modified by the staff's June 1, 2012, SECY-12-0034 was submitted to the Commission to obtain approval to publish for public comment, and it was approved

  14. Status of ECCS Acceptance Criteria Revision in U. S. NRC and Perspective

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Joosuk; Woo, Swengwoong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    Subsequently the NRC had conducted a fuel cladding research program to investigate the behavior of high burnup fuel cladding under LOCA conditions. This research program conducted at Argonne National Laboratory (ANL), as well as conducted as jointly-funded programs at the Kurchatov Institute and the Halden Reactor. From these programs, several important technical findings, listed in following section, for rule revision were obtained. On March 14, 2000, the Nuclear Energy Institute (NEI) submitted a petition for rulemaking (PRM) requesting that the NRC amend its regulations in 50.44 and 50.46 (PRM 50-71). The NEI petition stated that these regulations apply to only two specific zirconium-alloy fuel cladding materials (zircaloy and ZIRLO{sup TM}). The NRC resolved PRM-50-71 by deciding that it should be considered in the following rulemaking process. Meanwhile, on March 15, 2007, Mark Leyse submitted a PRM to the NRC (PRM 50-84). The petitioner requests that the NRC conduct rulemaking in the following areas: Establish regulations that require licensees to operate light-water power reactors under conditions that are effective in limiting the thickness of crud and/or oxide layers. Amend Appendix K to Part 50 to explicitly require that steady-state temperature distribution and stored energy in the reactor fuel at the onset of a postulated LOCA be calculated by factoring in the role of the thermal resistance of crud and oxide layers. Amend 50.46 to specify a maximum allowable percentage of hydrogen content in the cladding. The NRC resolved PRM-50-84 by deciding that the petitioner's issues should be considered in the rulemaking process. On August 13, 2009, the NRC published an Advance Notice of Proposed Rulemaking (ANPR) to obtain stakeholder views on issues associated with amending 50.46. On March 1, 2012, and subsequently modified by the staff's June 1, 2012, SECY-12-0034 was submitted to the Commission to obtain approval to publish for public comment, and it

  15. Occupational radiation exposures at NRC-licensed facilities

    International Nuclear Information System (INIS)

    Brooks, B.G.

    1980-01-01

    For the past ten years, the Nuclear Regulatory Commission and its predecessor, the Atomic Energy Commission, have required certain licensees to routinely submit two types of occupational radiation exposure reports: termination and annual reports. Each licensee engaged in any one of the activities: (1) operation of nuclear power reactors, (2) industrial radiography, (3) fuel fabrication, processing and reprocessing, and (4) large supply of byproduct material, is required to submit an annual statistical report and a termination report for each monitored employee who ends his employment or work assignment. A new regulation now requires all NRC licensees to submit annual reports for the years 1978 and 1979. These reports have been collected, computerized and maintained by the Commission at Oak Ridge, Tennessee. They are useful to the NRC in the evaluation of the risk of radiation exposure associated with the related activities. (author)

  16. List of U.S. Army Research Institute Research and Technical Publications for Public Release/Unlimited Distribution. Fiscal Year 2007 (October 1, 2006 to September 30, 2007) With Author Index and Report Titles and Subject Terms Index

    Science.gov (United States)

    2008-04-01

    Year 2007 October 1, 2006 to September 30, 2007 With Author Index and Report Titles and Subject Terms Index United States Army Research Institute for...Fiscal Year 2007 October 1, 2006 to September 30, 2007 With Author Index and Report Titles and Subject Terms Index CONTENTS Page Introduction...39 Author Index .................................................................................................................. 39

  17. Amalgamation of performance indicators to support NRC senior management reviews

    International Nuclear Information System (INIS)

    Wreathall, J.; Schurman, D.; Modarres, M.; Mosleh, A.; Anderson, N.; Reason, J.

    1991-01-01

    The purpose of this project is to develop a methodology for amalgamating performance indicators to provide an overall perspective on plant safety, as one input to Nuclear Regulatory Commission's (NRC) senior management reviews of plant safety. These reviews are used to adjust the level of oversight by NRC. Work completed to date includes the development of frameworks for relating indicator measures to safety, a classification scheme for performance indicators, and a mapping process to portray indicators in the frameworks

  18. 76 FR 10072 - Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station...

    Science.gov (United States)

    2011-02-23

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0013] Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System Voltages; Reopening of... (NRC's) Draft Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System...

  19. The use of U.S. NRC licensing practices for VVERs

    International Nuclear Information System (INIS)

    Popp, D.M.

    2000-01-01

    The licensing process for the upgraded Temelin I and C and Fuel designs were enhanced with the introduction of U.S. Nuclear Regulatory Commission, NRC practices. Specifically, the use of the NRC Regulatory Guide 1.70, 'Standard Format and Content Guide for Safety Analyses Reports' and NRC NUREG 0800, 'Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants', were beneficial in the development and review of Temelin licensing documentation. These standards have been used for the preparation and review of Safety Analysis Reports in the United States and also in a large number of licensing applications around the world. Both Regulatory Guide 1.70 and NUREG 0800 were developed to provide a predictable and structured approach to licensing. This paper discusses this approach and identifies the benefits to designers, writers of licensing documentation and reviewers of licensing documents. (author)

  20. NRC Information No. 88-12: Overgreasing of electric motor bearings

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    NRC personnel observed accumulations of grease on the air vent screens of electric motors used for driving such rotating equipment as fans and pumps at the Millstone and Calvert Cliffs nuclear power plants. The grease appeared to have come from overgreasing of the electric motor bearings. Grease was forced out of the bearing seals, onto the stator windings and rotor, from where it either fell or was thrown onto the inside of the motor housing. Because of these observations, the NRC began an investigation into problems that have been caused in the past, or could be caused in the future, by the overgreasing of electric motor bearings. The NRC staff has solicited technical information and operating experience on the problems caused by the overgreasing of electric motor bearings from motor and bearing manufacturers, as well as from other licensees. Their responses are summarized in this discussion

  1. 76 FR 57767 - Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for...

    Science.gov (United States)

    2011-09-16

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0204] Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for Operating Reactors AGENCY: Nuclear Regulatory Commission... FR 54507), that requested public comment on Draft NRC Generic Letter 2011- XX: Seismic Risk...

  2. Safeguards Summary Event List (SSEL). Pre-NRC through June 30, 1981

    International Nuclear Information System (INIS)

    MacMurdy, P.; Davidson, J.; Lin, H.

    1981-09-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, vandalism, arson, firearms, sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  3. NRC Regulatory Agenda semiannual report, July--December 1995. Volume 14, No. 2

    International Nuclear Information System (INIS)

    1996-02-01

    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 semianually

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

    International Nuclear Information System (INIS)

    1997-03-01

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

  5. NRC TLD [thermoluminescent dosimeter] Direct Radiation Monitoring Network: Progress report, January-March 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1988-06-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the first quarter of 1988

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

    International Nuclear Information System (INIS)

    1989-08-01

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

  7. NRC wants plant-specific responses on Thermo-Lag

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Dissatisfied with recent industry-backed efforts to assure fire safety at nuclear power plants, the Nuclear Regulatory Commission announced on November 24 that it would direct all nuclear plant owners to specify the actions they would take to assure that the use of the Thermo-Lag 330 fire barrier material would not lead to insufficient protection of electrical cables connected to safe-shutdown systems. Previously, the NRC had been content to let the matter wait until tests sponsored by the Nuclear Management and Resources Council (Numarc) could show whether Thermo-Lag, used and installed in certain ways, would provide sufficient protection, but the NRC and Numarc have disagreed over the test methodology, and the Numarc tests are now considered to be several months behind schedule

  8. NRC drug-free workplace plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

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

  9. NRC drug-free workplace plan. Revision 1

    International Nuclear Information System (INIS)

    1997-11-01

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

  10. Building beef cow nutritional programs with the 1996 NRC beef cattle requirements model.

    Science.gov (United States)

    Lardy, G P; Adams, D C; Klopfenstein, T J; Patterson, H H

    2004-01-01

    Designing a sound cow-calf nutritional program requires knowledge of nutrient requirements, diet quality, and intake. Effectively using the NRC (1996) beef cattle requirements model (1996NRC) also requires knowledge of dietary degradable intake protein (DIP) and microbial efficiency. Objectives of this paper are to 1) describe a framework in which 1996NRC-applicable data can be generated, 2) describe seasonal changes in nutrients on native range, 3) use the 1996NRC to predict nutrient balance for cattle grazing these forages, and 4) make recommendations for using the 1996NRC for forage-fed cattle. Extrusa samples were collected over 2 yr on native upland range and subirrigated meadow in the Nebraska Sandhills. Samples were analyzed for CP, in vitro OM digestibility (IVOMD), and DIP. Regression equations to predict nutrients were developed from these data. The 1996NRC was used to predict nutrient balances based on the dietary nutrient analyses. Recommendations for model users were also developed. On subirrigated meadow, CP and IVOMD increased rapidly during March and April. On native range, CP and IVOMD increased from April through June but decreased rapidly from August through September. Degradable intake protein (DM basis) followed trends similar to CP for both native range and subirrigated meadow. Predicted nutrient balances for spring- and summer-calving cows agreed with reported values in the literature, provided that IVOMD values were converted to DE before use in the model (1.07 x IVOMD - 8.13). When the IVOMD-to-DE conversion was not used, the model gave unrealistically high NE(m) balances. To effectively use the 1996NRC to estimate protein requirements, users should focus on three key estimates: DIP, microbial efficiency, and TDN intake. Consequently, efforts should be focused on adequately describing seasonal changes in forage nutrient content. In order to increase use of the 1996NRC, research is needed in the following areas: 1) cost-effective and

  11. Safeguards Summary Event List (SSEL), Pre-NRC through December 31, 1985

    International Nuclear Information System (INIS)

    1987-02-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  12. Safeguards Summary Event List (SSEL): Pre-NRC through December 31, 1986

    International Nuclear Information System (INIS)

    1987-07-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  13. Overview of the NRC nuclear waste management program

    International Nuclear Information System (INIS)

    Malaro, J.C.

    1976-01-01

    The NRC has firmly established waste management as a high-priority effort and has made the commitment to act rapidly and methodically to establish a sound regulatory base for licensing waste management activities. We believe the priorities for NRC work in waste management are consistent with the needs of the overall national waste management program. Present licensing procedures and criteria are adequate for the short term, and priority attention is being given to the longer term, when the quantities of waste to be managed will be greater and licensing demands will increase. Recognizing that its decision will affect industry, other governmental jurisdictions, private interest groups, and the public at large, NRC has encouraged and will continue to encourage their participation in planning our program. We also recognize that the problems of nuclear waste management are international in scope. Many waste management problems (e.g., potential for contamination of oceans and atmosphere, need for isolation of some wastes for longer periods than governments and political boundaries have remained stable in the past), require a set of internationally acceptable and accepted solutions. The wastes from the U.S. nuclear industry will account for only about one third of the nuclear waste generated in the world. Therefore, we propose to cooperate and where appropriate take the lead in establishing acceptable worldwide policies, standards and procedures for handling nuclear wastes

  14. Building confidence in nuclear waste regulation: how NRC is adapting in response to stakeholder concerns

    International Nuclear Information System (INIS)

    Kotra, Janet P.

    2004-01-01

    Increasing public confidence in the U.S. Nuclear Regulatory Commission as an effective and independent regulator is an explicit goal of the Agency. When developing new, site-specific regulations for the proposed geologic repository at Yucca Mountain, Nevada, NRC sought to improve its efforts to inform and involve the public in NRC's decision-making process. To this end, NRC has made, and continues to make significant organizational, process and policy changes. NRC successfully applied these changes as it completed final regulations for Yucca Mountain, when introducing a draft license review plan for public comment, and when responding to public requests for information on NRC's licensing and hearing process. It should be understood, however, that these changes emerged, and continue to be applied, in the context of evolving agency concern for increasing stakeholder confidence reflected in institutional changes within the agency as a whole. (author)

  15. Summary and recommendations of the NRC/INEL Activated Carbon Testing Program

    International Nuclear Information System (INIS)

    Scarpellino, C.D.; Sill, C.W.

    1986-01-01

    The Committee on Nuclear Air and Gas Treatment (CONAGT) of the American Society of Mechanical Engineers (ASME) sponsored an interlaboratory testing program, round-robin, of nuclear-grade activated carbon. The results of this round-robin revealed gross differences in penetration of radio-labeled methyl iodide as measured by the various laboratories when using Method A of the ASTM D-3803-79 Standard. These differences prompted the Nuclear Regulatory Commission (NRC) to establish the NRC/INEL Activated Carbon Testing Program to determine the causes of these discrepancies and to provide recommendations that could lead to an accurate and reliable testing procedure that would ensure an adequate method for assessing the capability of activated carbon to remove radioiodine from gas streams within commercial nuclear power plants. The NRC/INEL Activated Carbon Testing Program has conducted formal and informal interlaboratory comparisons to identify problems with the test method and its application and to assess the effectiveness of changes to procedures and equipment voluntarily implemented by commercial laboratories to mitigate the disparity of test results. The results of the first formal NRC/INEL Interlaboratory Comparison (IC) essentially verified the CONAGT round-robin results despite the use of a detailed test protocol. This data indicated that many of the participating laboratories probably had been operating outside the ASTM specifications for relative humidity (RH) and flow. In addition, this process provided information which was used to modify the testing protocol employed for the second NRC/INEL Interlaboratory Comparison (IC-2) to make it more rugged and reliable. These changes to the protocol together with the results of INEL sensitivity testing are the basis for the recommendations presented

  16. Bibliography, subject index, and author index of the literature examined by the radiation shielding information center. Volume 6. Reactor and weapons radiation shielding

    International Nuclear Information System (INIS)

    1980-05-01

    An indexed bibliography is presented of literature selected by the Radiation Shielding Information Center since the previous volume was published in 1978 in the area of radiation transport and shielding against radiation from nuclear reactors, x-ray machines, radioisotopes, nuclear weapons (including fallout), and low energy accelerators (e.g., neutron generators). The bibliography was typeset from data processed by computer from magnetic tape files. In addition to lists of literature titles by subject categories (accessions 4951-6200), an author index is given

  17. NRC Information No. 91-29: Deficiencies identified during electrical distribution system functional inspections

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    During multidisciplinary inspections, the US Nuclear Regulatory Commission (NRC) has identified many deficiencies related to the electrical distribution system. To address these deficiencies, the NRC has developed an inspection to specifically evaluate the electrical distribution system. During the last year, the NRC completed eight EDSFIs, performing at least one in each of the several common deficiencies in the licensees' programs and in the electrical distribution systems as designed and configured at each plant. These deficiencies included inadequate ac voltages at the 480 Vac and 120 Vac distribution levels, inadequate procedures to test circuit breakers, and inadequate determinations and evaluations of setpoints

  18. USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)

    International Nuclear Information System (INIS)

    Maskewitz, B.F.; Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository

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

    International Nuclear Information System (INIS)

    1996-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

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

  1. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1994-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1993. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  2. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1993-03-01

    This report present the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1992. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  3. Safeguards summary event list (SSEL): Pre-NRC through December 31, 1987

    International Nuclear Information System (INIS)

    1988-07-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, alcohol and drugs, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-10-01

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

  5. NRC's geotechnical engineering research needs for the high-level waste repository program

    International Nuclear Information System (INIS)

    Gupta, D.C.; Philip, J.; Lorig, L.J.; Chowdhury, A.H.

    1992-01-01

    To develop the capability for independently assessing the US Department of Energy's (DOE's) geologic repository design within a limited time, the US Nuclear Regulatory Commission (NRC) staff needs to perform certain research well before receiving the license application. The NRC staff is using a number of factors to identify the areas that it needs to research. The staff assigns priorities to the needed research based on programmatic considerations and the significance of the work. In the geotechnical engineering field, the staff is conducting research in the following three areas: response of the repository to repeated strong ground motion, rock-mass sealing, and coupled thermo-hydro-mechanical interactions. In this paper, the NRC staff also presents the areas of additional research needed in the geotechnical engineering field

  6. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center (Reactor and Weapons Radiation Shielding). [1973--1976

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    An indexed bibliography is presented of literature selected by the Radiation Shielding Information Center since the previous volume was published in 1974 in the area of radiation transport and shielding against radiation from nuclear reactors, x-ray machines, radioisotopes, nuclear weapons (including fallout), and low-energy accelerators (e.g., neutron generators). In addition to lists of literature titles by subject categories (accessions 3501-4950), author and keyword indexes are given. Most of the literature selected for Vol. V was published in the years 1973 to 1976.

  7. Differences in time-domain and spectral indexes of skin-surface laser-Doppler signals between controls and breast-cancer subjects.

    Science.gov (United States)

    Hsiu, Hsin; Chen, Chao-Tsung; Hung, Shuo-Hui; Chen, Guan-Zhang; Huang, Yu-Ling

    2018-04-13

    There is an urgent need to improve the early diagnosis of breast cancer. The present study applied spectral and beat-to-beat analyses to laser-Doppler (LDF) data sequences measured on the skin surface on the back of the right hands, with the aim of comparing the different peripheral microcirculatory-blood-flow (MBF) perfusion condition between breast-cancer and control subjects. ECG and LDF signals were obtained simultaneously and noninvasively from 23 breast-cancer patients and 23 age-matched control subjects. Time-domain beat-to-beat indexes and their variability parameters were calculated. Spectral indexes were calculated using the Morlet wavelet transform. The beat-to-beat LDF pulse width and its variability were significantly smaller in cancer patients than in the controls. The energy contributions of endothelial-, neural-, and myogenic-related frequency bands were also significantly smaller in cancer patients. The present study has revealed significant differences in the beat-to-beat and spectral indexes of skin-surface-acquired LDF signals between control subjects and breast-cancer patients. This illustrates that LDF indexes may be useful for monitoring the changes in the MBF perfusion condition induced by breast cancer. Since the breast-cancer patients were at TNM stages 0- 2, the present findings may aid the development of indexes for detecting breast cancer.

  8. High-level-waste records management system: the NRC pilot project

    International Nuclear Information System (INIS)

    Bender, A.; Altomare, P.

    1987-01-01

    The US Nuclear Regulatory Commission (NRC) and the US Dept. of Energy (DOE) have agreed to develop a licensing support system (LSS) to address the records management requirements created by the Nuclear Waste Policy Act (NWPA). The NRC is planning to conduct a negotiated rule making the modify 10CFR2, including rules governing discovery, so that parties to the licensing process will use a single information management system as a source for all licensing-related documents. The successful demonstration of the pilot project has resulted in an operational on-line record management system for NRC-related HLW documents. Both incoming and outgoing documents are being scanned and stored on a mainframe system and on an optical disk. At this writing the optical disk portion of the system is being tested to evaluate its potential use as a future archival and distribution medium for licensing records. Experience gained from this project is being shared with other government agencies that are in the process of using similar technologies to come to grips with the complex records management problem endemic to our information-based society

  9. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1991-04-01

    This report presents the results of the NRC [Nuclear Regulatory Commission] Direct Radiation Monitoring Network for the fourth quarter of 1990. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs

  10. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-12-01

    The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  11. Handbook for value-impact assessments of NRC regulatory actions

    International Nuclear Information System (INIS)

    Mullen, M.F.; DiPalo, A.J.

    1985-01-01

    According to current Nuclear Regulatory Commission (NRC) procedures, value-impact (cost-benefit) assessments must be prepared for all rulemaking actions and for a broad range of other regulatory requirements and guidance. Probabilistic risk assessment (PRA) methods furnish an important part of the information base for these assessments. PRA methods are frequently the principal quantitative tool for estimating the benefits (e.g., public risk reduction) of proposed regulatory actions. In December 1983, the NRC published A Handbook for Value-Impact Assessment, NUREG/CR-3568, which provides a set of systematic procedures for performing value-impact assessments. The Handbook contains methods, data, and sources of information that can assist the regulatory analyst in conducting such assessments. The use of probabilistic risk analysis to estimate the benefits of proposed regulatory actions is described. Procedures and methods are also given for evaluating the costs and other consequences associated with regulatory actions. The Handbook has been adopted by the NRC as the recommended guideline for value impact assessments. This paper presents the background, objectives, and scope of the Handbook, describes the value-impact assessment methods (including the use of probabilistic risk assessment to estimate benefits), and discusses a selection of current and planned applications, with examples to illustrate how the methods are used

  12. Triglyceride glucose index, a marker of insulin resistance, is associated with coronary artery stenosis in asymptomatic subjects with type 2 diabetes.

