WorldWideScience

Sample records for safety review advisory

  1. Development of web-based safety review advisory system

    International Nuclear Information System (INIS)

    Kim, M. W.; Lee, H. C.; Park, S. O.; Lee, K. H.; Hur, K. Y.; Lee, S. J.; Choi, S. S.; Kang, C. M.

    2002-01-01

    For the development of an expert system supporting the safety review of nuclear power plants, the application was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they are investigated by KINS (Korea Institute of Nuclear Safety). The Safety Review Advisory System(SRAS), this application on web-server environment was developed according to the above specifications. Reviews can do their safety reviewing regardless of their speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into four groups, administrator, project manager, project reviewer and general reviewer. Each user group is delegated appropriate access capability. The function and some screen shots of SRAS are described

  2. Development of web-based safety review advisory system

    International Nuclear Information System (INIS)

    Kim, M. W.; Hur, K. Y.; Lee, S. J.; Choi, S. J.

    2002-01-01

    For the development of an expert system supporting the safety review of nuclear power plants, the application was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they are investigated by KINS. Safety Review Advisory System (SRAS), this application on web-server environment was developed according to the above specifications. Reviews can do their safety reviewing regardless of their speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into four groups, administrator, project manager, project reviewer and general reviewer. Each user group is delegated appropriate access capability. The function and some screen shots of SRAS are described

  3. Development of safety review advisory system for nuclear power plants

    International Nuclear Information System (INIS)

    Kim, M. W.; Lee, H. C.; Park, S. O.; Park, W. J.; Lee, J. I.; Hur, K. Y.; Choi, S. S.; Lee, S. J.; Kang, C. M.

    2001-01-01

    For the development of an expert system supporting the safety review of nuclear power plants, the application program was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they were investigated by the safety review experts at KINS. Safety Review Advisory System (SRAS), the windows application on client-server environment was developed according to the above specifications. Reviewers can do their safety reviewing regardless of speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into three groups, administrator, project manager, and reviewer. Each user group has appropriate access capability. The function and some screen shots of SRAS are described in this paper

  4. 76 FR 62455 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-10-07

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-088)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel... Burch, Aerospace Safety Advisory Panel Administrative Officer, National Aeronautics and Space...

  5. 78 FR 1265 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-01-08

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-001] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel..., Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space Administration...

  6. 76 FR 19147 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2011-04-06

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-030)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel.... Kathy Dakon, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  7. 78 FR 56941 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-09-16

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: 13-114] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel.... Harmony Myers, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  8. 77 FR 25502 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-04-30

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (12-030)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel... FURTHER INFORMATION CONTACT: Ms. Harmony Myers, Aerospace Safety Advisory Panel Executive Director...

  9. 77 FR 38090 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2012-06-26

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-044] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel.... Harmony Myers, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  10. 75 FR 61219 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-10-04

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-116)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel... Dakon, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space Administration...

  11. 77 FR 58413 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-09-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-074] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel.... Harmony Myers, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  12. 75 FR 6407 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-02-09

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10- 020)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel... FURTHER INFORMATION CONTACT: Ms. Kathy Dakon, Aerospace Safety Advisory Panel Executive Director, National...

  13. 78 FR 36793 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-06-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-068] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel..., Huntsville, AL 35805 FOR FURTHER INFORMATION CONTACT: Ms. Harmony Myers, Aerospace Safety Advisory Panel...

  14. 78 FR 57903 - Aerospace Safety Advisory Panel; Charter Renewal

    Science.gov (United States)

    2013-09-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: 13-116] Aerospace Safety Advisory Panel... and amendment of the charter of the Aerospace Safety Advisory Panel. SUMMARY: Pursuant to sections 14... determined that renewal and amendment of the charter of the Aerospace Safety Advisory Panel is in the public...

  15. 76 FR 65750 - Aerospace Safety Advisory Panel; Charter Renewal

    Science.gov (United States)

    2011-10-24

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-105)] Aerospace Safety Advisory Panel... and amendment of the charter of the NASA Aerospace Safety Advisory Panel. SUMMARY: Pursuant to... determined that a renewal and amendment of the charter of the NASA Aerospace Safety Advisory Panel is in the...

  16. 76 FR 52016 - NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-08-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-074)] NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space... meeting of the NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel...

  17. 75 FR 36697 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-06-28

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-071)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel..., Room 116, Hampton, VA 23681. FOR FURTHER INFORMATION CONTACT: Ms. Kathy Dakon, Aerospace Safety...