    Science.gov (United States)

    Lee, Eun Young; Yang, Hae Kyung; Lee, Joonyub; Kang, Borami; Yang, Yeoree; Lee, Seung-Hwan; Ko, Seung-Hyun; Ahn, Yu-Bae; Cha, Bong Yun; Yoon, Kun-Ho; Cho, Jae Hyoung

    2016-09-15

    Insulin resistance is one of the most important contributing factors to cardiovascular disease. This study aimed to investigate the association between coronary artery stenosis (CAS) and triglyceride glucose index (TyG index), a simple insulin resistance marker, in asymptomatic subjects with type 2 diabetes. We recruited asymptomatic adults with type 2 diabetes but without previous history of coronary heart disease (n = 888). Significant CAS was defined as maximum intraluminal stenosis ≥70 % by coronary CT angiography. TyG index was calculated as log [fasting triglycerides (mg/dl) x fasting glucose (mg/dl)/2]. Mean age was 63.8 ± 9.5 and 58.9 % of the subjects were men. We analyzed the participants according to the tertile of TyG index. The TyG index was correlated with HOMA-IR (r = 0.397, P index were younger but showed worse clinical and metabolic parameters. The prevalence of CAS was higher in subjects with higher tertile of TyG compared with those with lower tertile of TyG (14 % vs. 7.8 %, P = 0.022). On multiple regression analysis, the highest tertile of TyG index was an independent risk factor for CAS after adjustment for other confounders (odds ratio, 3.19 [95 % CI, 1.371-7.424]). Subgroup analysis showed that TyG index showed more significant association with CAS in patients with risk factors such as old age, longer duration of diabetes, poor glycemic control, no statin use, and male gender. Higher TyG index is associated with increased risk of CAS in asymptomatic subjects with type 2 diabetes, particularly when they have risk factors for cardiovascular disease. This study was retrospectively registered in ClinicalTrials. gov with the registration number of NCT02070926 in Feb 23, 2014.

  13. Regulatory Multidimensionality of Gas Vesicle Biogenesis in Halobacterium salinarum NRC-1

    Directory of Open Access Journals (Sweden)

    Andrew I. Yao

    2011-01-01

    Full Text Available It is becoming clear that the regulation of gas vesicle biogenesis in Halobacterium salinarum NRC-1 is multifaceted and appears to integrate environmental and metabolic cues at both the transcriptional and posttranscriptional levels. The mechanistic details underlying this process, however, remain unclear. In this manuscript, we quantify the contribution of light scattering made by both intracellular and released gas vesicles isolated from Halobacterium salinarum NRC-1, demonstrating that each form can lead to distinct features in growth curves determined by optical density measured at 600 nm (OD600. In the course of the study, we also demonstrate the sensitivity of gas vesicle accumulation in Halobacterium salinarum NRC-1 on small differences in growth conditions and reevaluate published works in the context of our results to present a hypothesis regarding the roles of the general transcription factor tbpD and the TCA cycle enzyme aconitase on the regulation of gas vesicle biogenesis.

  14. Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

    International Nuclear Information System (INIS)

    James, R.W.; Shank, J.W.; Yoder, C.

    1996-01-01

    Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-08-01

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

  16. Reliability of levator scapulae index in subjects with and without scapular downward rotation syndrome.

    Science.gov (United States)

    Lee, Ji-Hyun; Cynn, Heon-Seock; Choi, Woo-Jeong; Jeong, Hyo-Jung; Yoon, Tae-Lim

    2016-05-01

    The objective of this study was to introduce levator scapulae (LS) measurement using a caliper and the levator scapulae index (LSI) and to investigate intra- and interrater reliability of the LSI in subjects with and without scapular downward rotation syndrome (SDRS). Two raters measured LS length twice in 38 subjects (19 with SDRS and 19 without SDRS). For reliability testing, intraclass correlation coefficients (ICCs), standard error of measurement (SEM), and minimal detectable change (MDC) were calculated. Intrarater reliability analysis resulted with ICCs ranging from 0.94 to 0.98 in subjects with SDRS and 0.96 to 0.98 in subjects without SDRS. These results represented that intrarater reliability in both groups were excellent for measuring LS length with the LSI. Interrater reliability was good (ICC: 0.82) in subjects with SDRS; however, interrater reliability was moderate (ICC: 0.75) in subjects without SDRS. Additionally, SEM and MDC were 0.13% and 0.36% in subjects with SDRS and 0.35% and 0.97% in subjects without SDRS. In subjects with SDRS, low dispersion of the measurement errors and MDC were shown. This study suggested that the LSI is a reliable method to measure LS length and is more reliable for subjects with SDRS. Copyright © 2015 Elsevier Ltd. All rights reserved.

  17. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2018-05-01

    2- 0010 Report Period: 02/06/2012-02/28/2018 4/11/2018, 12:17 PM During the reporting period, the National Academies of Sciences, Engineering , and...to advertise the NRC Research Associateship Programs included the following: 1) attendance at meetings of major scientific and engineering ...professional societies; 2) advertising in programs and career centers for these and other professional society meetings; 3) direct mailing and emailing of

  18. Perspective on US NRC Policy Issues Concerning Use of Risk Insights for Non-LWR

    International Nuclear Information System (INIS)

    Ha, Jun Su; Kim, In Goo; Huh, Chang Wook; Kim, Kyun Tae

    2011-01-01

    Since the PRA Implementation plan of US NRC (1994), PRA has been applied to all NPPs in USA and risk insights have been used for the regulation as a complement of the deterministic approaches. RIRIP (Risk-Informed Regulation Implementation Plan, 2000) and RPP (Risk-Informed and Performance-Based Plan, 2007) were announced by US NRC thereafter, which recommended enhanced use of risk insights. In the meantime, there have been lots of policy issues concerning use of risk insights for licensing Non-LWR designs, which will be discussed in this paper to understand the stream of perspectives on US NRC's approach

  19. 77 FR 33786 - NRC Enforcement Policy Revision

    Science.gov (United States)

    2012-06-07

    ... methods: Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2011... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems... either 2.3.2.a. or b. must be met for the disposition of a violation as an NCV.'' The following new...

  20. Shift technical advisors: in the eyes of the NRC

    International Nuclear Information System (INIS)

    Crocker, L.P.

    1981-01-01

    Since January 1, 1980, the NRC has required that Shift Technical Advisors be on-shift at all operating nuclear power plants. The objective of the requirement is to assure that technical expertise is immediately available to each operating shift to assess off-normal events and to provide advice to control room personnel. Further, this advice and assistance is to be provided by an individual not responsible for control manipulations or for directing the activities of reactor operators. The long-term requirement for on-shift technical expertise is firm. However, the exact manner in which this expertise must be furnished has not been determined. Licensees have proposed various alternatives to meet this requirement. These proposals still are being reviewed by the NRC staff

  1. The evolution of the structure and application of U.S. NRC regulations and standards

    International Nuclear Information System (INIS)

    Murley, T.E.; Rosztoczy, Z.R.; McPherson, G.D.

    1991-01-01

    NRC regulations and standards and their implementation have evolved from early adaptations of conventional engineering practices to a mature, cohesive set of regulations that govern NRC regulation of nuclear power plant safety in the United States. From a simple set of rules and design criteria and from the standards of the professional engineering societies, a hierarchy of practices, standards, guides, rules and goals has developed. Resting on a foundation of industrial practices, this hierarchy rises through levels of national standards, regulatory guides and standard review plans, policy statements and NRC regulations. The licensing process is evolving today toward one that permits both site approval and standard design certification before the plant is constructed. At the present time, NRC is reviewing five standard designs for certification for a period of 15 years. NRC focuses its regulation of operating nuclear plants on inspections conducted from five regional offices. Resident inspectors, specialist inspectors, and multi-disciplinary inspection teams examine specific plant situations. The results of all these inspections are used to develop a complete understanding of a plant's physical condition, its operation, maintenance and management. To improve safe operation of nuclear plants in the U.S., a most important program, the Systematic Assessment of Licensee Performance, measures operational performance, using a broad spectrum of functional areas. (orig.)

  2. SU-A-210-02: Medical Physics Opportunities at the NRC

    International Nuclear Information System (INIS)

    Abogunde, M.

    2015-01-01

    The purpose of this student annual meeting is to address topics that are becoming more relevant to medical physicists, but are not frequently addressed, especially for students and trainees just entering the field. The talk is divided into two parts: medical billing and regulations. Hsinshun Wu – Why should we learn radiation oncology billing? Many medical physicists do not like to be involved with medical billing or coding during their career. They believe billing is not their responsibility and sometimes they even refuse to participate in the billing process if given the chance. This presentation will talk about a physicist’s long career and share his own experience that knowing medical billing is not only important and necessary for every young medical physicist, but that good billing knowledge could provide a valuable contribution to his/her medical physics development. Learning Objectives: The audience will learn the basic definition of Current Procedural Terminology (CPT) codes performed in a Radiation Oncology Department. Understand the differences between hospital coding and physician-based or freestanding coding. Apply proper CPT coding for each Radiation Oncology procedure. Each procedure with its specific CPT code will be discussed in detail. The talk will focus on the process of care and use of actual workflow to understand each CPT code. Example coding of a typical Radiation Oncology procedure. Special procedure coding such as brachytherapy, proton therapy, radiosurgery, and SBRT. Maryann Abogunde – Medical physics opportunities at the Nuclear Regulatory Commission (NRC) The NRC’s responsibilities include the regulation of medical uses of byproduct (radioactive) materials and oversight of medical use end-users (licensees) through a combination of regulatory requirements, licensing, safety oversight including inspection and enforcement, operational experience evaluation, and regulatory support activities. This presentation will explore the

  3. SU-A-210-02: Medical Physics Opportunities at the NRC

    Energy Technology Data Exchange (ETDEWEB)

    Abogunde, M. [U.S. Nuclear Regulatory Commission (United States)

    2015-06-15

    The purpose of this student annual meeting is to address topics that are becoming more relevant to medical physicists, but are not frequently addressed, especially for students and trainees just entering the field. The talk is divided into two parts: medical billing and regulations. Hsinshun Wu – Why should we learn radiation oncology billing? Many medical physicists do not like to be involved with medical billing or coding during their career. They believe billing is not their responsibility and sometimes they even refuse to participate in the billing process if given the chance. This presentation will talk about a physicist’s long career and share his own experience that knowing medical billing is not only important and necessary for every young medical physicist, but that good billing knowledge could provide a valuable contribution to his/her medical physics development. Learning Objectives: The audience will learn the basic definition of Current Procedural Terminology (CPT) codes performed in a Radiation Oncology Department. Understand the differences between hospital coding and physician-based or freestanding coding. Apply proper CPT coding for each Radiation Oncology procedure. Each procedure with its specific CPT code will be discussed in detail. The talk will focus on the process of care and use of actual workflow to understand each CPT code. Example coding of a typical Radiation Oncology procedure. Special procedure coding such as brachytherapy, proton therapy, radiosurgery, and SBRT. Maryann Abogunde – Medical physics opportunities at the Nuclear Regulatory Commission (NRC) The NRC’s responsibilities include the regulation of medical uses of byproduct (radioactive) materials and oversight of medical use end-users (licensees) through a combination of regulatory requirements, licensing, safety oversight including inspection and enforcement, operational experience evaluation, and regulatory support activities. This presentation will explore the

  4. Directory of Certificates of Compliance for Radioactive Materials Packages. Summary report of NRC approved packages. Volume 1, Revision 8

    International Nuclear Information System (INIS)

    1985-10-01

    This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

  5. Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1. Revision 9

    International Nuclear Information System (INIS)

    1986-10-01

    This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and Corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Sections 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

  6. Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1, Revision 7

    International Nuclear Information System (INIS)

    1984-11-01

    This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

  7. 10 CFR 51.104 - NRC proceeding using public hearings; consideration of environmental impact statement.

    Science.gov (United States)

    2010-01-01

    ... environmental impact statement. 51.104 Section 51.104 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED....104 NRC proceeding using public hearings; consideration of environmental impact statement. (a)(1) In... scope of NEPA and this subpart are in issue, the NRC staff may not offer the final environmental impact...

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

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

  9. Changing emphasis at the NRC's Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Remick, F.J.

    1994-01-01

    One of the major objectives of the Office of Research is to ensure availability of sound technical information for timely decision making in support of the NRC's safety mission. The Office of Research is changing some of its emphasis to better meet the expected needs of the NRC's regulatory offices. Long-standing programs in support of operating reactors are nearing completion. These programs include plant aging and severe accident research for currently operating plants. This meeting will also address the new challenges faced by the NRC in its review of the advanced light water and non-light water reactors. As plant aging and severe accident research programs are nearing completion, the research activities are coming to focus on the emerging technologies, for example, digital instrumentation and control systems, both as replacement equipment for operating plants and as the technology of choice and necessity for the advanced reactors. Necessity, because analog equipment is becoming obsolete. Other examples include the use of new materials in operating plants, human factors considerations in the design and operation of the advanced plants, thermal-hydraulic characteristics of the advanced reactors, and new construction techniques

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

    International Nuclear Information System (INIS)

    1994-03-01

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

  11. The Rorschach Egocentricity Index in subjects with intellectual disability: a study on the incidence of different psychological pathologies.

    Science.gov (United States)

    Colucci, G; Pellicciotta, A; Buono, S; Di Nuovo, S F

    1998-10-01

    The aims of the present research were to assess the level of self-concern in people with intellectual disability using the Rorschach Egocentricity Index, to correlate the Index with other Rorschach and IQ variables, and to study the effect of associated psychological pathology. The Rorschach Inkblot Test and the Wechsler Intelligence Scale were administered to a group of 75 subjects with intellectual disability, aged between 18 and 38 years, who were divided into subgroups according to their additional diagnosis (i.e. personality disorders, psychosis and depression). A fourth subgroup was composed of people with intellectual disability but without other pathologies. The Egocentricity Index was very low in the subjects with intellectual disability and differences were a result of the effects of additional psychological pathologies. The meaning of the measurement of egocentricity in people with intellectual disability is discussed.

  12. INDEX - a solution to the high cost of processing transient workers

    International Nuclear Information System (INIS)

    Stroupe, E.P.

    1987-01-01

    In 1985 twelve midwestern utilities formed the Nuclear Employee Data System for the US Nuclear Regulatory Commission's (NRC's) Region III (NEDS III) group. These utilities are Cleveland Electric Illuminating Company, Commonwealth Edison Company, Consumers Power Company, Detroit Edison Company, Illinois Power Company, Indiana and Michigan Electric Company, Iowa Electric Light and Power Company, Northern States Power Company, Toledo Edison Company, Union Electric Company, and Wisconsin Public Service Corporation. Early in 1986, Kansas Gas and Electric of NRC's Region IV joined the group and a cost-benefit study of a nuclear employee data system was initiated. The purpose of this system is to reduce the cost of processing workers requiring unescorted access to nuclear power plants. The involved utilities continued this project as the Integrated Nuclear Data Exchange (INDEX). In 1987 the following additional utilities joined INDEX: Houston Lighting and Power, Pacific Gas and Electric, Texas Utilities Electric Company, Arkansas Power and Light, Louisiana Power and Light, Systems Energy Resources Inc., and Southern California Edison. This paper summarizes the results of the study and discusses the current status of the program

  13. Safeguards Summary Event List (SSEL). Pre-NRC-June 30, 1985. Revision 11

    International Nuclear Information System (INIS)

    1986-01-01

    The Safeguards Summary Event List (SSRL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels. 12 figs

  14. 48 CFR 2009.570 - NRC organizational conflicts of interest.

    Science.gov (United States)

    2010-10-01

    ... conflicts of interest. 2009.570 Section 2009.570 Federal Acquisition Regulations System NUCLEAR REGULATORY COMMISSION COMPETITION AND ACQUISITION PLANNING CONTRACTOR QUALIFICATIONS Organizational Conflicts of Interest 2009.570 NRC organizational conflicts of interest. ...

  15. In vivo monitoring of nuclear research centre (NRC) workers. Vol. 4

    Energy Technology Data Exchange (ETDEWEB)

    Gomaa, M A; Ali, E M; Taha, T M [Radiation Protection Departion, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

    1996-03-01

    Occupational workers of Nuclear research center (NRC) of atomic energy authority (AEA) working with radio-nuclides such as (Cs-137, I-131, and I-125) are monitored yearly. Individuals involved in routine work in hot laboratories are examined every three months. When an incident occurs, the workers involved are examined promptly. In order to measure internal contamination, the modified NRC-AEA whole body counter is used. More than hundred occupational workers had been examined in 1994. Results indicated that the annual limit of intake as recommended by ICRP was not exceeded. 3 figs., 3 tabs.

  16. NRC research on the application of advanced I and C technology to commercial nuclear power plants

    International Nuclear Information System (INIS)

    Gollei, K.R.; Hon, A.L.

    1983-01-01

    The operational safety and efficiency of commercial nuclear power plants (NPP's) could possibly be enhanced by utilizing advanced instrumentation and control technology developed by other industries. The NRC is interested in learning about new I and C technology that probably will or could be applied to new or existing plants. This would enable the NRC to be better prepared to evaluate the application without undue delays. It would also help identify any appropriate changes in NRC regulations or guidance necessary to facilitate the application of advanced IandC technology to NPP's. The NRC has initiated a project to work cooperatively with the advanced technology industry, power industry, EPRI, and technical organizations such as ISA toward this goal. This paper describes the objectives and plans of this cooperative effort. It summarizes the highlights of some of the advanced technology already being evaluated by NRC such as microprocessor applications, instruments to detect inadequate core cooling and other two-phase flow measurements, reactor noise surveillance and diagnostic techniques. This paper also suggests potential candidates for consideration such as utilization of advanced instruments for LOCA experiments. It also identifies some of the potential challenges facing the application of advanced technology to NPP's. It concludes that close cooperation between NRC and industry is essential for the success of such applications

  17. NRC approach to evaluating training effectiveness in accordance with the policy statement on training

    International Nuclear Information System (INIS)

    Persensky, J.J.; Blumer, A.H.

    1985-01-01

    The activity of the past two years has provided an opportunity for the NRC to examine and realign the way in which it views the training process. In the process, it has provided the industry with an incentive to emphasize training as an opportunity for enlightened self-regulation. As a result, the NRC and industry perspectives on training have, for all intents and purposes, merged into a single performance orientation. This cooperation should provide the needed momentum towards improvements in training effectiveness. It is the NRC's goal to monitor this momentum and to encourage progress toward the ideal of systematic, performance-based training for all essential personnel in the nuclear industry

  18. Association between subjective actual sleep duration, subjective sleep need, age, body mass index, and gender in a large sample of young adults.

    Science.gov (United States)

    Kalak, Nadeem; Brand, Serge; Beck, Johannes; Holsboer-Trachsler, Edith; Wollmer, M Axel

    2015-01-01

    Poor sleep is a major health concern, and there is evidence that young adults are at increased risk of suffering from poor sleep. There is also evidence that sleep duration can vary as a function of gender and body mass index (BMI). We sought to replicate these findings in a large sample of young adults, and also tested the hypothesis that a smaller gap between subjective sleep duration and subjective sleep need is associated with a greater feeling of being restored. A total of 2,929 university students (mean age 23.24±3.13 years, 69.1% female) took part in an Internet-based survey. They answered questions related to demographics and subjective sleep patterns. We found no gender differences in subjective sleep duration, subjective sleep need, BMI, age, or feeling of being restored. Nonlinear associations were observed between subjective sleep duration, BMI, and feeling of being restored. Moreover, a larger discrepancy between subjective actual sleep duration and subjective sleep need was associated with a lower feeling of being restored. The present pattern of results from a large sample of young adults suggests that males and females do not differ with respect to subjective sleep duration, BMI, or feeling of being restored. Moreover, nonlinear correlations seemed to provide a more accurate reflection of the relationship between subjective sleep and demographic variables.

  19. Implementation study for the NRC Application and Development Facility

    International Nuclear Information System (INIS)

    Sherwood, R.J.; Ross, D.J.; Sasser, D.W.

    1979-01-01

    The Nuclear Regulatory Commission (NRC) has expressed the desire to establish an Application and Development Facility (ADF) for NRC Headquarters. The ADF is a computer system which will provide safeguards analysts access to safeguards analysis computer software. This report analyzes the issues, requirements and options available in the establishment of an ADF. The purpose and goals of the ADF are presented, along with some general issues to be considered in the implementation of such a system. A phased approach for ADF implementation, which will allow for the earliest possible access to existing codes and also allow for future expansion, is outlined. Several options for central computers are discussed, along with the characteristics and approximate costs for each. The report concludes with recommended actions proposed to start the development of the ADF

  20. The glycaemic index values of foods containing fructose are affected by metabolic differences between subjects.

    Science.gov (United States)

    Wolever, T M S; Jenkins, A L; Vuksan, V; Campbell, J

    2009-09-01

    Glycaemic responses are influenced by carbohydrate absorption rate, type of monosaccharide absorbed and the presence of fat; the effect of some of these factors may be modulated by metabolic differences between subjects. We hypothesized that glycaemic index (GI) values are affected by the metabolic differences between subjects for foods containing fructose or fat, but not for starchy foods. The GI values of white bread (WB), fruit leather (FL) and chocolate-chip cookies (CCC) (representing starch, fructose and fat, respectively) were determined in subjects (n=77) recruited to represent all 16 possible combinations of age (40 years), sex (male, female), ethnicity (Caucasian, non-Caucasian) and body mass index (BMI) (25 kg/m2) using glucose as the reference. At screening, fasting insulin, lipids, c-reactive protein (CRP), aspartate transaminase (AST) and waist circumference (WC) were measured. There were no significant main effects of age, sex, BMI or ethnicity on GI, but there were several food x subject-factor interactions. Different factors affected each food's area under the curve (AUC) and GI. The AUC after oral glucose was related to ethnicity, age and triglycerides (r 2=0.27); after WB to ethnicity, age, triglycerides, sex and CRP (r 2=0.43); after CCC to age and weight (r 2=0.18); and after FL to age and CRP (r 2=0.12). GI of WB was related to ethnicity (r 2=0.12) and of FL to AST, insulin and WC (r 2=0.23); but there were no significant correlations for CCC. The GI values of foods containing fructose might be influenced by metabolic differences between -subjects, whereas the GI of starchy foods might be affected by ethnicity. However, the proportion of variation explained by subject factors is small.