  18. Patients' and healthcare workers' perceptions of a patient safety advisory.

    Science.gov (United States)

    Schwappach, David L B; Frank, Olga; Koppenberg, Joachim; Müller, Beat; Wasserfallen, Jean-Blaise

    2011-12-01

    To assess patients' and healthcare workers' (hcw) attitudes and experiences with a patient safety advisory, to investigate predictors for patients' safety-related behaviors and determinants for staff support for the advisory. Cross-sectional surveys of patients (n= 1053) and hcw (n= 275). Three Swiss hospitals. Patients who received the safety advisory and hcw caring for these patients. Patient safety advisory disseminated to patients at the study hospitals. Attitudes towards and experiences with the advisory. Hcw support for the intervention and patients' intentions to apply the recommendations were modelled using regression analyses. Patients (95%) and hcw (78%) agreed that hospitals should educate patients how to prevent errors. Hcw and patients' evaluations of the safety advisory were positive and followed a similar pattern. Patients' intentions to engage in safety were significantly predicted by behavioral control, subjective norms, attitudes, safety behaviors during hospitalization and experiences with taking action. Hcw support for the campaign was predicted by rating of the advisory (Odds ratio (OR) 3.4, confidence interval (CI) 1.8-6.1, Ppatients (OR 1.9, CI 1.1-3.3, P= 0.034) and experience of unpleasant situations (OR 0.6, CI 0.4-1.0, P= 0.035). The safety advisory was well accepted by patients and hcw. To be successful, the advisory should be accompanied by measures that target norms and barriers in patients, and support staff in dealing with difficult situations.

  19. 76 FR 23339 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-04-26

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-043)] Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of meeting... Register of April 6, 2011, announcing a meeting of the Aerospace Safety Advisory Panel (ASAP) to take place...

  20. 76 FR 24504 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2011-05-02

    ... DEPARTMENT OF HOMELAND SECURITY [Docket No. USCG-2011-0183] National Offshore Safety Advisory... Committee Meeting. SUMMARY: The National Offshore Safety Advisory Committee (NOSAC) will meet on May 19... completed its business. ADDRESSES: The meeting will be held at Wyndham Riverfront Hotel, Bacchus room, 701...

  1. 76 FR 32390 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2011-06-06

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee (MCSAC) Meeting. SUMMARY...

  2. 77 FR 46555 - Motor Carrier Safety Advisory Committee: Public Meeting

    Science.gov (United States)

    2012-08-03

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee: Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of meeting of Motor Carrier Safety Advisory Committee (MCSAC...

  3. 75 FR 2923 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-01-19

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA...

  4. 75 FR 29384 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-05-25

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2010-0143] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee meeting. SUMMARY: FMCSA...

  5. 75 FR 72863 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-11-26

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration, DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA announces...

  6. 75 FR 50797 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-08-17

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2010-0143] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA...

  7. 78 FR 70623 - Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory...

    Science.gov (United States)

    2013-11-26

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2009-0203] Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory Committee AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. [[Page...

  8. 78 FR 16045 - Safety Advisory: Unauthorized Marking of Compressed Gas Cylinders

    Science.gov (United States)

    2013-03-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0019; Notice No. 13-03] Safety Advisory: Unauthorized Marking of Compressed Gas Cylinders AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Safety Advisory...

  9. 76 FR 5424 - Motor Carrier Safety Advisory Committee; Request for Nominations

    Science.gov (United States)

    2011-01-31

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee; Request for Nominations AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Request for Nominations to the Motor Carrier Safety Advisory...

  10. 76 FR 60535 - Federal Advisory Council on Occupational Safety and Health

    Science.gov (United States)

    2011-09-29

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA--2011-0116] Federal Advisory Council on Occupational Safety and Health AGENCY: Occupational Safety and Health... the Federal Advisory Council on Occupational Safety and Health (FACOSH) until October 31, 2011. DATES...

  11. 78 FR 38346 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2013-06-26

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act...

  12. 77 FR 65000 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-10-24

    ...] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug...: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide... Use (ETASU) before CDER's Drug Safety and Risk Management Advisory Committee (DSaRM). The Agency plans...

  13. 78 FR 30929 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2013-05-23

    ...] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug...: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide... (REMS) with elements to assure safe use (ETASU) before its Drug Safety and Risk Management Advisory...

  14. 76 FR 32374 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2011-06-06

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0065] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and NACOSH subgroups. SUMMARY: The National Advisory...

  15. 75 FR 28659 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2010-05-21

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0012] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH). SUMMARY: The National Advisory Committee on Occupational...

  16. 77 FR 46126 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2012-08-02

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0003] Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and... Advisory Committee for Occupational Safety and Health. SUMMARY: OSHA invites interested persons to submit...

  17. 78 FR 21977 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2013-04-12

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and Health Administration (OSHA), Labor... Maritime Advisory Committee for Occupational Safety and Health. The Committee will better enable OSHA to...

  18. 76 FR 73689 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2011-11-29

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0065] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and NACOSH Work Groups. SUMMARY: The National Advisory...

  19. 76 FR 38183 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2011-06-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  20. 76 FR 11483 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2011-03-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  1. 78 FR 19268 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2013-03-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  2. 75 FR 78998 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2010-12-17

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  3. 78 FR 78965 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2013-12-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  4. 77 FR 40890 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2012-07-11

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  5. 77 FR 15761 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2012-03-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  6. 78 FR 732 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2013-01-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  7. 78 FR 78963 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2013-12-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  8. 78 FR 62635 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2013-10-22

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  9. 75 FR 39029 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2010-07-07

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  10. 76 FR 77235 - Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH...