  1. NRC Regulatory Agenda. Quarterly report, July-September 1985

    International Nuclear Information System (INIS)

    1985-10-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

  2. NRC Regulatory Agenda: Quarterly report, January--March 1988

    International Nuclear Information System (INIS)

    1988-07-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

  3. NRC Regulatory Agenda. Quarterly report, July-September 1982

    International Nuclear Information System (INIS)

    1982-10-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received and are pending disposition by the Commission. The agenda consists of two sections. Section I, Rules, includes: (1) rules on which final action has been taken since June 30, the cutoff date of the last Regulatory Agenda; (2) rules published previously as proposed rules and on which the Commission has not taken final action; (3) rules published as advance notices of proposed rulemaking and for which neither a proposed nor final rule has been issued; and (4) unpublished rules on which the NRC expects to take action. Section II, Petitions for Rulemaking, includes: (1) Petitions incorporated into final rules or petitions denied since the cutoff date of the last Regulatory Agenda; (2) Petitions incorporated into proposed rules, (3) Petitions pending staff review; and (4) Petitions with deferred action

  4. Safeguards Summary Event List (SSEL), Pre-NRC through December 31, 1983. Rev. 9

    International Nuclear Information System (INIS)

    1984-06-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing/allegedly stolen, transportation, tampering/vandalism, arson, firearms-related, radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  5. Geotechnical engineering considerations in the NRC's review of uranium mill tailings remedial action plans

    International Nuclear Information System (INIS)

    Gillen, D.M.

    1985-01-01

    To reduce potential health hazards associated with inactive uranium mill tailings sites, the Department of Energy (DOE) is presently investigating and implementing remedial actions at 24 sites in the Uranium Mill Tailings Remedial Action Program (UMTRAP). All remedial actions must be selected and performed with the concurrence of the Nuclear Regulatory Commission (NRC). This paper provides a discussion of geotechnical engineering considerations during the NRC's preconcurrence review of proposed remedial action plans. In order for the NRC staff to perform an adequate geotechnical engineering review, DOE documents must contain a presentation of the properties and stability of all in-situ and engineered soil and rock which may affect the ability of the remedial action plans to meet EPA standards for long-term stability and control. Site investigations, laboratory testing, and remedial action designs must be adequate in scope and technique to provide sufficient data for the NRC staff to independently evaluate static and dynamic stability, settlement, radon attenuation through the soil cover, durability of rock for erosion protection, and other geotechnical engineering factors

  6. Optimization Conditions of Extracellular Proteases Production from a Newly Isolated Streptomyces Pseudogrisiolus NRC-15

    Directory of Open Access Journals (Sweden)

    El-Sayed E. Mostafa

    2012-01-01

    Full Text Available Microbial protease represents the most important industrial enzymes, which have an active role in biotechnological processes. The objective of this study was to isolate new strain of Streptomyces that produce proteolytic enzymes with novel properties and the development of the low-cost medium. An alkaline protease producer strain NRC-15 was isolated from Egyptian soil sample. The cultural, morphological, physiological characters and chemotaxonomic evidence strongly indicated that the NRC-15 strain represents a novel species of the genus Streptomyces, hence the name Strptomyces pseudogrisiolus NRC-15. The culture conditions for higher protease production by NRC-15 were optimized with respect to carbon and nitrogen sources, metal ions, pH and temperature. Maximum protease production was obtained in the medium supplemented with 1% glucose, 1% yeast extract, 6% NaCl and 100 μmol/L of Tween 20, initial pH 9.0 at 50 °C for 96 h. The current results confirm that for this strain, a great ability to produce alkaline proteases, which supports the use of applications in industry.

  7. Safeguards Summary Event List (SSEL). Pre-NRC through December 31, 1984. Revision 10

    International Nuclear Information System (INIS)

    1985-05-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage and miscellaneous. The information contained in the event descriptions in derived primarily from official NRC reporting channels

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms, and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to

  9. Summary of NRC LWR safety research programs on fuel behavior, metallurgy/materials and operational safety

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1979-09-01

    The NRC light-water reactor safety-research program is part of the NRC regulatory program for ensuring the safety of nuclear power plants. This paper summarizes the results of NRC-sponsored research into fuel behavior, metallurgy and materials, and operational safety. The fuel behavior research program provides a detailed understanding of the response of nuclear fuel assemblies to postulated off-normal or accident conditions. Fuel behavior research includes studies of basic fuel rod properties, in-reactor tests, computer code development, fission product release and fuel meltdown. The metallurgy and materials research program provides independent confirmation of the safe design of reactor vessels and piping. This program includes studies on fracture mechanics, irradiation embrittlement, stress corrosion, crack growth, and nondestructive examination. The operational safety research provides direct assistance to NRC officials concerned with the operational and operational-safety aspects of nuclear power plants. The topics currently being addressed include qualification testing evaluation, fire protection, human factors, and noise diagnostics

  10. Licensing considerations in converting NRC-licensed non-power reactors from high-enriched to low-enriched uranium fuels

    International Nuclear Information System (INIS)

    Carter, R.E.

    1985-01-01

    During the mid-1970s, there was increasing concern with the possibility that highly enriched uranium (HEU), widely used in non-power reactors around the world, might be diverted from its intended peaceful uses. In 1982 the U.S. Nuclear Regulatory Commission (NRC) issued a policy statement that was intended to conform with the perceived international thinking, and that addressed the two relevant areas in which NRC has statutory responsibility, namely, export of special nuclear materials for non-USA non-power reactors, and the licensing of USA-based non-power reactors not owned by the Federal government. To further address the second area, NRC issued a proposed rule for public comment that would require all NRC-licensed non-power reactors using HEU to convert to low enriched uranium (LEU) fuel, unless they could demonstrate a unique purpose. Currently the NRC staff is revising the proposed rule. An underlying principle guiding the staff is that as long as a change in enrichment does not lead to safety-related reactor modifications, and does not involve an unreviewed safety question, the licensee could convert the core without prior NRC approval. At the time of writing this paper, a regulatory method of achieving this principle has not been finalized. (author)

  11. Licensing considerations in converting NRC-licensed non-power reactors from high-enriched to low-enriched uranium fuels

    Energy Technology Data Exchange (ETDEWEB)

    Carter, R E

    1985-07-01

    During the mid-1970s, there was increasing concern with the possibility that highly enriched uranium (HEU), widely used in non-power reactors around the world, might be diverted from its intended peaceful uses. In 1982 the U.S. Nuclear Regulatory Commission (NRC) issued a policy statement that was intended to conform with the perceived international thinking, and that addressed the two relevant areas in which NRC has statutory responsibility, namely, export of special nuclear materials for non-USA non-power reactors, and the licensing of USA-based non-power reactors not owned by the Federal government. To further address the second area, NRC issued a proposed rule for public comment that would require all NRC-licensed non-power reactors using HEU to convert to low enriched uranium (LEU) fuel, unless they could demonstrate a unique purpose. Currently the NRC staff is revising the proposed rule. An underlying principle guiding the staff is that as long as a change in enrichment does not lead to safety-related reactor modifications, and does not involve an unreviewed safety question, the licensee could convert the core without prior NRC approval. At the time of writing this paper, a regulatory method of achieving this principle has not been finalized. (author)

  12. A simple program to reduce the stress associated with NRC nuclear operator examinations

    International Nuclear Information System (INIS)

    Sajwau, T.; Chardos, S.

    1988-01-01

    The NRC license for nuclear reactor operators requires periodic written examinations to demonstrate ongoing technical competency. Poor performance raises a competency question and can affect the individuals' careers. Accordingly, the exams can be highly stressful events. Stress has been demonstrated to affect memory, perception, other cognitive attitudes, and test performance. The phenomenon of test anxiety is well known. Instead of a generic, broadly focused stress management approach, a sharply focused, two-part program was developed for TVA operators scheduled to take the NRC examination. The first part was presented early in preparatory training, and the second part was given just prior to the examination. The first part consisted of a simple model of stress found in exams, early warning signs of test stress, and tactics of stress management that were practical to use during the NRC exam itself

  13. International cooperation during radiological emergencies. NRC program guidance for the provision of technical advice to foreign counterpart organizations

    International Nuclear Information System (INIS)

    Senseney, R.

    1986-04-01

    This report defines the scope, application, and limits of the technical cooperation the Nuclear Regulatory Commission (NRC) would provide, upon request, to a foreign regulatory agency in a nuclear emergency. It outlines the basis for such cooperation, offers a model written agreement, and describes recent cases of NRC assistance. It also identifies non-NRC sources of emergency advisory assistance available to foreign organizations

  14. NRC Bulletin No. 87-02, Supplement 1: Fastener testing to determine conformance with applicable material specifications

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    Item 5 of NRC Compliance Bulletin 87-02 requested that all holders of operating licenses or construction permits for nuclear power reactors information regarding the identity of the suppliers and manufacturers of the safety-related and non-safety-related fasteners selected for testing. After further consideration, the NRC has determined that it needs information regarding the identity of all vendors from which safety-related and non-safety-related fasteners have been obtained within the past 10 years, a reasonable period which will not put undue burden on addressees. This information will assist the NRC in determining whether nuclear facility fasteners in use have been supplied in accordance with their intended use. In addition, this information is needed so that the NRC can properly coordinate information with other government agencies concerned with problems identified in the quality of fasteners

  15. Pilot program: NRC severe reactor accident incident response training manual: Severe reactor accident overview

    International Nuclear Information System (INIS)

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

    1987-02-01

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Severe Reactor Accident Overview is the second in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assesment. Each volume serves, respectively, as the text for a course of instruction in a series of courses. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  16. Subjective and psychophysiological indexes of listening effort in a competing-talker task.

    Science.gov (United States)

    Mackersie, Carol L; Cones, Heather

    2011-02-01

    The effects of noise and other competing backgrounds on speech recognition performance are well documented. There is less information, however, on listening effort and stress experienced by listeners during a speech-recognition task that requires inhibition of competing sounds. The purpose was (a) to determine if psychophysiological indexes of listening effort were more sensitive than performance measures (percentage correct) obtained near ceiling level during a competing speech task, (b) to determine the relative sensitivity of four psychophysiological measures to changes in task demand, and (c) to determine the relationships between changes in psychophysiological measures and changes in subjective ratings of stress and workload. A repeated-measures experimental design was used to examine changes in performance, psychophysiological measures, and subjective ratings in response to increasing task demand. Fifteen adults with normal hearing participated in the study. The mean age of the participants was 27 (range: 24-54). Psychophysiological recordings of heart rate, skin conductance, skin temperature, and electromyographic (EMG) activity were obtained during listening tasks of varying demand. Materials from the Dichotic Digits Test were used to modulate task demand. The three levels of task demand were single digits presented to one ear (low-demand reference condition), single digits presented simultaneously to both ears (medium demand), and a series of two digits presented simultaneously to both ears (high demand). Participants were asked to repeat all the digits they heard, while psychophysiological activity was recorded simultaneously. Subjective ratings of task load were obtained after each condition using the National Aeronautics and Space Administration Task Load Index questionnaire. Repeated-measures analyses of variance were completed for each measure using task demand and session as factors. Mean performance was higher than 96% for all listening tasks. There

  17. Safeguards Summary Event List (SSEL), pre-NRC through December 31, 1989

    International Nuclear Information System (INIS)

    1990-07-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, alcohol and drugs (involving reactor operators, security force members, or management persons), and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  18. NRC assessment of the high-level waste repository quality assurance program

    International Nuclear Information System (INIS)

    Kennedy, J.E.

    1987-01-01

    As part of its licensing responsibilities, the NRC is independently reviewing the DOE quality assurance program applied to the site characterization phase activities. Data collected and other information generated during this phase of the program will ultimately be used in a license application to demonstrate the suitability of one site for long-term isolation of waste. They must therefore fall under the quality assurance program to provide confidence in their adequacy. This NRC review consists of three main activities: development of staff guidance on quality assurance measures appropriate for site characterization activities; review of DOE QA plans and procedures; and audits and other reviews of the implementation of the program

  19. 76 FR 54507 - Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for...

    Science.gov (United States)

    2011-09-01

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0204] Proposed Generic Communication; Draft NRC Generic... functions. SSCs in operating nuclear power plants are designed either in accordance with, or have been... nuclear reactors. The background information relevant to this GL includes the individual plant...

  20. Pilot program: NRC severe reactor accident incident response training manual: Public protective actions: Predetermined criteria and initial actions

    International Nuclear Information System (INIS)

    Martin, J.A. Jr.; McKenna, T.J.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

    1987-02-01

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Public Protective Actions - Predetermined Criteria and Initial Actions is the fourth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume reviews public protective action criteria and objectives, their bases and implementation, and the expected public response. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  1. NRC Information No. 88-04: Inadequate qualification and documentation of fire barrier penetration seals

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    The current NRC review was prompted by reports, inspection findings, allegations, and other information that indicated the possibility that NRC requirements for fire barrier penetration seals were not being met in all aspects. The review included: evaluations of fire barrier penetration seal specifications and procedures developed by licensees, licensee agents, and licensee contractors; evaluations of various fire barrier penetration seal tests and test data; and inspections of various fire barrier penetrations seal designs and installations. The types of concerns identified to date and mentioned below are related to weaknesses in the implementation of NRC requirements and guidelines as related to fire barrier penetration seal design qualification. The NRC review also has identified a current practice that can affect the qualification status of installed seals. Plant modifications are being made that require running new cable and conduits through existing penetration seals. These modifications are generally being made without an associated technical review to ensure that the resulting penetration seal design configuration or design parameters are consistent with those validated by initial qualification tests. Over a period of time, numerous minor modifications to the same area could cumulatively result in a degraded fire barrier rating

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

    International Nuclear Information System (INIS)

    Weiss, S.H.

    1988-01-01

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

  3. Expression and purification of toxic anti-breast cancer p28-NRC chimeric protein

    OpenAIRE

    Soleimani, Meysam; Mirmohammad-Sadeghi, Hamid; Sadeghi-Aliabadi, Hojjat; Jahanian-Najafabadi, Ali

    2016-01-01

    Background: Chimeric proteins consisting of a targeting moiety and a cytotoxic moiety are now under intense research focus for targeted therapy of cancer. Here, we report cloning, expression, and purification of such a targeted chimeric protein made up of p28 peptide as both targeting and anticancer moiety fused to NRC peptide as a cytotoxic moiety. However, since the antimicrobial activity of the NRC peptide would intervene expression of the chimeric protein in Escherichia coli, we evaluated...

  4. NRC Support for the Kalinin (VVER) probabilistic risk assessment

    International Nuclear Information System (INIS)

    Bley, D.; Diamond, D.J.; Chu, T.L.; Azarm, A.; Pratt, W.T.; Johnson, D.; Szukiewicz, A.; Drouin, M.; El-Bassioni, A.; Su, T.M.

    1998-01-01

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

  5. Relationship of body mass index, ankle dorsiflexion, and foot pronation on plantar fascia thickness in healthy, asymptomatic subjects.

    Science.gov (United States)

    Pascual Huerta, Javier; García, Juan Maria Alarcón; Matamoros, Eva Cosin; Matamoros, Julia Cosin; Martínez, Teresa Díaz

    2008-01-01

    We sought to investigate the thickness of plantar fascia, measured by means of ultrasonographic evaluation in healthy, asymptomatic subjects, and its relationship to body mass index, ankle joint dorsiflexion range of motion, and foot pronation in static stance. One hundred two feet of 51 healthy volunteers were examined. Sonographic evaluation with a 10-MHz linear array transducer was performed 1 and 2 cm distal to its insertion. Physical examination was also performed to assess body mass index, ankle joint dorsiflexion, and degree of foot pronation in static stance. Both examinations were performed in a blinded manner. Body mass index showed moderate correlation with plantar fascia thickness at the 1- and 2-cm locations. Ankle dorsiflexion range of motion showed no correlation at either location. Foot pronation showed an inverse correlation with plantar fascia thickness at the 2-cm location and no correlation at the 1-cm location. Body mass index and foot supination at the subtalar joint are related to increased thickness at the plantar fascia in healthy, asymptomatic subjects. Although the changes in thickness were small compared with those in patients with symptomatic plantar fasciitis, they could play a role in the mechanical properties of plantar fascia and in the development of plantar fasciitis.

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  7. Assessment of current NRC/IE professional training program and recommendations for improvement

    International Nuclear Information System (INIS)

    Bartley, H.J.; Hagerup, J.E.; Harrison, O.J.; Heyer, F.H.K.; Kaas, I.W.; Schwartz, E.G.

    1978-05-01

    This document is the General Research Corporation (GRC) report on Task III: to assess the current NRC/IE professional training program and to provide recommendations for improvement. The major objectives of this task were to determine the overall effectiveness of the NRC/IE training program and to provide recommendations for improvements where appropriate. The research involved a review of course manuals and of student critiques, observation in the classroom and person to person interviews; it also included an evaluation of the assignment of instructors to the Career Management Branch. Findings addressed refresher training, retread training and initial training--with emphasis on the last of these. Conclusions are that: (1) The curriculum provides, in general, types and levels of training needed; (2) the mix of training methods used is correct; and (3) the training management is effective. However, the training facilities do not reflect a commitment to quality instruction nor is assignment as instructor to the Career Management Branch attractive to inspectors. Recommendations presented in the report are based upon the findings; all lie within the implementing authority of Headquarters NRC/IE

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

    International Nuclear Information System (INIS)

    BLACK, D.M.

    1999-01-01

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

  9. Review of NRC Regulatory processes and functions

    International Nuclear Information System (INIS)

    1980-01-01

    The Advisory Committee on Reactor Safeguards (ACRS) has spent much time over many years observing and examining the NRC licensing process. The Committee is, consequently, in a position to comment on the situation, and it believes this review will be helpful to those examining the regulatory process by discussing how it works, where it is weak, and the opportunities for improvement. The Committee's review may also help put current proposals and discussions in perspective

  10. Investigation and consideration on the framework of oversight-based safety regulation. U.S. NRC 'Risk-Informed, Performance-Based' Regulation

    International Nuclear Information System (INIS)

    Saji, Gen

    2001-01-01

    Regulation on safety, environment and health in Japan has before today been intended to correspond with an accident at forms of reinforcement of national standards and monitoring, if any. However, as it was thought that such regulation reinforcement was afraid to bring some social rigidity, and to weaken independent responsibility, as a result, because of anxiety of losing peoples' merits inversely, some fundamental directivity such as respect of self-responsibility principle' and 'necessary and least limit of regulation' were selected as a part of political innovation. On the other hand, at a background of wide improvements on various indexing values showing operation results of nuclear power stations in U.S.A., private independent effort on upgrading of safety is told to largely affect at beginning of INPO (Institute of Nuclear Power Operations), without regulation reinforcement of NRC side. This is a proof of concrete effect of transfer to oversight-based safety regulation. Here were introduced on nuclear safety in U.S.A. at a base of some references obtained on entering the 'MIT summer specialist program. Nuclear system safety', on focussing at new safety regulation of NRC and its effect and so on, and adding some considerations based on some knowledge thereafter. (G.K.)

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

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1995-11-01

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

  12. Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC approved packages

    International Nuclear Information System (INIS)

    1988-12-01

    This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  13. Directory of certificates of compliance for radioactive materials packages, Report of NRC approved packages

    International Nuclear Information System (INIS)

    1990-10-01

    This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Materials Packages effective October 1, 1990. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  14. NRC levies $62 100 fee for FY 1993 on all licensees

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The Nuclear Regulatory Commission has issued its final rule on fee collections for fiscal year 1993, partly in response to a court decision that challenged the agency's FY 1991 fee schedule. Because the NRC must recover all of its annual budget - in excess of $500 million - through fees on licensees and users of agency services, those licensees and users are very sensitive about who shoulders how much of the burden. The new rule voids the previous NRC policy of exempting nonprofit educational institutions from the fee schedule, and the allocation of generic costs for low-level waste management to groups of licensees, rather than to individual licensees. The new rule went into effect on August 19

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

    International Nuclear Information System (INIS)

    Bernholdt, David E.

    2012-01-01

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

  16. NRC nuclear-plant-analyzer concept and status at INEL

    International Nuclear Information System (INIS)

    Aguilar, F.; Wagner, R.J.

    1982-01-01

    The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

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

    Energy Technology Data Exchange (ETDEWEB)

    Bernholdt, David E [ORNL

    2012-06-01

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

  18. MHTGR demonstration role in the NRC design certification process

    International Nuclear Information System (INIS)

    Kelley, A.P. Jr.; Jones, G.

    1986-01-01

    A modular high-temperature gas-cooled reactor (MHTGR) design is being developed by the US HTGR Program. Because of the small size of the individual modules that would make up a commercial facility, it appears feasible to design and construct a single-module demonstration plant within the funding constraints on the public and private-sector program participants. Furthermore, the safety margins that can be made inherent to the design permit full-scale testing that could supply a new basis for demonstrating investment protection and safety adequacy to the public, the US Nuclear Regulatory Commission (NRC), and potential users. With this in mind, a Project Definition Study was sponsored by Gas-Cooled Reactor Associates and the Tennessee Valley Authority to study the potential benefits of undertaking such a demonstration project. One of the areas investigated was the potential benefits of such a facility in supporting the NRC design certification process, which is envisioned as a necessary commercialization step for the MHTGR

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

    Energy Technology Data Exchange (ETDEWEB)

    Rathbun, H.J.

    1996-12-01

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

  20. Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

    International Nuclear Information System (INIS)

    McKenna, T.J.; Martin, J.A. Jr.; Giitter, J.G.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Watkins

    1987-02-01

    Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

  1. NRC regulatory uses of PSA

    International Nuclear Information System (INIS)

    Murley, T.E.

    1991-01-01

    The publication in 1975 of WASH-1400, with its new probabilistic safety assessment (PSA) methodology, had the effect of presenting a pair of eyeglasses to a man with poor eyesight. Suddenly, it gave us a view of nuclear safety with a new clarity, and it allowed us to sort out the important safety issues from the unimportant. In the intervening years, PSA insights have permeated the fabric of nearly all our safety judgments. This acceptance can be seen from the following list of broad areas where the Nuclear Regulatory Commission (NRC) staff uses PSA insights and methodology: evaluating the safety significance of operating events and recommending safety improvements where warranted; requesting licensees to systematically look for design vulnerabilities in each operating reactor; evaluating the safety significance of design weaknesses or non-compliances when judging the time frame for necessary improvements; conducting sensitivity analyses to judge where safety improvements are most effective; assessing the relative safety benefits of design features for future reactors. In judging where PSA methodology can be improved to give better safety insights, it is believed that the following areas need more attention: better modeling of cognitive errors; more comprehensive modeling of accident sequences initiated from conditions other than full power; more comprehensive modeling of inter-system loss of coolant accident (ISLOCA) sequences. Although PSA is widely used in the staff's regulatory activities, the NRC deliberately chooses not to include probabilistic prescriptions in regulations or guidance documents. The staff finds the bottom line risk estimates to be one of the least reliable products of a PSA. The reason for this view is that PSA cannot adequately address cognitive errors nor assess the effects of a pervasive poor safety attitude

  2. NRC's license renewal regulations

    International Nuclear Information System (INIS)

    Akstulewicz, Francis

    1991-01-01

    In order to provide for the continuity of the current generation of nuclear power plant operating licenses and at the same time ensure the health and safety of the public, and the quality of the environment, the US Nuclear Regulatory Commission (NRC) established a goal of developing and issuing regulations and regulatory guidance for license renewal in the early 1990s. This paper will discuss some of those activities underway to achieve this goal. More specifically, this paper will discuss the Commission's regulatory philosophy for license renewal and the two major license renewal rule makings currently underway. The first is the development of a new Part 54 to address procedural and technical requirements for license renewal; the second is a revision to existing Part 51 to exclude environmental issues and impacts from consideration during the license renewal process. (author)

  3. Compilation of fastener testing data received in response to NRC Compliance Bulletin 87-02

    International Nuclear Information System (INIS)

    Cwalina, G.C.; Conway, J.T.; Parker, L.B.

    1989-06-01

    On November 6, 1987, the Nuclear Regulatory Commission (NRC) issued Bulletin 87-02, ''Fastener Testing to Determine Conformance With Applicable Material Specifications,'' to all holders of operating licenses or construction permits for nuclear power reactors (licensees). The bulletin was issued so that the NRC staff could gather data to determine whether counterfeit fasteners are a problem in the nuclear power industry. The bulletin requested nuclear power plant owners to determine whether fasteners obtained from suppliers and/or manufacturers for use in their facilities meet the mechanical and chemical specifications stipulated in the procurement documents. The licensees were requested to sample a minimum of 10 safety-related and 10 non-safety-related fasteners (studs, bolts, and/or cap screws) and a sample of typical nuts that would be used with each fastener and to report the testing results to the NRC. The results of this study did not indicate a safety concern relating to the use of mismarked or counterfeit fasteners in the nuclear industry, but they did indicate a nonconformance rate of 8 to 12 percent for fasteners. The NRC staff is considering taking action to improve the effectiveness of receipt inspection and testing programs for all materials at nuclear power plants

  4. 76 FR 40755 - Impact of Reduced Dose Limits on NRC Licensed Activities; Solicitation of Public Comment

    Science.gov (United States)

    2011-07-11

    ... scientifically justified, to achieve greater alignment with the 2007 recommendations of the International... and image files of the NRC's public documents. If you do not have access to ADAMS or if there are... informed of all the benefits and burdens associated with further alignment of NRC's current radiation...

  5. NRC licensing requirements: DOD options

    International Nuclear Information System (INIS)

    Pike, W.J.; O'Reilly, P.D.

    1982-09-01

    This report describes the licensing process (both safety and environmental) that would apply if the Department of Defense (DOD) chooses to obtain licenses from the US Nuclear Regulatory Commission (NRC) for using nuclear energy for power and luminous sources. The specific nuclear energy sources being considered include: small or medium-size nuclear power reactors; radioisotopic thermoelectric generators with 90 Sr or 238 Pu; radioisotopic dynamic electric generators with 90 Sr or 238 Pu; and applications of radioisotopes for luminous sources (lights) with 3 H, 85 Kr, or 147 Pm. The steps of the licensing process are summarized in the following sections, with particular attention given to the schedule and level of effort necessary to support the process

  6. The role of research in nuclear regulation: An NRC perspective

    International Nuclear Information System (INIS)

    Morrison, D.L.

    1997-01-01

    The role of research in the US Nuclear Regulatory Commission was broadly defined by the US Congress in the Energy Reorganization Act of 1975. This Act empowered the Commission to do research that it deems necessary for the performance of its licensing and regulatory functions. Congress cited a need for an independent capability that would support the licensing and regulatory process through the development and analysis of technical information related to reactor safety, safeguards and environmental protection. Motivation for establishing such a safety research function within the regulatory agency is the need to address the defects, abnormal occurrences and shutdowns involving light water reactors. Congress further stated that the NRC should limit its research to open-quotes confirmatory assessmentclose quotes and that the Agency open-quotes should never be placed in a position to generate, and then have to defend, basic design data of its own.close quotes The author reviews the activities of the research arm as related to regulatory research, performed in the past, today, and projected for the future. NRC's public health and safety mission demands that its research products be developed independently from its licensees; be credible and of the highest technical quality as established through peer review; and open to the public scrutiny through publication in technical journals as well as NRC documents. A special trust is placed on regulatory research through the products it produces as well as the three dimensions that underlie the processes through which they are produced

  7. Low-level mixed waste: An RCRA perspective for NRC licensees

    International Nuclear Information System (INIS)

    1990-08-01

    The publication presents an overview of RCRA requirements for commercially-generated low-level mixed waste. It is designed for Nuclear Regulatory Commission (NRC) licensees who may not be familiar with EPA regulations that apply to their waste products

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

    International Nuclear Information System (INIS)

    Fresco, A.; Gunther, W.

    1991-01-01

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

  9. Developing an Index of Deprivation Which Integrates Objective and Subjective Dimensions: Extending the Work of Townsend, Mack and Lansley, and Hallerod

    Science.gov (United States)

    Eroglu, Sebnem

    2007-01-01

    This article presents a new approach to index development, extending the methods used by Townsend, Mack and Lansley and Hallerod to measure deprivation in the developed world. The index combines three "objective" dimensions of deprivation (i.e. monetary, consumption and work-related), and weighs them according to subjective perceptions…

  10. Information to licensees regarding two NRC Inspection Manual sections on resolution of degraded and nonconforming conditions and on operability (Generic Letter 91-18)

    International Nuclear Information System (INIS)

    Partlow, J.G.

    1992-01-01

    The NRC staff has issued two sections to be included in Part 9900, Technical Guidance, of the NRC Inspection Manual. The first is, ''Resolution of Degraded and Nonconforming Conditions.'' The second is, ''Operable/Operability: Ensuring the Functional Capability of a System or Component.'' Copies of the additions to the NRC Inspection Manual are provided for information only. No specific licensee actions are required. The additions to the NRC Inspection Manual are based upon previously issued guidance. However, because of the complexity involved in operability determinations and the resolution of degraded and nonconforming conditions, there have been differences in application by NRC staff during past inspection activities. Thus, the purpose of publishing this guidance is to ensure consistency in application of this guidance by the NRC. Regional inspection personnel have been briefed on this guidance. The NRC will conduct further training on these topics to ensure uniform staff understanding

  11. Berkeley Lab Pilot on External Regulation of DOE National Laboratories by the U.S. NRC

    International Nuclear Information System (INIS)

    Zeman, Gary H.

    1999-01-01

    The US Department of Energy and the US Nuclear Regulatory Commission entered into an agreement in November 1997 to pursue external regulation of radiation safety at DOE national laboratories through a Pilot Program of simulated regulation at 6-10 sites over a 2 year period. The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab), the oldest of the DOE national laboratories, volunteered and was selected as the first Pilot site. Based on the similarities and linkages between Berkeley Lab and nearby university research laboratories, Berkeley Lab seemed a good candidate for external regulation and a good first step in familiarizing NRC with the technical and institutional issues involved in regulating laboratories in the DOE complex. NRC and DOE team members visited Berkeley Lab on four occasions between October 1997 and January 1998 to carry out the Pilot. The first step was to develop a detailed Work Plan, then to carry out both a technical review of the radiation safety program and an examination of policy and regulatory issues. The Pilot included a public meeting held in Oakland, CA in December 1997. The Pilot concluded with NRC's assessment that Berkeley Lab has a radiation protection program adequate to protect workers, the public and the environment, and that it is ready to be licensed by the NRC with minor programmatic exceptions. A draft final report of the Pilot was prepared and circulated for comment as a NUREG document (dated May 7, 1998). The report's recommendations include extending NRC regulatory authority to cover all ionizing radiation sources (including accelerators, x-ray units, NARM) at Berkeley Lab. Questions remaining to be resolved include: who should be the licensee (DOE, the Lab, or both)?; dealing with legacy issues and NRC D and D requirements; minimizing dual oversight; quantifying value added in terms of cost savings, enhanced safety, and improved public perception; extrapolating results to other national laboratories; and

  12. Generic communications index: User's manual

    International Nuclear Information System (INIS)

    Dean, R.S.; Steinbrecher, D.H.; Hennick, A.

    1987-12-01

    This report is a manual for providing information required to use a special computer program developed by the NRC for indexing generic communications. The program is written in a user-friendly menu driven form using dBASE III programming language. It facilitates use of the required dBASE III search and sort capabilities to access records in a database called Generic Communications Index. This index is made up of one record each for all bulletins, circulars, and information notices, including revisions and supplements, from 1971, when such documentation started, through 1986 (or to the latest update). The program is designed for use by anyone modestly acquainted with the general use of IBM-compatible personal computers. The manual contains both a brief overview and a detailed description of the program, as well as detailed instructions for getting started using the program on a personal computer with either a two-floppy disk or a hard disk system. Included at the end are a brief description of how to handle problems which might occur, and notes on the makeup of the program and database files for help in adding records of communications for future years

  13. Preparation for Scaling Studies of Ice-Crystal Icing at the NRC Research Altitude Test Facility

    Science.gov (United States)

    Struk, Peter M.; Bencic, Timothy J.; Tsao, Jen-Ching; Fuleki, Dan; Knezevici, Daniel C.

    2013-01-01

    This paper describes experiments conducted at the National Research Council (NRC) of Canadas Research Altitiude Test Facility between March 26 and April 11, 2012. The tests, conducted collaboratively between NASA and NRC, focus on three key aspects in preparation for later scaling work to be conducted with a NACA 0012 airfoil model in the NRC Cascade rig: (1) cloud characterization, (2) scaling model development, and (3) ice-shape profile measurements. Regarding cloud characterization, the experiments focus on particle spectra measurements using two shadowgraphy methods, cloud uniformity via particle scattering from a laser sheet, and characterization of the SEA Multi-Element probe. Overviews of each aspect as well as detailed information on the diagnostic method are presented. Select results from the measurements and interpretation are presented which will help guide future work.

  14. NRC Information Notice No. 91-29, Supplement 1: Deficiencies identified during electrical distribution system functional inspections

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1993-01-01

    During multidiscipline inspections such as safety system functional inspections (SSFIs) or safety system outage modification inspections (SSOMIs), the NRC identified a number of deficiencies related to the electrical distribution system (EDS). As a result of these deficiencies, the NRC developed the EDSFI to specifically evaluate the EDS. Since 1989, the NRC has performed over 50 EDSFIs, and found design weaknesses in the following generic areas: (1) undervoltage relay setpoints for degraded grid conditions; (2) interrupting capacity of fault protection devices; (3) improper coordination of fault protection devices; (4) analysis of emergency diesel generator (EDG) capacity to power safety-related loads during postulated accidents; and (5) EDG mechanical interfaces. Each of these issues are discussed

  15. Application of PLUTO Test Facility for U. S. NRC Licensing of a Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Dongseok; Shin, Changhwan; Lee, Kanghee; Kang, Heungseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The fuel assembly of the PLUS-7 loaded in the APR-1400 follows the same schedule. Meanwhile, In July 1998, the U.S. NRC adopted a research plan to address the effects of high burnup from a Loss of Coolant Accident (LOCA). From these programs, several important technical findings for rule revision were obtained. Based on the technical findings, the U. S. NRC has amended the 10 CFR 50.46 which will be proclaimed sooner or later. Through the amendment, a LOCA analysis on the fuel assembly has to show the safety at both a fresh and End of Life (EOL) state. The U. S. NRC has already required EOL effects on seismic/LOCA performance for a fuel assembly since 1998. To obtain U.S NRC licensing of a fuel assembly, based on the amendment of 10CFR50.46, a LOCA analysis of the fuel assembly has to show safety both fresh and EOL states. The proper damping factor of the fuel assembly measured at the hydraulic test loop for a dynamic model in a LOCA and a seismic analysis code are at least required. In this paper, we have examined the damping technologies and compared the test facility of PLUTO with others in terms of performance. PLUTO has a better performance on the operating conditions than any others.

  16. Development of RESRAD probabilistic computer codes for NRC decommissioning and license termination applications

    International Nuclear Information System (INIS)

    Chen, S. Y.; Yu, C.; Mo, T.; Trottier, C.

    2000-01-01

    In 1999, the US Nuclear Regulatory Commission (NRC) tasked Argonne National Laboratory to modify the existing RESRAD and RESRAD-BUILD codes to perform probabilistic, site-specific dose analysis for use with the NRC's Standard Review Plan for demonstrating compliance with the license termination rule. The RESRAD codes have been developed by Argonne to support the US Department of Energy's (DOEs) cleanup efforts. Through more than a decade of application, the codes already have established a large user base in the nation and a rigorous QA support. The primary objectives of the NRC task are to: (1) extend the codes' capabilities to include probabilistic analysis, and (2) develop parameter distribution functions and perform probabilistic analysis with the codes. The new codes also contain user-friendly features specially designed with graphic-user interface. In October 2000, the revised RESRAD (version 6.0) and RESRAD-BUILD (version 3.0), together with the user's guide and relevant parameter information, have been developed and are made available to the general public via the Internet for use

  17. Directory of certificates of compliance for radioactive materials packages: summary report of NRC approved quality-assurance programs for radioactive-material packages. Volume 3, Revision 3

    International Nuclear Information System (INIS)

    1983-09-01

    This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

  18. Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved quality assurance programs for radioactive material packages. Volume 3, Revision 4

    International Nuclear Information System (INIS)

    1984-11-01

    This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

  19. Purification and characterization of gamma poly glutamic acid from newly Bacillus licheniformis NRC20.

    Science.gov (United States)

    Tork, Sanaa E; Aly, Magda M; Alakilli, Saleha Y; Al-Seeni, Madeha N

    2015-03-01

    γ-poly glutamic acid (γ-PGA) has received considerable attention for pharmaceutical and biomedical applications. γ-PGA from the newly isolate Bacillus licheniformis NRC20 was purified and characterized using diffusion distance agar plate, mass spectrometry and thin layer chromatography. All analysis indicated that γ-PGA is a homopolymer composed of glutamic acid. Its molecular weight was determined to be 1266 kDa. It was composed of L- and D-glutamic acid residues. An amplicon of 3050 represents the γ-PGA-coding genes was obtained, sequenced and submitted in genbank database. Its amino acid sequence showed high similarity with that obtained from B. licheniformis strains. The bacterium NRC 20 was independent of L-glutamic acid but the polymer production enhanced when cultivated in medium containing L-glutamic acid as the sole nitrogen source. Finally we can conclude that γ-PGA production from B. licheniformis NRC20 has many promised applications in medicine, industry and nanotechnology. Copyright © 2014 Elsevier B.V. All rights reserved.

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

    Energy Technology Data Exchange (ETDEWEB)

    Barr, Cynthia; Grossman, Christopher; Alexander, George; Parks, Leah; Fuhrmann, Mark; Shaffner, James; McKenney, Christepher [U.S. NRC, Rockville, MD (United States); Pabalan, Roberto; Pickett, David [Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX (United States); Dinwiddie, Cynthia [Southwest Research Institute, San Antonio, TX (United States)

    2013-07-01

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

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

    International Nuclear Information System (INIS)

    Fresco, A.; Subudhi, M.

    1994-01-01

    Age-related degradation is managed through the maintenance program of a nuclear plant. From 1988 to 1991, the Nuclear Regulatory Commission (NRC) evaluated the maintenance program of every nuclear power plant in the United States. The authors reviewed 44 out of a total of 67 of the reports issued by the NRC on these in-depth team inspections. The reports were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components. The authors' conclusions are presented. 6 refs

  2. NRC licensing of uranium enrichment plants

    International Nuclear Information System (INIS)

    Moran, B.W.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) is preparing a rule making that establishes the licensing requirements for low-enriched uranium enrichment plants. Although implementation of this rule making is timed to correspond with receipt of a license application for the Louisiana Energy Services centrifuge enrichment plant, the rule making is applicable to all uranium enrichment technologies. If ownership of the US gaseous diffusion plants and/or atomic vapor laser isotope separation is transferred to a private or government corporation, these plants also would be licensable under the new rule making. The Safeguards Studies Department was tasked by the NRC to provide technical assistance in support of the rule making and guidance preparation process. The initial and primary effort of this task involved the characterization of the potential safeguards concerns associated with a commercial enrichment plant, and the licensing issues associated with these concerns. The primary safeguards considerations were identified as detection of the loss of special nuclear material, detection of unauthorized production of material of low strategic significance, and detection of production of uranium enriched to >10% 235 U. The primary safeguards concerns identified were (1) large absolute limit of error associated with the material balance closing, (2) the inability to shutdown some technologies to perform a cleanout inventory of the process system, and (3) the flexibility of some technologies to produce higher enrichments. Unauthorized production scenarios were identified for some technologies that could prevent conventional material control and accounting programs from detecting the production and removal of 5 kg 235 U as highly enriched uranium. Safeguards techniques were identified to mitigate these concerns

  3. NRC quarterly [status] report

    International Nuclear Information System (INIS)

    1987-01-01

    This report covers the third quarter of calendar year 1987. The NRC licensing activity during the period of this report included the issuance of a full-power license for Beaver Valley 2 on August 14, 1987, and operating license restricted to five percent power for South Texas Unit 1 on August 21, 1987. Additional licensing delay for Shoreham is projected due to complex litigation. Also, licensing delay may occur for Comanche Peak Unit 1, because the duration of the hearing is uncertain. Although a license authorizing fuel loading and precriticality testing for Seabrook Unit 1 has been issued, there is a projected delay for low-power licensing. Full-power licensing for Seabrook Unit 1 will be delayed due to offsite emergency preparedness issues. The length of the delay is not known at this time. With the exception of Seabrook and Shoreham, regulatory delays in this report are not impacted by the schedules for resolving off-site emergency preparedness issues

  4. The NRC and utility finances

    International Nuclear Information System (INIS)

    Byus, L.C.