    Science.gov (United States)

    2011-12-12

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Subcommittee on Procedures Review, Advisory Board on Radiation and Worker Health (ABRWH), National Institute for Occupational Safety and Health (NIOSH) In accordance with section 10(a)(2) of the Federal Advisory Committee Act (Pub...

  11. 75 FR 62147 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2010-10-07

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0031] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Advisory Council on Occupational Safety and Health (FACOSH) will meet October 21, 2010, in Washington, DC...

  12. 77 FR 22355 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0006] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Federal Advisory Council on Occupational Safety and Health (FACOSH) will meet May 3, 2012, in Washington...

  13. 76 FR 71077 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2011-11-16

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0192] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Federal Advisory Council on Occupational Safety and Health (FACOSH) will meet Thursday, December 1, 2011...

  14. 78 FR 30337 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2013-05-22

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2013-0013] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Federal Advisory Council on Occupational Safety and Health (FACOSH) will meet on June 6, 2013, in...

  15. 76 FR 28816 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2011-05-18

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0061] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Advisory Council on Occupational Safety and Health (FACOSH) will meet June 7, 2011, in Washington, DC. On...

  16. 77 FR 26790 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2012-05-07

    ... Safety Officer Medal of Valor Review Board AGENCY: Office of Justice Programs (OJP), Bureau of Justice... meeting (via conference call-in) of the Public Safety Officer Medal of Valor Review Board (``Board'') to... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions...

  17. 29 CFR 1912.5 - National Advisory Committee on Occupational Safety and Health.

    Science.gov (United States)

    2010-07-01

    ... Health. 1912.5 Section 1912.5 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND... Matters § 1912.5 National Advisory Committee on Occupational Safety and Health. (a) Section 7(a) of the Act established a National Advisory Committee on Occupational Safety and Health. The Committee is to...

  18. 75 FR 17417 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-04-06

    ...] Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory... Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory Committee. This meeting was... Drug Safety and Risk Management Advisory Committee would be held on May 12, 2010. On page 10490, in the...

  19. 76 FR 27337 - Houston/Galveston Navigation Safety Advisory Committee

    Science.gov (United States)

    2011-05-11

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [USCG-2010-1116] Houston/Galveston Navigation Safety...: The Houston/Galveston Navigation Safety Advisory Committee postponed its originally scheduled February... Houston Ship Channel, and various other navigation safety matters in the Galveston Bay area. The meeting...

  20. 78 FR 66801 - Motor Carrier Safety Advisory Committee; Charter Renewal

    Science.gov (United States)

    2013-11-06

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee; Charter Renewal AGENCY: Federal Motor Carrier Safety... and recommendations on motor carrier safety programs and motor carrier safety regulations through a...

  1. 77 FR 75176 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-12-19

    ...] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug... being rescheduled due to the postponement of the October 29-30, 2012, Drug Safety and Risk Management... Committee: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide...

  2. 78 FR 41496 - Pipeline Safety: Meetings of the Gas and Liquid Pipeline Advisory Committees

    Science.gov (United States)

    2013-07-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0156] Pipeline Safety: Meetings of the Gas and Liquid Pipeline Advisory Committees AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of advisory committee...

  3. 75 FR 54915 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2010-09-09

    ... Safety Officer Medal of Valor Review Board AGENCY: Office of Justice Programs (OJP), Justice. ACTION... Officer Medal of Valor Review Board to vote on recommendations for the 2009-2010 Medal of Valor... Public Safety Officer Medal of Valor Review Board carries out those advisory functions specified in 42 U...

  4. 76 FR 8372 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2011-02-14

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2011-0070] Commercial Fishing Safety... Commercial Fishing Safety Advisory Committee (CFSAC) will meet in Portsmouth, Virginia to discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to the public...

  5. 77 FR 40622 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2012-07-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH..., oxygen supply partnership, safety culture, occupational health and safety management systems, preventing...

  6. 77 FR 62248 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2012-10-12

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2012-0936] Commercial Fishing Safety.... SUMMARY: The Commercial Fishing Safety Advisory Committee (CFSAC) will meet in Washington, DC to discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to the...

  7. 78 FR 44958 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2013-07-25

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2013-0625] Commercial Fishing Safety.... SUMMARY: The Commercial Fishing Safety Advisory Committee (CFSAC) will meet in Washington, DC to discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to the...

  8. 78 FR 58604 - Safety Advisory: Unauthorized Marking of Compressed Gas Cylinders

    Science.gov (United States)

    2013-09-24

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Safety Advisory... Investigator, Eastern Region, Office of Hazardous Materials Safety, Pipeline and Hazardous Materials Safety...

  9. 76 FR 23810 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

    Science.gov (United States)

    2011-04-28

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response Interoperability Center Public Safety Advisory Committee Meeting AGENCY... Fullano, Associate Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission...