    1992-01-01

    In a speech before the National Association of Regulatory Utility Commissioners in November 1991, Nuclear Regulatory Commission Chairman Ivan Selin presented what he called an open-quotes expansion of the concept of safety beyond our previous narrow bounds.close quotes He went on to explain, open-quotes To be seen as successful and safe operators of nuclear facilities, utilities must have safe and predictable cash flows.close quotes While there is little disagreement that the concepts of successful plant operations and financial strength go hand in hand, the relationship between the two is not clear. Which came first, successful operation of generating plants or financial strength? Selin's views on NRC involvement in financial aspects of utility operation in the United States are sure to stimulate debate on the issue

  5. NRC Enforcement Policy Review, July 1995-July 1997

    International Nuclear Information System (INIS)

    Lieberman, J.; Pedersen, R.M.

    1998-04-01

    On June 30, 1995, the Nuclear Regulatory Commission (NRC) issued a complete revision of its General Statement of Policy and Procedure for Enforcement Action (Enforcement Policy) (60 FR 34381). In approving the 1995 revision to the Enforcement Policy, the Commission directed the staff to perform a review of its implementation of the Policy after approximately 2 years of experience and to consider public comments. This report represents the results of that review

  6. Fasting Ghrelin Levels Are Decreased in Obese Subjects and Are Significantly Related With Insulin Resistance and Body Mass Index

    Directory of Open Access Journals (Sweden)

    Dimitrios Papandreou

    2017-10-01

    CONCLUSION: Obese subjects have low fasting ghrelin levels that they are significantly related to insulin resistance and body mass index. More prospective studies are needed to establish the role of ghrelin in the pathogenesis of human obesity.

  7. Funding for reactor decommissioning: the NRC perspective

    International Nuclear Information System (INIS)

    Wood, R.S.

    1981-01-01

    The cost of decommissioning a nuclear power plant is discussed. Four funding approaches that have received the most attention from the NRC are: prepayment into a trust fund of estimated decommissioning funds at the start of facility operation; annual contributions into a trust fund outside the control of the utility over the estimated life of a facility; internal reserve or sinking fund amortizations over the estimated life of a facility; and insurance or other surety mechanisms used separately or in conjunction with any of the first three mechanisms

  8. Continuing the Conversation: Development of the U.S. NRC's Definition of Safety Culture and its Traits

    International Nuclear Information System (INIS)

    Barnes, Valerie; Koves, Ken

    2012-01-01

    Val Barnes gave a presentation on behalf of the US NRC and INPO. She summarised the work done by the US NRC to develop the US NRC Policy on Safety Culture. Stakeholder representatives were involved in panel sessions to develop a common definition of safety culture and define the traits of a positive safety culture. A survey-based validation study of the eight traits identified through the panel sessions was then conducted across the 63 US nuclear sites by INPO. The INPO study also examined the correlations between the safety culture traits and safety performance. Strong correlations were found for some factors (for example, the number of unplanned scrams correlated strongly with perceptions on management responsibility). The results of the survey supported the inclusion of an additional safety culture trait (questioning attitude) resulting in the following nine traits: - Leadership Safety Values and Actions. - Problem Identification and Resolution. - Personal Accountability. - Work Process. - Continuous Learning. - Environment for Raising Concerns. - Effective Safety Communication. - Respectful Work Environment. - Questioning Attitude. The US NRC has also issued a safety culture policy statement which provides the following definition: 'Nuclear safety culture is the core values and behaviors resulting from a collective commitment by leaders and individuals to emphasize safety over competing goals to ensure protection of people and the environment'. The US NRC and its regulated communities are now working on implementing the policy statement. It was concluded that the work carried out to develop the safety culture policy statement has helped to develop a common language and understanding amongst stakeholders

  9. 75 FR 6063 - Availability of NRC Open Government Web Site

    Science.gov (United States)

    2010-02-05

    ... ( http://www.nrc.gov/open ) will be available by February 6, 2010, and directs that, after February 10... http://www.regulations.gov Web site. FOR FURTHER INFORMATION CONTACT: James B. Schaeffer, Deputy..., 2010, and provided options for submitting comments by mail, fax, or at http://www.regulations.gov , but...

  10. Directory of Book Trade and Related Organizations. Books Trade Associations, United States and Canada; International and Foreign Book Trade Associations; National Information Standards Organization (NISO) Standards; Calendar, 2003-2012; Acronyms; Index of Organizations; Subject Index.

    Science.gov (United States)

    Bowker Annual Library and Book Trade Almanac, 2003

    2003-01-01

    Includes two lists: one of book trade associations in the United States and Canada, and one of international and foreign book trade associations. Concludes with National Information Standards Organization (NISO) standards; calendar, 2003-2012; acronyms; index of organizations; and subject index. (LRW)

  11. Composition of The Knee Index, a novel three-dimensional biomechanical index for knee joint load, in subjects with mild to moderate knee osteoarthritis

    DEFF Research Database (Denmark)

    Clausen, Brian; Andriacchi, Tom; Nielsen, Dennis Brandborg

    Background Knee joint load is an important factor associated with progression of knee osteoarthritis. To provide an overall understanding of knee joint loading, the Knee Index (KI) has been developed to include moments from all three planes (frontal, sagittal and transversal). However, before KI...... index of joint load for the knee, in patients with mild to moderate knee osteoarthritis. Methods The contribution of frontal, sagittal and transversal plane knee moments to KI was investigated in 24 subjects (13 women, age: 58 ± 7.6 years, BMI: 27.1 ± 3.0) with clinically diagnosed mild to moderate knee...... kinematics (i.e. the knee adduction moment), and secondarily the sagittal plane kinematics (i.e. the knee flexion moment). This holds promise for using KI in clinical trials since both frontal and sagittal knee joint moments have been suggested to be associated with the knee osteoarthritis disease...

  12. Leg joint power output during progressive resistance FES-LCE cycling in SCI subjects: developing an index of fatigue

    Directory of Open Access Journals (Sweden)

    Faghri Pouran D

    2008-04-01

    Full Text Available Abstract Background The purpose of this study was to investigate the biomechanics of the hip, knee and ankle during a progressive resistance cycling protocol in an effort to detect and measure the presence of muscle fatigue. It was hypothesized that knee power output can be used as an indicator of fatigue in order to assess the cycling performance of SCI subjects. Methods Six spinal cord injured subjects (2 incomplete, 4 complete between the ages of twenty and fifty years old and possessing either a complete or incomplete spinal cord injury at or below the fourth cervical vertebra participated in this study. Kinematic data and pedal forces were recorded during cycling at increasing levels of resistance. Ankle, knee and hip power outputs and resultant pedal force were calculated. Ergometer cadence and muscle stimulation intensity were also recorded. Results The main findings of this study were: (a ankle and knee power outputs decreased, whereas hip power output increased with increasing resistance, (b cadence, stimulation intensity and resultant pedal force in that combined order were significant predictors of knee power output and (c knowing the value of these combined predictors at 10 rpm, an index of fatigue can be developed, quantitatively expressing the power capacity of the knee joint with respect to a baseline power level defined as fatigue. Conclusion An index of fatigue was successfully developed, proportionalizing knee power capacity during cycling to a predetermined value of fatigue. The fatigue index value at 0/8th kp, measured 90 seconds into active, unassisted pedaling was 1.6. This indicates initial power capacity at the knee to be 1.6 times greater than fatigue. The fatigue index decreased to 1.1 at 2/8th kp, representing approximately a 30% decrease in the knee's power capacity within a 4 minute timespan. These findings suggest that the present cycling protocol is not sufficient for a rider to gain the benefits of FES and thus

  13. Leg joint power output during progressive resistance FES-LCE cycling in SCI subjects: developing an index of fatigue.

    Science.gov (United States)

    Haapala, Stephenie A; Faghri, Pouran D; Adams, Douglas J

    2008-04-26

    The purpose of this study was to investigate the biomechanics of the hip, knee and ankle during a progressive resistance cycling protocol in an effort to detect and measure the presence of muscle fatigue. It was hypothesized that knee power output can be used as an indicator of fatigue in order to assess the cycling performance of SCI subjects. Six spinal cord injured subjects (2 incomplete, 4 complete) between the ages of twenty and fifty years old and possessing either a complete or incomplete spinal cord injury at or below the fourth cervical vertebra participated in this study. Kinematic data and pedal forces were recorded during cycling at increasing levels of resistance. Ankle, knee and hip power outputs and resultant pedal force were calculated. Ergometer cadence and muscle stimulation intensity were also recorded. The main findings of this study were: (a) ankle and knee power outputs decreased, whereas hip power output increased with increasing resistance, (b) cadence, stimulation intensity and resultant pedal force in that combined order were significant predictors of knee power output and (c) knowing the value of these combined predictors at 10 rpm, an index of fatigue can be developed, quantitatively expressing the power capacity of the knee joint with respect to a baseline power level defined as fatigue. An index of fatigue was successfully developed, proportionalizing knee power capacity during cycling to a predetermined value of fatigue. The fatigue index value at 0/8th kp, measured 90 seconds into active, unassisted pedaling was 1.6. This indicates initial power capacity at the knee to be 1.6 times greater than fatigue. The fatigue index decreased to 1.1 at 2/8th kp, representing approximately a 30% decrease in the knee's power capacity within a 4 minute timespan. These findings suggest that the present cycling protocol is not sufficient for a rider to gain the benefits of FES and thus raises speculation as to whether or not progressive resistance

  14. Essential and non-essential DNA replication genes in the model halophilic Archaeon, Halobacterium sp. NRC-1

    Directory of Open Access Journals (Sweden)

    DasSarma Shiladitya

    2007-06-01

    Full Text Available Abstract Background Information transfer systems in Archaea, including many components of the DNA replication machinery, are similar to those found in eukaryotes. Functional assignments of archaeal DNA replication genes have been primarily based upon sequence homology and biochemical studies of replisome components, but few genetic studies have been conducted thus far. We have developed a tractable genetic system for knockout analysis of genes in the model halophilic archaeon, Halobacterium sp. NRC-1, and used it to determine which DNA replication genes are essential. Results Using a directed in-frame gene knockout method in Halobacterium sp. NRC-1, we examined nineteen genes predicted to be involved in DNA replication. Preliminary bioinformatic analysis of the large haloarchaeal Orc/Cdc6 family, related to eukaryotic Orc1 and Cdc6, showed five distinct clades of Orc/Cdc6 proteins conserved in all sequenced haloarchaea. Of ten orc/cdc6 genes in Halobacterium sp. NRC-1, only two were found to be essential, orc10, on the large chromosome, and orc2, on the minichromosome, pNRC200. Of the three replicative-type DNA polymerase genes, two were essential: the chromosomally encoded B family, polB1, and the chromosomally encoded euryarchaeal-specific D family, polD1/D2 (formerly called polA1/polA2 in the Halobacterium sp. NRC-1 genome sequence. The pNRC200-encoded B family polymerase, polB2, was non-essential. Accessory genes for DNA replication initiation and elongation factors, including the putative replicative helicase, mcm, the eukaryotic-type DNA primase, pri1/pri2, the DNA polymerase sliding clamp, pcn, and the flap endonuclease, rad2, were all essential. Targeted genes were classified as non-essential if knockouts were obtained and essential based on statistical analysis and/or by demonstrating the inability to isolate chromosomal knockouts except in the presence of a complementing plasmid copy of the gene. Conclusion The results showed that ten

  15. Safeguards Summary Event List (SSEL), pre-NRC through December 31, 1982

    International Nuclear Information System (INIS)

    1983-08-01

    This document represents a revision of the list published December 1980 of safeguards-related events involving NRC licensees and licensed material. It summarizes events occurring between June 30, 1982 and December 31, 1982. Editorial changes to earlier pages are also included

  16. Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved packages

    International Nuclear Information System (INIS)

    1983-01-01

    This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  17. U.S. NRC's generic issues program

    International Nuclear Information System (INIS)

    Kauffman, J.V.; Foster, J.W.

    2008-01-01

    The United States Nuclear Regulatory Commission (NRC) has a Generic Issues Program (GIP) to address Generic Issues (GI). A GI is defined as 'a regulatory matter involving the design, construction, operation, or decommissioning of several, or a class of, NRC licensees or certificate holders that is not sufficiently addressed by existing rules, guidance, or programs'. This rather legalistic definition has several practical corollaries: First, a GI must involve safety. Second, the issue must involve at least two plants, or it would be a plant-specific issue rather than a GI. Third, the potential safety question must not be covered by existing regulations and guidance (compliance). Thus, the effect of a GI is to potentially change the body of regulations and associated guidance (e.g., regulatory guides). The GIP was started in 1976, thus it is a relatively mature program. Approximately 850 issues have been processed by the program to date. More importantly, even after 30 years, new GIs continue to be proposed. The entire set of Generic Issues (GIs) is updated annually in NUREG-0933, 'A Prioritization of Generic Safety Issues'. GIs normally involve complex questions of safety and regulation. Efficient and effective means of addressing these issues are very important for regulatory effectiveness. If an issue proves to pose a genuine, significant safety question, then swift, effective, enforceable, and cost-effective action needs to be taken. Conversely, if an issue is of little safety significance, the issue should be dismissed in an expeditious manner, avoiding unnecessary expenditure of resources and regulatory burden or uncertainty. This paper provides a summary of the 5-stage program, from identification through the regulatory assessment stage. The paper also includes a discussion of the program's seven criteria, sources of proposed GIs, recent improvements, publicly available information, historical performance, and status of current GIs. (authors)

  18. 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.

  19. 75 FR 10526 - In the Matter of Mr. Lawrence E. Grimm; Order Prohibiting Involvement in NRC-Licensed Activities

    Science.gov (United States)

    2010-03-08

    ... NUCLEAR REGULATORY COMMISSION [IA-09-068; NRC-2010-0085] In the Matter of Mr. Lawrence E. Grimm; Order Prohibiting Involvement in NRC-Licensed Activities I Mr. Lawrence E. Grimm was employed as a... NIST-Boulder facility in accordance with the conditions specified therein. Mr. Grimm was listed on the...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-05-01

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

  1. NRC Licensing Status Summary Report for NGNP

    Energy Technology Data Exchange (ETDEWEB)

    Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinsey, James Carl [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

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

  2. Assessment of US NRC fuel rod behavior codes to extended burnup

    International Nuclear Information System (INIS)

    Laats, E.T.; Croucher, D.W.; Haggag, F.M.

    1982-01-01

    The purpose of this paper is to report the status of assessing the capabilities of the NRC fuel rod performance codes for calculating extended burnup rod behavior. As part of this effort, a large spectrum of fuel rod behavior phenomena was examined, and the phenomena deemed as being influential during extended burnup operation were identified. Then, the experiment data base addressing these identified phenomena was examined for availability and completeness at extended burnups. Calculational capabilities of the NRC's steady state FRAPCON-2 and transient FRAP-T6 fuel rod behavior codes were examined for each of the identified phenomenon. Parameters calculated by the codes were compared with the available data base, and judgments were made regarding model performance. Overall, the FRAPCON-2 code was found to be moderately well assessed to extended burnups, but the FRAP-T6 code cannot be adequately assessed until more transient high burnup data are available

  3. NRC proposes changes to nuke decommissioning funding rules

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The Nuclear Regulatory Commission (NRC) has proposed to amend its regulations to allow self-guarantee as a means of assuring adequate funding for nuclear plant decommissioning. It acted in response to a rulemaking petition filed by General Electric Co. and Westinghouse Electric Corp. The proposal would allow self-guarantees if certain conditions are met: Tangible net worth of at least $1 billion; Tangible net worth at least 10 times the present decommissioning cost estimate for all activities the utility is responsible for as a self-guaranteeing licensee and as parent guarantor; Domestic assets amounting to at least 90 percent of total assets or at least 10 times the present decommissioning cost estimate; A credit rating for the utility's most recent bond issuance of AAA, AA, or A (Standard ampersand Poor's), or Aaa, Aa, or A (Moody's). Additional requirements include that the utility licensee must have at least one class of equity securities registered under the Securities Exchange Act of 1934, and that an independent auditor must verify that the utility met the financial test. A utility also would be responsible for reporting any change in circumstances affecting the criteria used to meet the financial test, and would be responsible for meeting that test within 90 days of each financial year. The NRC will accept written comments until March 29, 1993

  4. Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved quality assurance programs for radioactive material packages. Volume 3, Revision 6

    International Nuclear Information System (INIS)

    1986-10-01

    This directory contains a Summary Report of NRC Approved Packages (Volumes 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use of transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

  5. Quality of pharmacy-specific Medical Subject Headings (MeSH) assignment in pharmacy journals indexed in MEDLINE.

    Science.gov (United States)

    Minguet, Fernando; Salgado, Teresa M; van den Boogerd, Lucienne; Fernandez-Llimos, Fernando

    2015-01-01

    The Medical Subject Headings (MeSH) is the National Library of Medicine (NLM) controlled vocabulary for indexing articles. Inaccuracies in the MeSH thesaurus have been reported for several areas including pharmacy. To assess the quality of pharmacy-specific MeSH assignment to articles indexed in pharmacy journals. The 10 journals containing the highest number of articles published in 2012 indexed under the MeSH 'Pharmacists' were identified. All articles published over a 5-year period (2008-2012) in the 10 previously selected journals were retrieved from PubMed. MeSH terms used to index these articles were extracted and pharmacy-specific MeSH terms were identified. The frequency of use of pharmacy-specific MeSH terms was calculated across journals. A total of 6989 articles were retrieved from the 10 pharmacy journals, of which 328 (4.7%) were articles not fully indexed and therefore did not contain any MeSH terms assigned. Among the 6661 articles fully indexed, the mean number of MeSH terms was 10.1 (SD = 4.0), being 1.0 (SD = 1.3) considered as Major MeSH. Both values significantly varied across journals. The mean number of pharmacy-specific MeSH terms per article was 0.9 (SD = 1.2). A total of 3490 (52.4%) of the 6661 articles were indexed in pharmacy journals without a single pharmacy-specific MeSH. Of the total 67193 MeSH terms assigned to articles, on average 10.5% (SD = 13.9) were pharmacy-specific MeSH. A statistically significant different pattern of pharmacy-specific MeSH assignment was identified across journals (Kruskal-Wallis P journals can be improved to further enhance evidence gathering in pharmacy. Over half of the articles published in the top-10 journals publishing pharmacy literature were indexed without a single pharmacy-specific MeSH. Copyright © 2015 Elsevier Inc. All rights reserved.

  6. 75 FR 64749 - Request for Comments on the Use of Electronic Signatures for NRC Documents Related to the Medical...

    Science.gov (United States)

    2010-10-20

    ... Pike, Rockville, Maryland. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly... systems exclusively. NRC is seeking comments on acceptable forms of electronic signatures for documents... system that generates the electronic document must have functions that provide a legible document for the...

  7. NRC inspections of licensee activities to improve the performance of motor-operated valves

    International Nuclear Information System (INIS)

    Scarbrough, T.G.

    1992-01-01

    The NRC regulations require that components important to the safe operation of a nuclear power plant be treated in a manner that provides assurance of their proper performance. Despite these regulatory requirements, operating experience and research programs have raised concerns regarding the performance of motor-operated valves (MOVs) in nuclear power plants. In June 1990, the staff issued NUREG-1352, Action Plans for Motor-Operated Valves and Check Valves, which contains planned actions to organize the activities aimed at resolving the concerns about MOV performance. A significant task of the MOV action plan is the staff's review of the implementation of Generic Letter (GL) 89-10 (June 28, 1989), 'Safety-Related Motor-Operated Valve Testing and Surveillance,' and its supplements, by nuclear power plant licensees. The NRC staff has issued several supplements to GL 89-10 to provide additional guidance for use by licensees in responding to the generic letter. The NRC staff has conducted initial inspections of the GL 89-10 programs at most licensee facilities. This paper outlines some of the more significant findings of those inspections. For example, licensees who have begun differential pressure and flow testing have found some MOVs to require more thrust to operate than predicted by the standard industry equation with typical valve factors assumed in the past. The NRC staff has found weaknesses in licensee procedures for conducting the differential pressure and flow tests, the acceptance criteria for the tests in evaluating the capability of the MOV to perform its safety function under design basis conditions, and feedback of the test results into the methodology used by the licensee in predicting the thrust requirements for other MOVs. Some licensees have not made adequate progress toward resolving the MOV issue for their facilities within the recommended schedule of GL 89-10

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

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

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

    International Nuclear Information System (INIS)

    1998-05-01

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

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

    International Nuclear Information System (INIS)

    DiBiasio, A.M.

    1998-05-01

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

  11. NRC TLD Direct Radiation Monitoring Network. Volume 5, No. 2. Progress report, April-June 1985

    International Nuclear Information System (INIS)

    Jang, J.; Kramaric, M.; Cohen, L.

    1985-09-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network provides continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the second quarter of 1985. A complete listing of the site facilities monitored is included

  12. Policy issues raised by intervenor requests for financial assistance in NRC proceedings

    International Nuclear Information System (INIS)

    1975-01-01

    The purpose of the report presented is to focus and develop the myriad issues raised by intervenor requests for financial assistance for the NRC's proposed rulemaking proceeding. The report analyzes and assesses the various alternatives open to the Commission, and collects relevant data and material which may be informative to those participating in and conducting the rulemaking. Three major questions are examined: (1) should the Commission, as a matter of policy choice, provide financial assistance to intervenors in NRC proceedings; (2) are there preferable alternatives to direct intervenor financial aid, such as the establishment of an office of public counsel or provision of other forms of Commission assistance; and (3) what are the legal, administrative and policy considerations involved in implementing a determination to award financial assistance to intervenors, should the Commission so decide

  13. New NRC methodology for estimating biological risks from exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Willis, C.A; Branagan, E.F.

    1983-01-01

    In licensing commercial nuclear power reactors, in the US Nuclear Regulatory Commission considers the potential health effects from the release of radioactive effluents. This entails reliance on epidemiological study results and interpretations. The BEIR III report is a principal source of information but as newer information becomes available, it is desirable to include this in NRC models. To facilitate both the estimation of potential health effects and the evaluation of epidemiological study results, the NRC has supported the development of a new computer code (SPAHR). This new code utilizes much more comprehensive demographic models than did the previously used codes (CAIRD and BIERMOD). SPAHR can accommodate variations in all the principal demographic statistics such as age distribution, age-specific computing risks, and sex ratio. Also SPAHR can project effects over a number of generations

  14. NRC regulatory agenda: Quarterly report, April-June 1987

    International Nuclear Information System (INIS)

    1987-07-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  15. Do recent data from the Seychelles Islands alter the conclusions of the NRC Report on the toxicological effects of methylmercury?

    Directory of Open Access Journals (Sweden)

    Jacobson Joseph L

    2004-01-01

    Full Text Available Abstract In 2000, the National Research Council (NRC, an arm of the National Academy of Sciences, released a report entitled, "Toxicological Effects of Methylmercury." The overall conclusion of that report was that, at levels of exposure in some fish- and marine mammal-consuming communities (including those in the Faroe Islands and New Zealand, subtle but significant adverse effects on neuropsychological development were occurring as a result of in utero exposure. Since the release of that report, there has been continuing discussion of the public health relevance of current levels of exposure to Methylmercury. Much of this discussion has been linked to the release of the most recent longitudinal update of the Seychelles Island study. It has recently been posited that these findings supercede those of the NRC committee, and that based on the Seychelles findings, there is little or no risk of adverse neurodevelopmental effects at current levels of exposure. In this commentary, members of the NRC committee address the conclusions from the NRC report in light of the recent Seychelles data. We conclude that no evidence has emerged since the publication of the NRC report that alters the findings of that report.

  16. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed.

  17. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki

    2013-01-01

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed

  18. Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Packages

    International Nuclear Information System (INIS)

    1993-10-01

    This directory contains a Report of NRC Approved Packages (Volume 1). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

  19. NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Levin, A.E.

    1995-09-01

    New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

  20. Estimated incremental costs for NRC licensees to implement the US/IAEA safeguards agreement

    International Nuclear Information System (INIS)

    Clark, R.G.; Brouns, R.J.; Chockie, A.D.; Davenport, L.C.; Merrill, J.A.

    1979-01-01

    A study was recently completed for the US Nuclear Regulatory Commision (NRC) by the Pacific Northwest Laboratory (PNL) to identify the incremental cost of implementing the US/IAEA safeguards treaty agreement to eligible NRC licensees. Sources for the study were cost estimates from several licensees who will be affected by the agreement and cost analyses by PNL staff. The initial cost to all eligible licensees to implement the agreement is estimated by PNL to range from $1.9 to $7.2 million. The annual cost to these same licensees for the required accounting and reporting activities is estimated at $0.5 to $1.5 million. Annual inspection costs to the industry for the limited IAEA inspection being assumed is estimated at $80,000 to $160,000

  1. NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident

    International Nuclear Information System (INIS)

    1983-11-01

    Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquaters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

  2. Dewey Decimal Classification Online Project: Evaluation of a Library Schedule and Index Integrated into the Subject Searching Capabilities of an Online Catalog. Final Report.

    Science.gov (United States)

    Markey, Karen; Demeyer, Anh N.

    In this research project, subject terms from the Dewey Decimal Classification (DDC) Schedules and Relative Index were incorporated into an online catalog as searcher's tools for subject access, browsing, and display. Four features of the DDC were employed to help searchers browse for and match their own subject terms with the online catalog's…

  3. NRC staff preliminary analysis of public comments on advance notice of proposed rulemaking on emergency planning

    International Nuclear Information System (INIS)

    Peabody, C.A.; Hickey, J.W.N.

    1980-01-01

    The Nuclear Regulatory Commission (NRC) published an advance notice of proposed rulemaking on emergency planning on July 17, 1979 (44 FR 41483). In October and November 1979, the NRC staff submitted several papers to the Commission related to the emergency planning rulemaking. One of these papers was a preliminary analysis of public comments received on the advance notice (SECY-79-591B, November 13, 1979). This document consists of the preliminary analysis as it was submitted to the Commission, with minor editorial changes

  4. NRC safety research in support of regulation. Selected highlights

    International Nuclear Information System (INIS)

    1986-05-01

    The report presents selected highlights of how research has contributed to the regulatory effort. It explains the research role of the NRC and nuclear safety research contributions in the areas of: pressure vessel integrity, piping, small- and large-break loss-of-coolant accidents, hydrogen and containment, source term analysis, seismic hazards and high-level waste management. The report also provides a summary of current and future research directions in support of regulation

  5. Neutron spectral characterization of the NRC-HSST experiments

    Energy Technology Data Exchange (ETDEWEB)

    Stallmann, F. W.; Kam, F. B.K.

    1979-01-01

    Irradiation experiments are being performed for the US Nuclear Regulatory Commission (NRC) Heavy Section Steel Technology (HSST) program. Results of dosimetry performed in the second experiment have been previously reported. Similar procedures were followed in the third experiment. The experiences gained in these two experiments have led to modifications in the composition and distribution of foil dosimeters which monitor the neutron flux-spectra in the irradiated steel specimens. It is expected that in the new experiments much higher accuracies than previously possible can be achieved in the determination of irradiation damage parameters.

  6. Neutron spectral characterization of the NRC-HSST experiments

    International Nuclear Information System (INIS)

    Stallmann, F.W.; Kam, F.B.K.

    1979-01-01

    Irradiation experiments are being performed for the US Nuclear Regulatory Commission (NRC) Heavy Section Steel Technology (HSST) program. Results of dosimetry performed in the second experiment have been previously reported. Similar procedures were followed in the third experiment. The experiences gained in these two experiments have led to modifications in the composition and distribution of foil dosimeters which monitor the neutron flux-spectra in the irradiated steel specimens. It is expected that in the new experiments much higher accuracies than previously possible can be achieved in the determination of irradiation damage parameters

  7. Performance of Hybrid Steel Fibers Reinforced Concrete Subjected to Air Blast Loading

    Directory of Open Access Journals (Sweden)

    Mohammed Alias Yusof

    2013-01-01

    Full Text Available This paper presents the results of the experimental data and simulation on the performance of hybrid steel fiber reinforced concrete (HSFRC and also normal reinforced concrete (NRC subjected to air blast loading. HSFRC concrete mix consists of a combination of 70% long steel hook end fibre and also 30% of short steel hook end fibre with a volume fraction of 1.5% mix. A total of six concrete panels were subjected to air blast using plastic explosive (PE4 weighing 1 kg each at standoff distance of 0.3 meter. The parameters measured are mode of failure under static and blast loading and also peak overpressure that resulted from detonation using high speed data acquisition system. In addition to this simulation work using AUTODYN was carried out and validated using experimental data. The experimental results indicate that hybrid steel fiber reinforced concrete panel (HSFRC possesses excellent resistance to air blast loading as compared to normal reinforced concrete (NRC panel. The simulation results were also found to be close with experimental data. Therefore the results have been validated using experimental data.

  8. Implementation and interpretation of the NRC/IAEA transport regulations in the United States

    International Nuclear Information System (INIS)

    Shappert, L.B.

    1987-01-01

    For those materials used in the construction of spent fuel casks that are covered by the many available codes (ASME, ASTM, etc.), their acceptance by NRC can be expected to be straightforward. When materials are used that are not recognized by the codes, NRC has taken a more cautious attitude in their acceptance and approval. As mentioned earlier, they have initiated a number of studies involving ferritic steels, including DCI. More recently, they are organizing a panel of independent experts to consider all the data available and provide guidance as to whether these ferritic materials meet the safety requirements of the regulations and, if so, under what conditions. They will also be considering the testing that has been applied to casks fabricated from DCI and the likely margins of safety they possess. (orig./DG)

  9. Directory of certificates of compliance for radioactive materials packages. Volume 1, Revision 17: Report of NRC approved packages

    International Nuclear Information System (INIS)

    1994-10-01

    This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  11. Consolidation and Decomposition of APR1400 NRC Design Certification Processes for Collaborative and Accelerated Processing

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young Chul [FNC Technology Co., Yongin (Korea, Republic of); Kang, Deog Ji [KNHP, Daejeon (Korea, Republic of)

    2016-05-15

    KEPCO and KHNP are conducting APR1400 Design Certification from NRC. For the proper management of processes and information, a system called RIS (Regulatory Information management System) has been implemented by FNC from 2014, and it is on the final stage. In retaining the certification from NRC, RIS will be a very essential role by providing platform for collaborative and accelerated processing of responses to RAI (Request of Additional Information). Preparation of responses to RAI with this kind of systematic approach may be the first in the world. Westinghouse is doing manually and using MS Excel to collect the processing status. Where as, RIS will enable each member can do his own job and collect the status automatically. In this paper, how collaborative and accelerated processing of responses to RAI can be enabled will be described, and further enhancements will also be discussed. It handles MS Word directory with the help of VSTO. And with the help of Aspose.Total for .NET, the prepared response to RAI meets NRC's requirements. Through some further work and direct integration with requirement management solution, RIS can be expanded to cover a prior impact notice in case of DCD being altered.

  12. Friction correction for model ship resistance and propulsion tests in ice at NRC's OCRE-RC

    Directory of Open Access Journals (Sweden)

    Michael Lau

    2018-05-01

    Full Text Available This paper documents the result of a preliminary analysis on the influence of hull-ice friction coefficient on model resistance and power predictions and their correlation to full-scale measurements. The study is based on previous model-scale/full-scale correlations performed on the National Research Council - Ocean, Coastal, and River Engineering Research Center's (NRC/OCRE-RC model test data. There are two objectives for the current study: (1 to validate NRC/OCRE-RC's modeling standards in regarding to its practice of specifying a CFC (Correlation Friction Coefficient of 0.05 for all its ship models; and (2 to develop a correction methodology for its resistance and propulsion predictions when the model is prepared with an ice friction coefficient slightly deviated from the CFC of 0.05. The mean CFC of 0.056 and 0.050 for perfect correlation as computed from the resistance and power analysis, respectively, have justified NRC/OCRE-RC's selection of 0.05 for the CFC of all its models. Furthermore, a procedure for minor friction corrections is developed. Keywords: Model test, Ice resistance, Power, Friction correction, Correlation friction coefficient

  13. NRC Regulatory Agenda. Quarterly report, October-December 1985. Volume 4, No. 4

    International Nuclear Information System (INIS)

    1986-03-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

  14. NRC high-level radioactive waste program. Annual progress report: Fiscal Year 1996

    International Nuclear Information System (INIS)

    Sagar, B.

    1997-01-01

    This annual status report for fiscal year 1996 documents technical work performed on ten key technical issues (KTI) that are most important to performance of the proposed geologic repository at Yucca Mountain. This report has been prepared jointly by the staff of the Nuclear Regulatory Commission (NRC) Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses. The programmatic aspects of restructuring the NRC repository program in terms of KTIs is discussed and a brief summary of work accomplished is provided. The other ten chapters provide a comprehensive summary of the work in each KTI. Discussions on probability of future volcanic activity and its consequences, impacts of structural deformation and seismicity, the nature of of the near-field environment and its effects on container life and source term, flow and transport including effects of thermal loading, aspects of repository design, estimates of system performance, and activities related to the U.S. Environmental Protection Agency standard are provided

  15. Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

    International Nuclear Information System (INIS)

    Essig, T.H.

    1995-01-01

    This talk summary addresses the issue of how future policies of the NRC will affect nuclear power in areas such as construction, emergency preparedness, and licensing. Specific topics covered include the following: Emergent EP licensing issues for operating nuclear Power Plants; 10CFR Part 52 and the process for licensing of Advanced Light Water Reactors (ALWRs); and potential revisions to emergency preparedness programs for future nuclear power plants

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

    International Nuclear Information System (INIS)

    1995-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

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

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

    International Nuclear Information System (INIS)

    1993-06-01

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

  19. NRC TLD [Nuclear Regulatory Commission thermoluminescent dosimeter] direct radiation monitoring network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1990-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1989. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  20. 75 FR 21979 - NRC Region II Address and Main Telephone Number Changes

    Science.gov (United States)

    2010-04-27

    ... Region II Address and Main Telephone Number Changes AGENCY: Nuclear Regulatory Commission. ACTION: Final... address for its Region II office and to update the main telephone number. The Region II office move and... update the NRC Region II office street address and office main telephone number. The physical location of...

  1. Armenian nuclear power plant: US NRC assistance programme for seismic upgrade and safety analysis

    International Nuclear Information System (INIS)

    Simos, N.; Perkins, K.; Jo, J.; Carew, J.; Ramsey, J.

    2003-01-01

    This paper summarizes the U.S. Nuclear Regulatory Commission's (US NRC) technical support program activities associated with the Armenian Nuclear Power Plant (ANPP) safety upgrade. The US NRC program, integrated within the overall IAEA-led initiative for safety re-evaluation of the WWER plants, has as its main thrust the technical support to the Armenian Nuclear Regulatory Authority (ANRA) through close collaboration with the scientific staff at Brookhaven National Laboratory (BNL). Several major technical areas of support to ANRA form the basis of the NRC program. These include the seismic re-evaluation and upgrade of the ANPP, safety evaluation of critical systems, and the generation of the Safety Analysis Report (SAR). Specifically, the seismic re-evaluation of the ANPP is part of a broader activity that involves the re-assessment of the seismic hazard at the site, the identification of the Safe Shutdown Equipment at the plant and the evaluation of their seismic capacity, the detailed modeling and analysis of the critical facilities at ANPP, and the generation of the Floor Response Spectra (FRS). Based on the new spectra that incorporate all new findings (hazard, site soil, structure, etc.), the overall capacity of the main structures and the seismic capacity of the critical systems are being re-evaluated. In addition, analyses of critical safe shutdown systems and safe shutdown processes are being performed to ensure both the capabilities of the operating systems and the enhancement of safety due to system upgrades. At present, one of the principal goals of the US NRC's regulatory assistance activities with ANRA is enhancing ANRA's regulatory oversight of high-priority safety issues (both generic and plant-specific) associated with operation of the ANPP. As such, assisting ANRA in understanding and assessing plant-specific seismic and other safety issues associated with the ANPP is a high priority given the ANPP's being located in a seismically active area

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

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

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

  3. MutS and MutL are dispensable for maintenance of the genomic mutation rate in the halophilic archaeon Halobacterium salinarum NRC-1.

    Directory of Open Access Journals (Sweden)

    Courtney R Busch

    Full Text Available BACKGROUND: The genome of the halophilic archaeon Halobacterium salinarum NRC-1 encodes for homologs of MutS and MutL, which are key proteins of a DNA mismatch repair pathway conserved in Bacteria and Eukarya. Mismatch repair is essential for retaining the fidelity of genetic information and defects in this pathway result in the deleterious accumulation of mutations and in hereditary diseases in humans. METHODOLOGY/PRINCIPAL FINDINGS: We calculated the spontaneous genomic mutation rate of H. salinarum NRC-1 using fluctuation tests targeting genes of the uracil monophosphate biosynthesis pathway. We found that H. salinarum NRC-1 has a low incidence of mutation suggesting the presence of active mechanisms to control spontaneous mutations during replication. The spectrum of mutational changes found in H. salinarum NRC-1, and in other archaea, appears to be unique to this domain of life and might be a consequence of their adaption to extreme environmental conditions. In-frame targeted gene deletions of H. salinarum NRC-1 mismatch repair genes and phenotypic characterization of the mutants demonstrated that the mutS and mutL genes are not required for maintenance of the observed mutation rate. CONCLUSIONS/SIGNIFICANCE: We established that H. salinarum NRC-1 mutS and mutL genes are redundant to an alternative system that limits spontaneous mutation in this organism. This finding leads to the puzzling question of what mechanism is responsible for maintenance of the low genomic mutation rates observed in the Archaea, which for the most part do not have MutS and MutL homologs.

  4. NRC Task Force report on review of the federal/state program for regulation of commercial low-level radioactive waste burial grounds

    International Nuclear Information System (INIS)

    1977-01-01

    The underlying issue explored in this report is that of Federal vs State regulation of commercial radioactive waste burial grounds. The need for research and development, a comprehensive set of standards and criteria, a national plan for low-level waste management, and perpetual care funding are closely related to the central issue and are also discussed. Five of the six commercial burial grounds are regulated by Agreement States; the sixth is regulated solely by the NRC (NRC also regulates Special Nuclear Material at the sites). The sites are operated commercially. The operators contribute to the perpetual care funds for the sites at varying rates. The States have commitments for the perpetual care of the decommissioned sites except for one site, located on Federally owned land. Three conclusions are reached. Federal control over the disposal of low-level waste should be increased by requiring joint Federal/State site approval, NRC licensing, Federal ownership of the land, and a Federally administered perpetual care program. The NRC should accelerate the development of its regulatory program for the disposal of low-level waste. The undisciplined proliferation of low-level burial sites must be avoided. NRC should evaluate alternative disposal methods, conduct necessary studies, and develop a comprehensive low-level waste regulatory program (i.e., accomplish the above recommendations) prior to the licensing of new disposal sites

  5. Risk-based regulation - an NRC perspective and status

    International Nuclear Information System (INIS)

    King, T.L.; Murphy, J.A.

    1993-01-01

    The consideration of risk in regulatory decision making has traditionally been part of the US Nuclear Regulatory Commission's (NRC's) policy and practice. In the early days of regulation, this consideration was more qualitative in nature and was reflected in prescriptive/deterministic regulatory requirements. However, with the development of quantitative risk assessment methods, more detailed and comprehensive (although not complete) risk information on nuclear power plants is available to the designer, operator, and regulator. The availability of such information provides an opportunity to assess the need for change in the current regulatory structure and to develop future regulatory requirements in a less prescriptive, more performance-oriented fashion

  6. NRC safety research in support of regulation, 1986

    International Nuclear Information System (INIS)

    1987-09-01

    This report is the second in a series of annual reports responding to congressional inquiries as to the utilization of nuclear regulatory research. NUREG-1175, ''NRC Safety Research in Support of Regulation,'' published in May 1986, reported major research accomplishments between about FY 1980 and FY 1985. This report narrates the accomplishments of FY 1986 and does not restate earlier accomplishments. Earlier research results are mentioned in the context of current results in the interest of continuity. Both the direct contributions to scientific and technical knowledge and their regulatory applications, when there has been a definite regulatory outcome during FY 1986, have been described

  7. Comments on the NRC Safety Research Program budget

    International Nuclear Information System (INIS)

    1979-07-01

    This report includes comments on the budget levels and program plans for the supplemental request for FY 1980 to support research related to the accident at Three Mile Island, Unit 2 (TMI) as well as for the FY 1981 Budget. For both budgets, the funding levels considered by the ACRS are the original requests by RES and the Budget Review Group (BRG) markup as of July 10, 1979. In its current review of the NRC research program, the ACRS has given special attention to both the short- and long-term implications of the TMI accident and their significance to research for both the short- and long-term research programs

  8. Regulatory and technical reports (abstract index journal)

    International Nuclear Information System (INIS)

    1994-06-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually

  9. NRC licensing speedup. Hearing before a Subcommittee of the Committee on Government Operations, House of Representatives, Ninety-Seventh Congress, First Session, June 18, 1981

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    Joseph Hendrie, Acting Chairman of the Nuclear Regulatory Commission (NRC), was the principal witness at a June 18, 1981 hearing on whether the NRC is responsible for idling and delaying nuclear plants at a high cost to consumers. Congress is considering an interim licensing procedure that will allow plants to operate before safety hearings are completed. NRC evidence suggests that most plant delays are only projected ones, and that utilities must bear the blame for slippage in most construction schedules. Mr. Hendrie discussed the status of the nine impacted plants on the NRC list and outlined steps the Commission is taking to improve efficiency without impairing safety. His testimony and letters, statements, and other materials submitted for the record make up the hearing report

  10. Comparison between Radiology Science Laboratory, Brazil (LCR) and National Research Council, Canada (NRC) of the absorbed dose in water using Fricke dosimetry

    International Nuclear Information System (INIS)

    Salata, Camila; David, Mariano Gazineu; Almeida, Carlos Eduardo de

    2014-01-01

    The absorbed dose to water standards for HDR brachytherapy dosimetry developed by the Radiology Science Laboratory, Brazil (LCR) and the National Research Council, Canada (NRC), were compared. The two institutions have developed absorbed dose standards based on the Fricke dosimetry system. There are significant differences between the two standards as far as the preparation and readout of the Fricke solution and irradiation geometry of the holder. Measurements were done at the NRC laboratory using a single Ir-192 source. The comparison of absorbed dose measurements was expressed as the ratio Dw(NRC)/Dw(LCR), which was found to be 1.026. (author)

  11. Inventory of Information Resources; A Comparison of the American Geological Institute (AGI) Pilot Project with the National Referral Center (NRC) Inventory.