  10. Report of the summative evaluation by the advisory committee on nuclear safety research

    International Nuclear Information System (INIS)

    2005-03-01

    The Research Evaluation Committee of the Japan Atomic Energy Research Institute (JAERI) set up an Advisory Committee on Nuclear Safety Research in accordance with the 'Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations. The Advisory Committee on Nuclear Safety Research evaluated the adequacy of the plans of nuclear safety research to be succeeded from JAERI to a new research institute which will be established by integration of JAERI and the Japan Nuclear Cycle Development Institute (JNC). The Advisory Committee consisted of eight specialists from outside the JAERI conducted its activities from June 2004 to August 2004. The evaluation was performed on the basis of the materials submitted in advanced and of the oral presentations made at the Advisory Committee meeting which was held on July 27, 2004, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Advisory Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on December 1, 2004. This report describes the result of the evaluation by the Advisory Committee on Safety Research. (author)

  11. 75 FR 23782 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2010-05-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug...: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide...

  12. 75 FR 51473 - Houston/Galveston Navigation Safety Advisory Committee

    Science.gov (United States)

    2010-08-20

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2010-0656] Houston/Galveston... Houston/Galveston Navigation Safety Advisory Committee (HOGANSAC) and its working groups will meet in Houston, Texas, to discuss waterway improvements, aids to navigation, area projects impacting safety on...

  13. 78 FR 54923 - Federal Advisory Council on Occupational Safety and Health

    Science.gov (United States)

    2013-09-06

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2013-0013] Federal Advisory Council on Occupational Safety and Health AGENCY: Occupational Safety and Health... Occupational Safety and Health (FACOSH). SUMMARY: The Assistant Secretary of Labor for Occupational Safety and...

  14. 78 FR 40743 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2013-07-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... Director, NIOSH, on priorities in mine safety and health research, including grants and contracts for such...

  15. 77 FR 67658 - Navigation Safety Advisory Council

    Science.gov (United States)

    2012-11-13

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2012-0212] Navigation Safety Advisory.../en/hotels/florida/embassy-suites-tampa-downtown-convention-center-TPAESES/index.html . For... possible. To facilitate public participation, we are inviting public comment on the issues to be considered...

  16. 75 FR 12554 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2010-03-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... priorities in mine safety and health research, including grants and contracts for such research, 30 U.S.C...

  17. 75 FR 52988 - National Advisory Committee on Occupational Safety and Health

    Science.gov (United States)

    2010-08-30

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0012] National Advisory Committee on Occupational Safety and Health AGENCY: Occupational Safety and Health... Occupational Safety and Health (NACOSH) will meet September 14 and 15, 2010, in Washington, DC. In conjunction...

  18. Recommendations and comments on the report of the Ontario Nuclear Safety Review

    International Nuclear Information System (INIS)

    1988-12-01

    The report of the Ontario Nuclear Safety Review (ONSR) prepared by Dr. F. Kenneth Hare in March 1988, is reviewed by the Advisory Committee on Nuclear Safety (ACNS) to assess for the Atomic Energy Control Board the relevance and importance of the ONSR recommendations and comments. The ACNS conclusions from this study are embodied in nineteen recommendations, as well as several suggestions and some specific comments

  19. 78 FR 77501 - NASA Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-12-23

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: 13-153] NASA Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of Meeting...

  20. 78 FR 20327 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-04-04

    ... Management Advisory Committee; Amendment of Notice AGENCY: Food and Drug Administration, HHS. ACTION: Notice... of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk Management... Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee...

  1. 75 FR 57103 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-09-17

    ...-2010-0074] The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of... Future of Aviation Advisory Committee (FAAC): Aviation Safety Subcommittee; Notice of Meeting. SUMMARY... of the FAAC Aviation Safety Subcommittee, which will be held September 28, 2010, via teleconference...

  2. 75 FR 60163 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-09-29

    ...-2010-0074] The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of... Future of Aviation Advisory Committee (FAAC): Aviation Safety Subcommittee; Notice of Meeting. SUMMARY... of the FAAC Aviation Safety Subcommittee, which will be held October 19, 2010, in Everett, Washington...

  3. 77 FR 60507 - Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting

    Science.gov (United States)

    2012-10-03

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Meeting of Compliance, Safety...

  4. 77 FR 39743 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2012-07-05

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0022] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Occupational Safety and Health (FACOSH). SUMMARY: The Assistant Secretary of Labor for Occupational Safety and...

  5. 76 FR 39902 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2011-07-07

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0116] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Occupational Safety and Health (FACOSH). SUMMARY: The Assistant Secretary of Labor for Occupational Safety and...

  6. 75 FR 78775 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2010-12-16

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0012] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and NACOSH subgroup meetings. SUMMARY: The National...

  7. 75 FR 28661 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2010-05-21

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0012] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... Committee on Occupational Safety and Health (NACOSH). SUMMARY: The Assistant Secretary of Labor for...

  8. 76 FR 60085 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2011-09-28

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0065] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... Assistant Secretary of Labor for Occupational Safety and Health requests nominations for membership on...

  9. 77 FR 64549 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2012-10-22

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and a NACOSH Work Group. SUMMARY: NACOSH will meet...

  10. 75 FR 35090 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2010-06-21

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and Health Administration (OSHA), Labor... for Occupational Safety and Health (MACOSH or Committee) was established under Section 7 of the...