    Science.gov (United States)

    Price, John F.

    The National Referral Center (NRC) and its many services to the scientific and technical community are discussed in some detail as a preamble to a proposal of a cooperative arrangement between NRC and the American Geological Institute (AGI), its supporting societies, and all geoscientists in a combined effort to enlarge and maintain a…

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

    International Nuclear Information System (INIS)

    1987-07-01

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

  13. 77 FR 30332 - Mr. James Chaisson; Order Prohibiting Involvement in NRC-Licensed Activities

    Science.gov (United States)

    2012-05-22

    ... industrial radiographic operations in accordance with conditions specified therein. The license was... NRC conducted a safety and security inspection of the use of byproduct material for industrial... requirements. Mr. Chaisson chose to store a radiographic exposure device at a leased facility on Elk Street in...

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

    International Nuclear Information System (INIS)

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1997-03-01

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

  16. PRISIM: A plant risk status information management system for NRC inspectors

    International Nuclear Information System (INIS)

    Reilly, H.J.; Glynn, J.C.; Campbell, D.J.

    1987-01-01

    The Plant Risk Status Information Management System (PRISIM) is a microcomputer program that presents results of probabilistic risk assessments (PRAs), and related information, for use by United States Nuclear Regulatory Commission (NRC) decisionmakers. Plant-specific PRISIMs have been developed for three nuclear plants in the United States. The usefulness of PRISIM for these plants is now under evaluation, and an improved PRISIM is being developed

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

    Energy Technology Data Exchange (ETDEWEB)

    Struckmeyer, R.

    1997-03-01

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

  18. Comparative analysis of DOE Order 5820.2A, NRC, and EPA radioactive and mixed waste management requirements

    International Nuclear Information System (INIS)

    1991-07-01

    As directed by DOE-Headquarters and DOE-Idaho, the Radioactive Waste Technical Support Program (TSP) drafted an analysis of DOE Order 5820. 2A on ''Radioactive Waste Management'' to develop guidelines and criteria for revising the Order. This comparative matrix is a follow up to the earlier analysis. This matrix comparing the requirements of DOE Order 5820.2A with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) regulations was prepared at the request of EM-30. The matrix compares DOE Order 5820.2A with the following: NRC regulations in 10 CFR Part 61 on ''Licensing Requirements for Land Disposal of Radioactive Waste''; NRC regulations in 10 CFR Part 60 on ''Disposal of High-Level Radioactive Waste in Geologic Repositories''; EPA regulations in 40 CFR Part 191 on ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste''; EPA regulations in 40 FR Part 192 on ''Health and Environmental Protection Standards for Uranium and Thorium Mill Tailing''; and EPA regulations under the Resource Conservation and Recovery Act

  19. Grinding the Antitesting Ax: More Bias than Evidence behind NRC Panel's Conclusions

    Science.gov (United States)

    Hanushek, Eric A.

    2012-01-01

    In all the acrimonious discussion surrounding No Child Left Behind Act of 2001 (NCLB), surprisingly little attention has been given to the actual impact of that legislation and other accountability systems on student performance. Now a reputable body, a committee set up by the National Research Council (NRC), the research arm of the National…

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

    Energy Technology Data Exchange (ETDEWEB)

    Suber, Gregory [Nuclear Regulatory Commission (United States)

    2012-07-01

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

  1. Manual for subject analysis

    International Nuclear Information System (INIS)

    2002-01-01

    This document is one in a series of publications known as the ETDE/INIS Joint Reference Series and also constitutes a part of the ETDE Procedures Manual. It presents the rules, guidelines and procedures to be adopted by centers submitting input to the International Nuclear Information System (INIS) or the Energy Technology Data Exchange (ETDE). It is a manual for the subject analysis part of input preparation, meaning the selection, subject classification, abstracting and subject indexing of relevant publications, and is to be used in conjunction with the Thesauruses, Subject Categories documents and the documents providing guidelines for the preparation of abstracts. The concept and structure of the new manual are intended to describe in a logical and efficient sequence all the steps comprising the subject analysis of documents to be reported to INIS or ETDE. The manual includes new chapters on preparatory analysis, subject classification, abstracting and subject indexing, as well as rules, guidelines, procedures, examples and a special chapter on guidelines and examples for subject analysis in particular subject fields. (g.t.; a.n.)

  2. Update of NRC uranium mill licensing activities

    International Nuclear Information System (INIS)

    Martin, J.B.

    1978-01-01

    Increased vigilance must be given to controlling emissions from active milling operations, particularly windblown tailings, to assure that the soon-to-be-effective EPA Fuel Cycle Standard is met. Comprehensive environmental monitoring programs will have to be developed to confirm that, in fact, the limit is met. Just as was the case last year, tailings management and disposal is still the major item of concern relating to uranium milling operations. As stated earlier, the NRC feels that below-grade disposal is the preferred method of tailings disposal in that it provides the greatest assurances of long-term isolation. In any event, tailings must be disposed of in such a way that no active care is required of disposal sites, to avoid committing future generations to a significant, lingering obligation to care for wastes generated to produce benefits which they will only indirectly receive, if at all. While the primary means of providing long-term isolation of tailings must be by physical barriers, as a prudent, supplementary measure of control, we are concluding in the GEIS on Uranium Milling that ownership of disposal sites by a Government agency is desirable. We expect a low level of continued surveillance at disposal sites with small expense involved. We are concluding that requiring operators to contribute on the order of $100,000 per disposal site to cover ongoing expenses would be the most apropriate means of conforming to the principle that the waste generator should pay full costs of waste disposal. We feel such an arrangement would be fair, simple, and efficient, favoring it over complicated schemes involving such things as taxes on product or tailings generated and continued management of ear-marked funds. Legislation is now pending in the Congress which would give NRC direct regulatory control over mill tailings and put into place the authorities needed to implement the long-term control and funding arrangements discussed above

  3. NRC (2001 equations to predict the energy value of agroindustry byproducts in Brazilian northeast Equações do NRC (2001 para predição do valor energético de co-produtos da agroindústria no nordeste brasileiro

    Directory of Open Access Journals (Sweden)

    Arturo Bernardo Selaive Villarroel

    2008-06-01

    Full Text Available Fractions of carbohydrates and protein, and energy value estimative based in NRC (2001 equations, of agroindustry byproducts of cashew, passion fruit, melon, anatto seeds, pineapple and barbados cherry were evaluated. NRC (2001 equations were used to predict the energy value of the passion fruit, pineapple and barbados cherry using “in vivo” data. Carbohydrates fraction A + B1 ranged from 20.00 to 52.21% of the total carbohydrates, for melon and anatto seeds, respectively. Cashew and barbados cherry presented close values for the fraction B2 (11.88 and 14.25% and C (52.69 and 59.45% and, approximately three times lower of fraction B2 than the passion fruit and the pineapple (47.93 and 45.38%. It was concluded that the analyses of the fractions of carbohydrates and protein should be a laboratorial routine, since it consists in a simple analysis, inexpensive and allows the establishment of mechanicists parameters for feed evaluations. The observed values of TDN of ingredients and those predicted by NRC (2001 equations were similar, being appropriate to predict the energy value of feeds in Brazilian conditions.Objetivou-se, neste estudo, avaliar as frações de carboidratos e proteínas, e estimar o valor energético a partir das equações do NRC (2001 dos co-produtos da agroindústria do caju, maracujá, melão, urucum, abacaxi e acerola. Foi realizada a avaliação das equações do NRC (2001 para predição do valor energético do maracujá, abacaxi e acerola, a partir de dados in vivo. A fração A + B1 dos carboidratos variou de 20,00 a 52,21% dos carboidratos totais, para melão e urucum, respectivamente. O caju e a acerola apresentaram valores próximos para a fração B2 (11,88 e 14,25% e C (52,69 e 59,45% e, aproximadamente, três vezes menos fração B2 que o maracujá e o abacaxi (47,93 e 45,38%. O valor A da fração protéica (NNP variou de 5,01 a 33,02% para melão e urucum, respectivamente. A fração C da proteína foi menor

  4. NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident. Revision 1

    International Nuclear Information System (INIS)

    1985-02-01

    Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquarters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

  5. Complete cumulative index (1963-1983)

    International Nuclear Information System (INIS)

    1983-01-01

    This complete cumulative index covers all regular and special issues and supplements published by Atomic Energy Review (AER) during its lifetime (1963-1983). The complete cumulative index consists of six Indexes: the Index of Abstracts, the Subject Index, the Title Index, the Author Index, the Country Index and the Table of Elements Index. The complete cumulative index supersedes the Cumulative Indexes for Volumes 1-7: 1963-1969 (1970), and for Volumes 1-10: 1963-1972 (1972); this Index also finalizes Atomic Energy Review, the publication of which has recently been terminated by the IAEA

  6. Indexes to Nuclear Regulatory Commission issuances, January--June 1995. Volume 41, Index 2

    International Nuclear Information System (INIS)

    1995-09-01

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

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

    International Nuclear Information System (INIS)

    1984-01-01

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

  8. Indexes to Nuclear Regulatory Commission Issuances, July--December 1993. Volume 38, Index 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

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

  9. Indexes to Nuclear Regulatory Commission issuances, January--June 1995. Volume 41, Index 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

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

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

    International Nuclear Information System (INIS)

    1984-11-01

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

  11. The physiological cost index of walking with a powered knee-ankle-foot orthosis in subjects with poliomyelitis: A pilot study.

    Science.gov (United States)

    Arazpour, Mokhtar; Ahmadi Bani, Monireh; Samadian, Mohammad; Mousavi, Mohammad E; Hutchins, Stephen W; Bahramizadeh, Mahmood; Curran, Sarah; Mardani, Mohammad A

    2016-08-01

    A powered knee-ankle-foot orthosis was developed to provide restriction of knee flexion during stance phase and active flexion and extension of the knee during swing phase of gait. The purpose of this study was to determine its effect on the physiological cost index, walking speed and the distance walked in people with poliomyelitis compared to when walking with a knee-ankle-foot orthosis with drop lock knee joints. Quasi experimental study. Seven subjects with poliomyelitis volunteered for the study and undertook gait analysis with both types of knee-ankle-foot orthosis. Walking with the powered knee-ankle-foot orthosis significantly reduced walking speed (p = 0.015) and the distance walked (p = 0.004), and also, it did not improve physiological cost index values (p = 0.009) compared to walking with the locked knee-ankle-foot orthosis. Using a powered knee-ankle-foot orthosis did not significantly improve any of the primary outcome measures during walking for poliomyelitis subjects. This powered knee-ankle-foot orthosis design did not improve the physiological cost index of walking for people with poliomyelitis when compared to walking with a knee-ankle-foot orthosis with drop lock knee joints. This may have been due to the short training period used or the bulky design and additional weight of the powered orthosis. Further research is therefore warranted. © The International Society for Prosthetics and Orthotics 2015.

  12. NRC Confirmatory Testing Program for SBWR

    International Nuclear Information System (INIS)

    Han, J.T.; Bessette, D.E.; Shotkin, L.M.

    1994-01-01

    The objective of the NRC Confirmatory Testing Program for SBWR is to provide integral data for code assessment, which reasonably reproduce the important phenomena and processes expected in the SBWR under various loss-of-coolant accident (LOCA) and transient conditions. To achieve this objective, the Program consists of four coupled elements: (1) to design and construct an integral, carefully-scaled SBWR test facility at Purdue Univ., (2) to provide pre-construction RELAP5/CONTAIN predictions of the facility design, (3) to provide confirmatory data for code assessment, and (4) to assess the RELAP5/CONTAIN code with data. A description of the open-quotes preliminary designclose quotes of the Purdue test facility and test matrix is presented. The facility is scheduled to be built by December 1994. Approximately 50 tests will be performed from April 1995 through April 1996 and documented by interim data reports. A final and complete data report is scheduled to be published by July 31, 1996

  13. Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

    International Nuclear Information System (INIS)

    1993-10-01

    This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

  14. Writing and the 'Subject'

    DEFF Research Database (Denmark)

    Greve, Charlotte

    /page. It is, moreover, an index pointing to the painting/writing subject; it is a special deictic mode of painting/writing. The handwriting of the Russian avant-garde books, the poetics of handwriting, and the way handwriting is represented in poetry emphasize the way the subject (the speaking and the viewing...... in the early as well as the contemporary avant-garde, it becomes clear that the ‘subject’ is an unstable category that can be exposed to manipulation and play. Handwriting is performing as a signature (as an index), but is at the same time similar to the signature of a subject (an icon) and a verbal construct...

  15. NRC review of passive reactor design certification testing programs: Overview and regulatory perspective

    International Nuclear Information System (INIS)

    Levin, A.E.

    1993-01-01

    Reactor vendors are developing new designs for future deployment, including open-quotes passiveclose quotes light water reactors (LWRs), such as General Electric's (G.E.'s) simplified boiling water reactor (SBWR) and Westinghouse's AP600, which depend primarily on inherent processes, such as national convection and gravity feed, for safety injection and emergency core cooling. The U.S. Nuclear Regulatory Commission (NRC) has implemented a new process, certification of standardized reactor designs, for licensing these Plants. Part 52 of Title 10 of the Code of Federal Regulations (10CFR52) contains the requirements that vendors must meet for design certification. One important section, 10CFR52.47, reads open-quotes Certification of a standard design which . . . utilizes simplified, inherent, passive, or other innovative means to accomplish its safety functions will be granted only if: (1) The performance of each safety feature of the design has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof; (2) Interdependent effects among the safety features have been found acceptable by analysis, appropriate test programs, experience, or a combination thereof; and (3) Sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses. . . . The vendors have initiated programs to test innovative features of their designs and to develop data bases needed to validate their analytical codes, as required by the design certification rule. Accordingly, the NRC is reviewing and evaluating the vendors programs to ensure that they address adequately key issues concerning safety system performance. This paper provides an overview of the NRC's review process and regulatory perspective

  16. Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1988-12-01

    This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  17. Software for automated tracking of open items at NRC

    International Nuclear Information System (INIS)

    DeWispelare, A.R.; Mackin, P.C.; Johnson, R.L.

    1995-01-01

    The Open Item Tracking System (OITS) was developed in response to the Nuclear Regulatory Commission (NRC) need for a reliable, easy to use automated database system, to track all open (awaiting resolution) items related to regulatory, institutional, and technical uncertainties for the Department of Energy's (DOE's) high-level waste (HLW) disposal program. The OITS system was integrated with the Regulatory Program Database (RPD) Version 1.1, resulting in the RPD/OITS Version 2.0 system. RPD/OITS is a network bases system with client server architecture and a graphical user interface. This paper outlines the system and results of its implementation

  18. Survey by senior NRC management to obtain veiwpoints on the safety impact of regulatory activities from representative utilities operating and constructing nuclear power plants

    International Nuclear Information System (INIS)

    1981-08-01

    A survey of licensee staff members representing the several organizational elements in different licensee corporate and plant staffs was conducted by senior NRC management to obtain licensee views on the potential safety consequences and impact of NRC regulatory activities. The comments received addressed the full scope of NRC activities and the negative impact of agency actions on licensee resources, staff performance, planning and scheduling, and organizational effectiveness. The findings of the survey is that the pace and nature of regulatory actions have created a potential safety problem which deserves further evaluation by the agency

  19. Uncertainty Methods Framework Development for the TRACE Thermal-Hydraulics Code by the U.S.NRC

    International Nuclear Information System (INIS)

    Bajorek, Stephen M.; Gingrich, Chester

    2013-01-01

    The Code of Federal Regulations, Title 10, Part 50.46 requires that the Emergency Core Cooling System (ECCS) performance be evaluated for a number of postulated Loss-Of-Coolant-Accidents (LOCAs). The rule allows two methods for calculation of the acceptance criteria; using a realistic model in the so-called 'Best Estimate' approach, or the more prescriptive following Appendix K to Part 50. Because of the conservatism of Appendix K, recent Evaluation Model submittals to the NRC used the realistic approach. With this approach, the Evaluation Model must demonstrate that the Peak Cladding Temperature (PCT), the Maximum Local Oxidation (MLO) and Core-Wide Oxidation (CWO) remain below their regulatory limits with a 'high probability'. Guidance for Best Estimate calculations following 50.46(a)(1) was provided by Regulatory Guide 1.157. This Guide identified a 95% probability level as being acceptable for comparisons of best-estimate predictions to the applicable regulatory limits, but was vague with respect to acceptable methods in which to determine the code uncertainty. Nor, did it specify if a confidence level should be determined. As a result, vendors have developed Evaluation Models utilizing several different methods to combine uncertainty parameters and determine the PCT and other variables to a high probability. In order to quantify the accuracy of TRACE calculations for a wide variety of applications and to audit Best Estimate calculations made by industry, the NRC is developing its own independent methodology to determine the peak cladding temperature and other parameters of regulatory interest to a high probability. Because several methods are in use, and each vendor's methodology ranges different parameters, the NRC method must be flexible and sufficiently general. Not only must the method apply to LOCA analysis for conventional light-water reactors, it must also be extendable to new reactor designs and type of analyses where the acceptance criteria are less

  20. Design basis for the NRC Operations Center

    Energy Technology Data Exchange (ETDEWEB)

    Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

    1983-05-01

    This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project.

  1. Design basis for the NRC Operations Center

    International Nuclear Information System (INIS)

    Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

    1983-05-01

    This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project

  2. NRC's limit on intake of uranium-ore dust

    International Nuclear Information System (INIS)

    McGuire, S.A.

    1983-04-01

    In 1960 the Atomic Energy Commission adopted an interim limit on the intake by inhalation of airborne uranium-ore dust. This report culminates two decades of research aimed at establishing the adequacy of that limit. The report concludes that the AEC underestimated the time that thorium-230, a constituent of uranium-ore dust, would remain in the human lung. The AEC assumed that thorium-230 in ore dust would behave like uranium with a 120-day biological half-life in the lung. This report concludes that the biological half-life is actually on the order of 1 year. Correcting the AEC's underestimate would cause a reduction in the permitted airborne concentration of uranium-ore dust. However, another factor that cancels the need for that reduction was found. The uranium ore dust in uranium mills was found to occur with very large particle sizes (10-micron activity median aerodynamic diameter). The particles are so large that relatively few of them are deposited in the pulmonary region of the lung, where they would be subject to long-term retention. Instead they are trapped in the upper regions of the respiratory tract, subsequently swallowed, and then rapidly excreted from the body through the gastrointestinal tract. The two effects are of about the same magnitude but in opposing directions. Thus the present uranium-ore dust intake limit in NRC regulations should provide a level of protection consistent with that provided for other airborne radioactive materials. The report recalculates the limit on intake of uranium-ore dust using the derived air concentrations (DAC) from the International Commission on Radiological Protection's recent Publication 30. The report concludes that the silica contained in uranium-ore dust is a greater hazard to workers than the radiological hazard

  3. Objective and Subjective Attractiveness and Early Adolescent Adjustment.

    Science.gov (United States)

    Jovanovic, Jasna; And Others

    1989-01-01

    Used data from Pennsylvania Early Adolescent Transitions Study to assess how objective physical attractiveness (PA), indexed by appraisals from others, and subjective PA, indexed by self-appraisals, related to each other and to early adolescent adjustment. Findings indicated low relationship between objective and subjective PA; only subjective PA…

  4. Critical power prediction by CATHARE2 of the OECD/NRC BFBT benchmark

    Energy Technology Data Exchange (ETDEWEB)

    Lutsanych, Sergii, E-mail: s.lutsanych@ing.unipi.it [San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, Via Livornese 1291, 56122, San Piero a Grado, Pisa (Italy); Sabotinov, Luben, E-mail: luben.sabotinov@irsn.fr [Institut for Radiological Protection and Nuclear Safety (IRSN), 31 avenue de la Division Leclerc, 92262 Fontenay-aux-Roses (France); D’Auria, Francesco, E-mail: francesco.dauria@dimnp.unipi.it [San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, Via Livornese 1291, 56122, San Piero a Grado, Pisa (Italy)

    2015-03-15

    Highlights: • We used CATHARE code to calculate the critical power exercises of the OECD/NRC BFBT benchmark. • We considered both steady-state and transient critical power tests of the benchmark. • We used both the 1D and 3D features of the CATHARE code to simulate the experiments. • Acceptable prediction of the critical power and its location in the bundle is obtained using appropriate modelling. - Abstract: This paper presents an application of the French best estimate thermal-hydraulic code CATHARE 2 to calculate the critical power and departure from nucleate boiling (DNB) exercises of the International OECD/NRC BWR Fuel Bundle Test (BFBT) benchmark. The assessment activity is performed comparing the code calculation results with available in the framework of the benchmark experimental data from Japanese Nuclear Power Engineering Corporation (NUPEC). Two-phase flow calculations on prediction of the critical power have been carried out both in steady state and transient cases, using one-dimensional and three-dimensional modelling. Results of the steady-state critical power tests calculation have shown the ability of CATHARE code to predict reasonably the critical power and its location, using appropriate modelling.