  11. 76 FR 54806 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2011-09-02

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0007] Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and... Committee for Occupational Safety and Health (MACOSH) was established under Section 7 of the Occupational...

  12. 77 FR 43616 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2012-07-25

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... Assistant Secretary of Labor for Occupational Safety and Health requests nominations for membership on...

  13. 77 FR 31398 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2012-05-25

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and NACOSH Work Groups. SUMMARY: NACOSH will meet June 20...

  14. 77 FR 58174 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2012-09-19

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0006] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Occupational Safety and Health (FACOSH) will meet October 18, 2012, in Washington, DC. DATES: FACOSH meeting...

  15. 77 FR 33495 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2012-06-06

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0003] Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and..., Docket No. OSHA- 2012-0003, U.S. Department of Labor, Occupational Safety and Health Administration, Room...

  16. 76 FR 18798 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2011-04-05

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No OSHA-2011-0007] Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and.... MACOSH will contribute to OSHA's performance of the duties imposed by the Occupational Safety and Health...

  17. 78 FR 68865 - Federal Advisory Council on Occupational Safety and Health (FACOSH)

    Science.gov (United States)

    2013-11-15

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2013-0013] Federal Advisory Council on Occupational Safety and Health (FACOSH) AGENCY: Occupational Safety and Health... Occupational Safety and Health (FACOSH) will meet December 5, 2013, in Washington, DC. DATES: FACOSH meeting...

  18. 77 FR 5577 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2012-02-03

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0003] Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and..., Docket No. OSHA- 2012-0003, U.S. Department of Labor, Occupational Safety and Health Administration, Room...

  19. 75 FR 13783 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH)

    Science.gov (United States)

    2010-03-23

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration Maritime Advisory Committee for Occupational Safety and Health (MACOSH) AGENCY: Occupational Safety and Health Administration (OSHA), Labor... Health (MACOSH) was established under Section 7 of the Occupational Safety and Health (OSH) Act of 1970...

  20. 75 FR 49508 - Navigation Safety Advisory Council; Vacancies

    Science.gov (United States)

    2010-08-13

    ... Council; Vacancies AGENCY: Coast Guard, DHS. ACTION: Request for applications. SUMMARY: The Coast Guard seeks applications for membership on the Navigation Safety Advisory Council (NAVSAC). This Committee... prevention of collisions, rammings, and groundings. This includes, but is not limited to: Inland and...

  1. 76 FR 33773 - Navigation Safety Advisory Council; Vacancies

    Science.gov (United States)

    2011-06-09

    ... Council; Vacancies AGENCY: Coast Guard, DHS. ACTION: Request for applications. SUMMARY: The Coast Guard seeks applications for membership on the Navigation Safety Advisory Council (NAVSAC). NAVSAC provides... the U.S. Coast Guard, on matters relating to prevention of maritime collisions, rammings, and...

  2. 75 FR 10629 - Federal Advisory Council on Occupational Safety and Health

    Science.gov (United States)

    2010-03-08

    ... Part III Department of Labor Occupational Safety and Health Administration Federal Advisory Council on Occupational Safety and Health; Notice #0;#0;Federal Register / Vol. 75, No. 44 / Monday, March 8, 2010 / Notices#0;#0; [[Page 10630

  3. 75 FR 29385 - Safety Advisory 2010-01

    Science.gov (United States)

    2010-05-25

    .... Conduct a visual inspection of the vertical hand brake supports for cracks or evidence of a stanchion that... Supports on FTTX Flatcars. SUMMARY: FRA is issuing Safety Advisory 2010-01 in order to provide guidance to... hand brake supports that have been modified to accommodate a 10-inch wide hand brake step. FRA's Office...

  4. 78 FR 30937 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2013-05-23

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2013-0015] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... meeting is open to the public. Section 7(a) of the Occupational Safety and Health Act of 1970 (OSH Act...

  5. 75 FR 10490 - Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-03-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management Advisory... Drug Safety and Risk Management Advisory Committee. General Function of the Committees: To provide...

  6. Lithuanian Nuclear Safety Advisory Committee - 1993-2003

    International Nuclear Information System (INIS)

    Medeliene, D.

    2003-01-01

    Brief overview of the Lithuanian Nuclear Safety Advisory Committee (LNSAC) activities is presented. LNSAC was established in May 1993, main task is to advise the Lithuanian government on industrial and regulatory matters of nuclear safety. One of the most of important tasks was to exert pressure on the Government so that it allocates sufficient funds from the national budget for setting up a national regulatory body. Statements of the members of LNSAC are presented. In the CD minutes of the meetings of the LNSAC in 1993-2003 and official documents regulating Committee activities are included

  7. 77 FR 12863 - Towing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2012-03-02

    ... DEPARTMENT OF HOMELAND SECURITY [Docket No. USCG-2012-0098] Towing Safety Advisory Committee... Airport, 9100 Gulf Freeway; Houston TX 77017. Hotel Web site: http://www.marriott.com/hotels/travel/houhh... the issues to be considered by the committee. Written comments must be identified by Docket No. USCG...