  5. FAVOR: A new fracture mechanics code for reactor pressure vessels subjected to pressurized thermal shock

    International Nuclear Information System (INIS)

    Dickson, T.L.

    1993-01-01

    This report discusses probabilistic fracture mechanics (PFM) analysis which is a major element of the comprehensive probabilistic methodology endorsed by the NRC for evaluation of the integrity of Pressurized Water Reactor (PWR) pressure vessels subjected to pressurized-thermal-shock (PTS) transients. It is anticipated that there will be an increasing need for an improved and validated PTS PFM code which is accepted by the NRC and utilities, as more plants approach the PTS screening criteria and are required to perform plant-specific analyses. The NRC funded Heavy Section Steel Technology (HSST) Program at Oak Ridge National Laboratories is currently developing the FAVOR (Fracture Analysis of Vessels: Oak Ridge) PTS PFM code, which is intended to meet this need. The FAVOR code incorporates the most important features of both OCA-P and VISA-II and contains some new capabilities such as PFM global modeling methodology, the capability to approximate the effects of thermal streaming on circumferential flaws located inside a plume region created by fluid and thermal stratification, a library of stress intensity factor influence coefficients, generated by the NQA-1 certified ABAQUS computer code, for an adequate range of two and three dimensional inside surface flaws, the flexibility to generate a variety of output reports, and user friendliness

  6. Energy data base: subject thesaurus

    International Nuclear Information System (INIS)

    Redford, J.S.

    1981-10-01

    The technical staff of the DOE Technical Information Center, during its subject indexing activities, develops and structures a vocabulary that allows consistent machine storage and retrieval of information necessary to the accomplishment of the DOE mission. This thesaurus incorporates that structured vocabulary. The terminology of this thesaurus is used for the subject control of information announced in DOE Energy Research Abstracts, Energy Abstracts for Policy Analysis, and various update journals and bulletins in specialized areas. This terminology also facilitates subject searching of the DOE Energy Data Base on the DOE/RECON on-line retrieval system and on other commercial retrieval systems. The rapid expansion of the DOE's activities will result in a commitant thesaurus expansion as information relating to new activities is indexed. Only the terms used in the indexing of documents at the Technical Information Center to date are included

  7. Large-scale international validation of the ADO index in subjects with COPD

    DEFF Research Database (Denmark)

    Puhan, Milo A; Hansel, Nadia N; Sobradillo, Patricia

    2012-01-01

    BACKGROUND: Little evidence on the validity of simple and widely applicable tools to predict mortality in patients with chronic obstructive pulmonary disease (COPD) exists. OBJECTIVE: To conduct a large international study to validate the ADO index that uses age, dyspnoea and FEV(1) to predict 3......-IV. MEASUREMENTS: We validated the original ADO index. We then obtained an updated ADO index in half of our cohorts to improve its predictive accuracy, which in turn was validated comprehensively in the remaining cohorts using discrimination, calibration and decision curve analysis and a number of sensitivity......-to-moderate risk of 3-year mortality than FEV(1) alone. INTERPRETATION: The updated 15-point ADO index accurately predicts 3-year mortality across the COPD severity spectrum and can be used to inform patients about their prognosis, clinical trial study design or benefit harm assessment of medical interventions....

  8. NRC safety research in support of regulation, 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  9. Review and critique of April 10, 1985 exercise at the new NRC Operations Center

    International Nuclear Information System (INIS)

    Laats, E.T.; Charlton, T.R.; Bryan, G.R.; Beelman, R.J.; Bray, M.A.; Bethke, G.A.; King, M.A.

    1985-07-01

    An emergency preparedness training exercise was conducted. Objectives of the exercise addressed how well the new Operations Center was utilized when responding to an incident at a nuclear power plant. The simulated accident portrayed a small (approx.75 gpm) leak from the Turkey Point Unit 3 primary coolant system, that led to radionuclide release that exceeded EPA guidelines at the site boundary. The Operation Center response was led by NRC Chairman Nunzio J. Palladino and the roles of the simulated power plant and other outside organizations were jointly portrayed by EG and G Idaho, COMEX Corporation and the NRC's Office of Inspection and Enforcement. Overall, the exercise was successful. The new Operations Center facility provided capabilities and services never before available, which significantly aided the performance of the Operations Center staff. The various teams that manned the Center performed credibly. Substantial improvement in team performance was noted over the past several exercises

  10. NRC perspective on extended on-site storage of low-level radioactive waste after 1993

    International Nuclear Information System (INIS)

    Remick, Forrest J.

    1992-01-01

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires that each State, which has not provided for disposal capacity by January 1, 1993, must take title and possession of the low-level radioactive wastes generated in the State. If the states do not take title and possession of the wastes, the rebates to which the states would have been entitled to would be returned to the waste generators. in considering the matter, the Commission solicited comments from States) low-level radioactive waste compacts, local governments, and the general public so that the public's views could be factored into the Commission's deliberations on this issue. This paper addresses the current status of NRC positions on the adequacy of the NRC's existing regulatory framework associated with the title transfer provisions of the LLRWPAA and the Commission's views on extended on-site storage of low-level radioactive wastes after the 1993 and 1996 milestones. (author)

  11. NRC Seismic Design Margins Program Plan

    International Nuclear Information System (INIS)

    Cummings, G.E.; Johnson, J.J.; Budnitz, R.J.

    1985-08-01

    Recent studies estimate that seismically induced core melt comes mainly from earthquakes in the peak ground acceleration range from 2 to 4 times the safe shutdown earthquake (SSE) acceleration used in plant design. However, from the licensing perspective of the US Nuclear Regulatory Commission, there is a continuing need for consideration of the inherent quantitative seismic margins because of, among other things, the changing perceptions of the seismic hazard. This paper discusses a Seismic Design Margins Program Plan, developed under the auspices of the US NRC, that provides the technical basis for assessing the significance of design margins in terms of overall plant safety. The Plan will also identify potential weaknesses that might have to be addressed, and will recommend technical methods for assessing margins at existing plants. For the purposes of this program, a general definition of seismic design margin is expressed in terms of how much larger that the design basis earthquake an earthquake must be to compromise plant safety. In this context, margin needs to be determined at the plant, system/function, structure, and component levels. 14 refs., 1 fig

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  13. ABC Transporter for Corrinoids in Halobacterium sp. Strain NRC-1†

    OpenAIRE

    Woodson, Jesse D.; Reynolds, April A.; Escalante-Semerena, Jorge C.

    2005-01-01

    We report evidence for the existence of a putative ABC transporter for corrinoid utilization in the extremely halophilic archaeon Halobacterium sp. strain NRC-1. Results from genetic and nutritional analyses of Halobacterium showed that mutants with lesions in open reading frames (ORFs) Vng1370G, Vng1371Gm, and Vng1369G required a 105-fold higher concentration of cobalamin for growth than the wild-type or parent strain. The data support the conclusion that these ORFs encode orthologs of the b...

  14. 75 FR 20009 - Development of NRC's Safety Culture Policy Statement: Cancellation of Public Workshops Scheduled...

    Science.gov (United States)

    2010-04-16

    ... included the development of the safety culture common terminology effort comprised of: (1) Development of a... alignment on the safety culture common terminology effort. The NRC held the first workshop on February 2-4... of individual industry groups, such as, [[Page 20010

  15. NRC TLD [thermoluminescent dosimeter] Direct Radiation Monitoring Network: Progress report, October--December 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; NcNamara, N.

    1989-04-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1988. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 4 tabs

  16. Influence of body mass index on short-term subjective improvement and risk of reoperation after mid-urethral sling surgery

    DEFF Research Database (Denmark)

    Weltz, Vibeke; Guldberg, Rikke; Larsen, Michael D.

    2018-01-01

    Introduction and hypothesis: The objective was to evaluate the impact of body mass index (BMI) on the subjective improvement and risk of reoperation after first-time mid-urethral sling surgery. Methods: Data were retrieved from the national Danish Urogynaecological Database, including women...... was defined as any new surgical procedure for stress urinary incontinence performed within the study period. Results: During the study period, 6,414 mid-urethral sling procedures were performed; 80.0% of these women filled out both pre- and post-surgical International Consultation on Incontinence...

  17. Responsiveness and minimum important change of the Oswestry Disability Index in Italian subjects with symptomatic lumbar spondylolisthesis.

    Science.gov (United States)

    Vanti, Carla; Ferrari, Silvano; Villafañe, Jorge Hugo; Berjano, Pedro; Monticone, Marco

    2017-06-01

    This study aims to investigate the responsiveness and the minimum important change of the Italian version of the Oswestry Disability Index (ODI-I) in subjects with symptomatic specific low back pain associated with lumbar spondylolisthesis (SPL). One hundred and fifty-one patients with symptomatic SPL completed the ODI-I, a 0-100 numerical rating scale (NRS), and performed the prone and supine bridge tests. The global perception of effectiveness was measured with a 7-point Likert scale. Responsiveness was assessed by distribution methods (minimum detectable change [MDC], effect size [ES], standardized response mean [SRM]) and anchor-based methods (ROC curves). The MDC was 4.23, the ES was 0.95 and the SRM was 1.25. ROC analysis revealed an area under the curve of 0.76 indicating moderate discriminating capacity. The best cut-off point for the dichotomous outcome was 7.5 (sensitivity 90.3%, specificity 56.7%). . The ODI-I proved to be responsive in detecting changes after conservative treatment in subjects with lumbar SPL. II.

  18. Title list of documents made publicly available, July 1-31, 1979

    International Nuclear Information System (INIS)

    1979-09-01

    This document is a monthly publication containing descriptions of information received and generated by the US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The docketed information includes information formerly issued through US DOE's Technical Information Center under the title Power Reactor Docket Information (PRDI). This document replaces PRDI, which will no longer be prepared. It is indexed by a Personal Author Index, Corporate Source Index, US NRC Organizational Source Index and Personal Author Index

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

    International Nuclear Information System (INIS)

    1988-05-01

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

  20. What it took to get an NRC license for centralized incineration

    International Nuclear Information System (INIS)

    DiSalvo, R.; Zielenbach, W.

    1987-01-01

    In 1982, Battelle joined five other commercial generators of low level radioactive waste in conducting a study of the technical and economic feasibility and the licensability of a central facility for incinerating LLW. The project generated a license application to the USNRC and supporting documentation related to the safety and environmental impacts of the facility. After thorough review, the NRC has issued a Finding of No Significant Impact and the associated license authorization, which is the first of its kind for an incineration facility

  1. Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1983-01-01

    This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  2. Significant decrease of saturation index in erythrocytes membrane from subjects with non-alcoholic fatty liver disease (NAFLD).

    Science.gov (United States)

    Notarnicola, Maria; Caruso, Maria Gabriella; Tutino, Valeria; Bonfiglio, Caterina; Cozzolongo, Raffaele; Giannuzzi, Vito; De Nunzio, Valentina; De Leonardis, Giampiero; Abbrescia, Daniela I; Franco, Isabella; Intini, Vincenza; Mirizzi, Antonella; Osella, Alberto R

    2017-08-23

    The lipidomic profiling of erythrocyte membranes is expected to provide a peculiar scenario at molecular level of metabolic and nutritional pathways which may influence the lipid balance and the adaptation and homeostasis of the organism. Considering that lipid accumulation in the cell is important in promoting tissue inflammation, the purpose of this study is to analyze the fatty acid profile in red blood cell membranes of patients with Non-Alcoholic Fatty Liver Disease (NAFLD), in order to identify and validate membrane profiles possibly associated with the degree of hepatic damage. This work presents data obtained at baseline from 101 subjects that participated to a nutritional trial (registration number: NCT02347696) enrolling consecutive subjects with NAFLD. Diagnosis of liver steatosis was performed by using vibration-controlled elastography implemented on FibroScan. Fatty acids, extracted from phospholipids of erythrocyte membranes, were quantified by gas chromatography method. The subjects with severe NAFLD showed a significant decrease of the ratio of stearic acid to oleic acid (saturation index, SI) compared to controls, 1.281 ± 0.31 vs 1.5 ± 0.29, respectively. Low levels of SI in red blood cell membranes, inversely associated with degree of liver damage, suggest that an impairment of circulating cell membrane structure can reflect modifications that take place in the liver. Subjects with severe NAFLDalso showed higher levels of elongase 5 enzymatic activity, evaluated as vaccenic acid to palmitoleic acid ratio. Starting from these evidences, our findings show the importance of lipidomic approach in the diagnosis and the staging of NAFLD.

  3. Validação das equações do NRC (2001 para predição do valor energético de alimentos nas condições brasileiras Validation of NRC (2001 equations for estimation of energy value of feeds in Brazilian conditions

    Directory of Open Access Journals (Sweden)

    Marcos Antonio Lana Costa

    2005-02-01

    Full Text Available O estudo foi conduzido para estimar os valores energéticos (NDT de vários alimentos, concentrados e volumosos e validar as equações propostas pelo NRC (2001 por meio da comparação dos valores estimados por estas equações, com os observados, obtidos a partir da coleta total de fezes. Foram avaliados cinco alimentos concentrados (farelo de trigo, farelo de soja, fubá de milho, grão de soja e caroço de algodão e cinco volumosos (feno de capim-braquiária, silagem de milho, silagem pré-seca de capim-tifton, silagem de capim-elefante e capim-elefante utilizando-se 20 novilhos mestiços HolandêsxZebu. O procedimento de validação das variáveis avaliadas foi realizado por intermédio do ajuste do modelo de regressão linear simples dos valores preditos e observados. Os valores de NDT dos alimentos concentrados e volumosos observados e preditos pelas equações do NRC (2001 foram similares (P>0,05. Conclui-se que as equações do NRC (2001 foram adequadas para estimar o valor energético dos alimentos nas condições brasileiras.This research was developed to estimate the energy values (TDN of feeds, concentrate and roughage, through equations proposed by NRC (2001 and validate from the comparison among TDN values estimated by these equations and those observed in the total collection feces. Five concentrate feeds (wheat bran, soybean meal, corn ground, whole soybean and whole cotton seed an five roughage feeds (brachiaria hay, corn silage, tifton haylage, elephant grass silage and elephantgrass were evaluated by using 20 crossbred Holstein x Zebu steers. The procedure to validate the variables evaluated was done by adjusting models of simple linear regression using predicted and observed values. The observed and predicted value of TDN values for roughage and concentrate feeds were similar (P>0,05. It was concluded that the equations proposed by NRC (2001 were efficient to estimate the TDN values of feeds under brazilian conditions.

  4. 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.

  5. The ruins of neo-liberalism and the construction of a new (scientific) subjectivity

    Science.gov (United States)

    Lather, Patti

    2012-12-01

    Given my long-time interests in neoliberalism and questions of subjectivity, I am pleased to respond to Jesse Bazzul's paper, "Neoliberal Ideology, global capitalism, and science education: Engaging the question of subjectivity." In what follows, I first summarize what I see as Bazzul's contributions to pushing science education in `post' directions. I next introduce the concept of "post-neoliberalism" as a tool in this endeavor. Finally, I address what all of this might have to do with subjectivity in the context of science education. I speak as a much-involved veteran of a version of the science wars fought out in education research for the last decade (NRC 2002). My interest is to use this "battle" to think politics and science anew toward an engaged social science, without certainty, rethinking subjectivity, the unconscious and bodies where I ask "what kind of science for what kind of politics?"

  6. Title list of documents made publicly available: September 1--30, 1996. Volume 18, Number 9

    International Nuclear Information System (INIS)

    1996-11-01

    The report describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  7. Title list of documents made publicly available: April 1--30, 1996. Volume 18, Number 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    This publication describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  8. Title list of documents made publicly available: April 1--30, 1996. Volume 18, Number 4

    International Nuclear Information System (INIS)

    1996-06-01

    This publication describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  9. Title list of documents made publicly available: June 1--30, 1995. Volume 17, Number 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  10. Title list of documents made publicly available: June 1--30, 1995. Volume 17, Number 6

    International Nuclear Information System (INIS)

    1995-08-01

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  11. Title list of documents made publicly available: September 1--30, 1996. Volume 18, Number 9

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The report describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  12. Title List of documents made publicly available

    International Nuclear Information System (INIS)

    1982-05-01

    This document contains descriptions of the information received and generated by the US NRC. This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  13. Automatic inference of indexing rules for MEDLINE

    Directory of Open Access Journals (Sweden)

    Shooshan Sonya E

    2008-11-01

    Full Text Available Abstract Background: Indexing is a crucial step in any information retrieval system. In MEDLINE, a widely used database of the biomedical literature, the indexing process involves the selection of Medical Subject Headings in order to describe the subject matter of articles. The need for automatic tools to assist MEDLINE indexers in this task is growing with the increasing number of publications being added to MEDLINE. Methods: In this paper, we describe the use and the customization of Inductive Logic Programming (ILP to infer indexing rules that may be used to produce automatic indexing recommendations for MEDLINE indexers. Results: Our results show that this original ILP-based approach outperforms manual rules when they exist. In addition, the use of ILP rules also improves the overall performance of the Medical Text Indexer (MTI, a system producing automatic indexing recommendations for MEDLINE. Conclusion: We expect the sets of ILP rules obtained in this experiment to be integrated into MTI.

  14. NRC's rulemaking to require materials licensees to be financially responsible for cleanup of accidental releases

    International Nuclear Information System (INIS)

    Seeman, M.J.

    1987-01-01

    On June 7, 1985, the US Nuclear Regulatory Commission (NRC) published an advance notice of proposed rulemaking (ANPRM) in the Federal Register to address funding for cleanup of accidents and unexpected decontamination by certain materials licensees. The NRC asked for public comment to help them determine whether to amend its regulations to require certain materials and fuel cycle licensees to demonstrate that they possess adequate financial means to pay for cleanup of accidental releases of radioactive materials. If licensees lack adequate financial resources and funds are to available for prompt cleanup, the consequences could be potentially significant for the public, the licencee and the federal government. The purpose of this paper is to explain the purpose and scope of the Commission's proposed regulatory action, as well as describing several accidents that made the Commission consider this action. Additionally, the paper will address other regulatory precedents. Finally, the paper will conclude by generally characterizing the public comments and items of concern raised by commenters

  15. Applications of probabilistic techniques at NRC

    International Nuclear Information System (INIS)

    Thadani, A.; Rowsome, F.; Speis, T.

    1984-01-01

    The NRC is currently making extensive use of probabilistic safety assessment in the reactor regulation. Most of these applications have been introduced in the regulatory activities in the past few years. Plant Probabilistic Safety Studies are being utilized as a design tool for applications for standard designs and for assessment of plants located in regions of particularly high population density. There is considerable motivation for licenses to perform plant-specific probabilistic studies for many, if not all, of the existing operating nuclear power plants as a tool for prioritizing the implementation of the many outstanding licensing actions of these plants as well as recommending the elimination of a number of these issues which are judged to be insignificant in terms of their contribution to safety and risk. Risk assessment perspectives are being used in the priorization of generic safety issues, development of technical resolution of unresolved safety issues, assessing safety significance of proposed new regulatory requirements, assessment of safety significance of some of the occurrences at operating facilities and in environmental impact analyses of license applicants as required by the National Environmental Policy Act. (orig.)

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-07-01

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

  18. NRC Microwave Refractive Index Gas Thermometry Implementation Between 24.5 K and 84 K

    Science.gov (United States)

    Rourke, P. M. C.

    2017-07-01

    The implementation of microwave refractive index gas thermometry at the National Research Council between 24.5 K and 84 K is reported. A new gas-handling system for accurate control and measurement of experimental gas pressure has been constructed, and primary thermometry measurements have been taken using a quasi-spherical copper resonator and helium gas at temperatures corresponding to three defining fixed points of the International Temperature Scale of 1990 (ITS-90). These measurements indicate differences between the thermodynamic temperature T and ITS-90 temperature T_{90} of ( T - T_{90} ) = -0.60 ± 0.56 mK at T_{90} = 24.5561 K, ( T - T_{90} ) = -2.0 ± 1.3 mK at T_{90} = 54.3584 K, and ( T - T_{90} ) = -4.0 ± 2.9 mK at T_{90} = 83.8058 K. The present results at T_{90} = 24.5561 K and T_{90} = 83.8058 K agree with previously reported measurements from other primary thermometry techniques of acoustic gas thermometry and dielectric constant gas thermometry, and the result at T_{90} = 54.3584 K provides new information in a temperature region where there is a gap in other recent data sets.

  19. 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

  20. 7 CFR 1770.3 - Index of records.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 12 2010-01-01 2010-01-01 false Index of records. 1770.3 Section 1770.3 Agriculture... Index of records. (a) Each borrower shall maintain a master index of records. The master index shall... maintained. The master index shall be subject to review by RUS and RUS shall reserve the right to add records...