  8. 77 FR 62536 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2012-10-15

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... Section 7(a) of the Occupational Safety and Health Act of 1970 (OSH Act) (29 U.S.C. 651, 656) to advise...

  9. 78 FR 5243 - Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees

    Science.gov (United States)

    2013-01-24

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of meeting of Motor Carrier Safety...

  10. 75 FR 23793 - Houston/Galveston Navigation Safety Advisory Committee

    Science.gov (United States)

    2010-05-04

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2010-0032] Houston/Galveston... Houston/Galveston Navigation Safety Advisory Committee (``HOGANSAC'' or ``the Committee'') and its working groups will meet in Houston, Texas to discuss waterway improvements, aids to navigation, area projects...

  11. 78 FR 14314 - Towing Safety Advisory Committee; Meetings

    Science.gov (United States)

    2013-03-05

    ...: The Towing Safety Advisory Committee will meet in New York City, New York, March 21 and 22, 2013, to... the agenda in the SUPPLEMENTARY INFORMATION section below. The subcommittees will meet March 20, 2012, and work on seven assigned tasks listed in the referenced agenda. All meetings will be open to the...

  12. 76 FR 59142 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-09-23

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the...., [[Page 59143

  13. 76 FR 63929 - Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and...

    Science.gov (United States)

    2011-10-14

    ...] Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and... Administration (FDA). The meeting will be open to the public. Name of Committees: Drug Safety and Risk Management... Safe Use (ETASU) before its Drug Safety and Risk Management Advisory Committee (DSaRM). On December 1...

  14. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    International Nuclear Information System (INIS)

    Herborn, D.I.

    1991-10-01

    The requirements for Westinghouse Hanford independent review of the Preliminary Safety Analysis Report (PSAR) are contained in Section 1.0, Subsection 4.3 of WCH-CM-4-46. Specifically, this manual requires the following: (1) Formal functional reviews of the HWVP PSAR by the future operating organization (HWVP Operations), and the independent review organizations (HWVP and Environmental Safety Assurance, Environmental Assurance, and Quality Assurance); and (2) Review and approval of the HWVP PSAR by the Tank Waste Disposal (TWD) Subcouncil of the Safety and Environmental Advisory Council (SEAC), which provides independent advice to the Westinghouse Hanford President and executives on matters of safety and environmental protection. 7 refs

  15. Review of fuel safety criteria in France

    Energy Technology Data Exchange (ETDEWEB)

    Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier [Institut de Radioprotection et du Surete Nucleaire, Fontenay-aux-Roses (France)

    2018-01-15

    Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

  16. Review of fuel safety criteria in France

    International Nuclear Information System (INIS)

    Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier

    2018-01-01

    Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

  17. 75 FR 66797 - National Advisory Committee on Occupational Safety and Health (NACOSH), Charter Renewal

    Science.gov (United States)

    2010-10-29

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0012] National Advisory Committee on Occupational Safety and Health (NACOSH), Charter Renewal AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of renewal of the NACOSH charter...

  18. 76 FR 2916 - Houston/Galveston Navigation Safety Advisory Committee; Meetings

    Science.gov (United States)

    2011-01-18

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [USCG-2010-1116] Houston/Galveston Navigation Safety Advisory Committee; Meetings AGENCY: Coast Guard, DHS. ACTION: Notice of Meetings. SUMMARY: The Houston... will meet in Texas City, Texas and Houston, Texas to discuss waterway improvements, aids to navigation...

  19. 76 FR 40735 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-07-11

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... East, Adelphi, MD. The conference center telephone number is: 301 985-7300. Contact Person: Kalyani...

  20. 78 FR 2677 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-01-14

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... before February 7, 2013. Time allotted for each presentation may be limited. If the number of registrants...

  1. 76 FR 59143 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-09-23

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the..., Adelphi, MD. The conference center telephone number is 301-985-7300. Contact Person: Kalyani Bhatt, Center...

  2. 76 FR 10362 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2011-02-24

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal... Cybersecurity and Communications Reliability Public Safety and Homeland Security Bureau, Federal Communications...

  3. 77 FR 12054 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2012-02-28

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal..., Associate Bureau Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission, 445...

  4. 78 FR 16271 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-03-14

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... presentation may be limited. If the number of registrants requesting to speak is greater than can be reasonably...

  5. 76 FR 54234 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2011-08-31

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal.... Postal Service Mail to Jeffery Goldthorp, Associate Bureau Chief, Public Safety and Homeland Security...

  6. 75 FR 9899 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2010-03-04

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council; Notice of Public Meeting... Analysis Division, Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th...

  7. 76 FR 1460 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH); Committee Reestablishment

    Science.gov (United States)

    2011-01-10

    ... duties imposed by the Occupational Safety and Health (OSH) Act of 1970 (29 U.S.C. 655, 656). Authority to...(b) of the Occupational Safety and Health Act of 1970 (29 U.S.C. 655(b)(1), 656(b)), the Federal... DEPARTMENT OF LABOR Occupational Safety and Health Administration Maritime Advisory Committee for...

  8. 76 FR 37375 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2011-06-27

    ... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions... who wish to participate must register at least seven (7) days in advance of the meeting/conference... registration. Anyone requiring special accommodations should contact Mr. Joy at least seven (7) days in advance...

  9. International review on safety requirements for the prototype fast breeder reactor “Monju”

    International Nuclear Information System (INIS)

    2016-01-01

    In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report “Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju” taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)

  10. 76 FR 10898 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

    Science.gov (United States)

    2011-02-28

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory..., Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th Street, SW., Room..., Public Safety and Homeland Security Bureau. [FR Doc. 2011-4398 Filed 2-25-11; 8:45 am] BILLING CODE 6712...

  11. 75 FR 14609 - Commercial Fishing Industry Vessel Safety Advisory Committee; Vacancies

    Science.gov (United States)

    2010-03-26

    ... which Chapter 45 of Title 46, U.S.C. applies and persons representing the marine insurance industry... Industry Vessel Safety Advisory Committee; Vacancies AGENCY: Coast Guard, DHS. ACTION: Request for applications. SUMMARY: The Coast Guard seeks applications for membership on the Commercial Fishing Industry...

  12. 75 FR 30859 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2010-06-02

    ... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions... participate must register at least seven (7) days in advance of the meeting/conference call by contacting Mr.... Anyone requiring special accommodations should contact Mr. Joy at least seven (7) days in advance of the...

  13. 75 FR 56502 - National Advisory Committee on Meat and Poultry Inspection

    Science.gov (United States)

    2010-09-16

    ... Advisory Committee on Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... and Poultry Inspection (NACMPI) will hold a public meeting on September 29-30, 2010, to review and... disks or CD-ROMs: Send to National Advisory Committee on Meat and Poultry Inspection, USDA, FSIS, 14th...

  14. Report of the meeting of the INES advisory committee, 16-17 October 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The INES advisory committee discussed at its meeting the following issues: report on results from questionnaires, review of events, proposed simplification of the user's manual, guidance on relationship between initiators and safety functions, computerized rating procedure, future work of the advisory committee

  15. Report of the meeting of the INES advisory committee, 16-17 October 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The INES advisory committee discussed at its meeting the following issues: report on results from questionnaires, review of events, proposed simplification of the user`s manual, guidance on relationship between initiators and safety functions, computerized rating procedure, future work of the advisory committee.

  16. A Global Perspective on Vaccine Safety and Public Health: The Global Advisory Committee on Vaccine Safety

    Science.gov (United States)

    Folb, Peter I.; Bernatowska, Ewa; Chen, Robert; Clemens, John; Dodoo, Alex N. O.; Ellenberg, Susan S.; Farrington, C. Patrick; John, T. Jacob; Lambert, Paul-Henri; MacDonald, Noni E.; Miller, Elizabeth; Salisbury, David; Schmitt, Heinz-J.; Siegrist, Claire-Anne; Wimalaratne, Omala

    2004-01-01

    Established in 1999, the Global Advisory Committee on Vaccine Safety advises the World Health Organization (WHO) on vaccine-related safety issues and enables WHO to respond promptly, efficiently, and with scientific rigor to issues of vaccine safety with potential global importance. The committee also assesses the implications of vaccine safety for practice worldwide and for WHO policies. We describe the principles on which the committee was established, its modus operandi, and the scope of the work undertaken, both present and future. We highlight its recent recommendations on major issues, including the purported link between the measles–mumps–rubella vaccine and autism and the safety of the mumps, influenza, yellow fever, BCG, and smallpox vaccines as well as that of thiomersal-containing vaccines. PMID:15514229

  17. 75 FR 36427 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-06-25

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug Administration, HHS. ACTION: Notice. This notice...

  18. IAEA advisory group meeting on nuclear data for radiation damage assessment and related safety aspects, Vienna, 12-16 October 1981

    International Nuclear Information System (INIS)

    Kocherov, N.

    1982-01-01

    This Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was convened by the IAEA Nuclear Data Section, at IAEA Headquarters in Vienna, Austria, from 12-16 October 1981. The meeting was attended by 34 participants from 15 countries and 2 international organizations. The main objective of the meeting was to review the requirements for and the status of nuclear data needed for radiation damage estimates in reactor structural materials and related reactor safety aspects, and to develop recommendations to the Nuclear Data Section of the IAEA for its future activities in this field. (author)

  19. 75 FR 4904 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2010-01-29

    ... amend regulations protecting persons who work on, under, or between rolling equipment; and persons...-7257] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad... Committee (RSAC) Working Group Activities. SUMMARY: The FRA is updating its announcement of RSAC's Working...

  20. 75 FR 51525 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2010-08-20

    .... The Working Group continues to work on after arrival orders, and at the September 25-26, 2008, meeting... protecting persons who work on, under, or between rolling equipment and persons applying, removing or.... 63] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad...

  1. International review on safety requirements for the prototype fast breeder reactor “Monju” (Translated document)

    International Nuclear Information System (INIS)

    2016-02-01

    In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report “Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju” taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)

  2. A comparative review of patient safety initiatives for national health information technology

    DEFF Research Database (Denmark)

    Magrabi, Farah; Aarts, Jos; Nøhr, Christian

    2013-01-01

    OBJECTIVE: To collect and critically review patient safety initiatives for health information technology (HIT). METHOD: Publicly promulgated set of advisories, recommendations, guidelines, or standards potentially addressing safe system design, build, implementation or use were identified...... by searching the websites of regional and national agencies and programmes in a non-exhaustive set of exemplar countries including England, Denmark, the Netherlands, the USA, Canada and Australia. Initiatives were categorised by type and software systems covered. RESULTS: We found 27 patient safety initiatives...... were aimed at certification in the USA, Canada and Australia. Safety is addressed alongside interoperability in the Australian certification programme but it is not explicitly addressed in the US and Canadian programmes, though conformance with specific functionality, interoperability, security...

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

    International Nuclear Information System (INIS)

    1982-02-01

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

  4. Development of Operational Safety Monitoring System and Emergency Preparedness Advisory System for CANDU Reactors (I)

    International Nuclear Information System (INIS)

    Kim, Ma Woong; Shin, Hyeong Ki; Lee, Sang Kyu; Kim, Hyun Koon; Yoo, Kun Joong; Ryu, Yong Ho; Son, Han Seong; Song, Deok Yong

    2007-01-01

    As increase of operating nuclear power plants, an accident monitoring system is essential to ensure the operational safety of nuclear power plant. Thus, KINS has developed the Computerized Advisory System for a Radiological Emergency (CARE) system to monitor the operating status of nuclear power plant continuously. However, during the accidents or/and incidents some parameters could not be provided from the process computer of nuclear power plant to the CARE system due to limitation of To enhance the CARE system more effective for CANDU reactors, there is a need to provide complement the feature of the CARE in such a way to providing the operating parameters using to using safety analysis tool such as CANDU Integrated Safety Analysis System (CISAS) for CANDU reactors. In this study, to enhance the safety monitoring measurement two computerized systems such as a CANDU Operational Safety Monitoring System (COSMOS) and prototype of CANDU Emergency Preparedness Advisory System (CEPAS) are developed. This study introduces the two integrated safety monitoring system using the R and D products of the national mid- and long-term R and D such as CISAS and ISSAC code

  5. 75 FR 67805 - The Future of Aviation Advisory Committee (FAAC) Subcommittee on Aviation Safety; Notice of Meeting

    Science.gov (United States)

    2010-11-03

    ...-2010-0074] The Future of Aviation Advisory Committee (FAAC) Subcommittee on Aviation Safety; Notice of..., announces a meeting of the FAAC Subcommittee on Aviation Safety, which will be held at the offices [[Page... needs, challenges, and opportunities of the global economy. The Subcommittee on Aviation Safety will...

  6. 75 FR 74050 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2010-11-30

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal...) Communications Security, Reliability, and Interoperability Council (CSRIC) will hold its fourth meeting on...

  7. 75 FR 56533 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2010-09-16

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal...) Communications Security, Reliability, and Interoperability Council (CSRIC) will hold its third meeting on October...

  8. 77 FR 70777 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2012-11-27

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal... Security, Reliability, and Interoperability Council (CSRIC III) scheduled for December 5, 2012, at Federal...

  9. Centers for manufacturing technology: Industrial Advisory Committee Review

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    An advisory committee, composed of senior managers form industrial- sector companies and major manufacturing trade associations and representatives from appropriate educational institutions, meets semi-annually to review and advise the Oak Ridge Centers for Manufacturing Technology (ORCMT) on its economic security program. Individual papers have been indexed separately for the database.

  10. Aerospace Safety Advisory Panel

    Science.gov (United States)

    1999-01-01

    This report covers the activities of the Aerospace Safety Advisory Panel (ASAP) for calendar year 1998-a year of sharp contrasts and significant successes at NASA. The year opened with the announcement of large workforce cutbacks. The slip in the schedule for launching the International Space Station (ISS) created a five-month hiatus in Space Shuttle launches. This slack period ended with the successful and highly publicized launch of the STS-95 mission. As the year closed, ISS assembly began with the successful orbiting and joining of the Functional Cargo Block (FGB), Zarya, from Russia and the Unity Node from the United States. Throughout the year, the Panel maintained its scrutiny of NASA's safety processes. Of particular interest were the potential effects on safety of workforce reductions and the continued transition of functions to the Space Flight Operations Contractor. Attention was also given to the risk management plans of the Aero-Space Technology programs, including the X-33, X-34, and X-38. Overall, the Panel concluded that safety is well served for the present. The picture is not as clear for the future. Cutbacks have limited the depth of talent available. In many cases, technical specialties are 'one deep.' The extended hiring freeze has resulted in an older workforce that will inevitably suffer significant departures from retirements in the near future. The resulting 'brain drain' could represent a future safety risk unless appropriate succession planning is started expeditiously. This and other topics are covered in the section addressing workforce. The major NASA programs are also limited in their ability to plan property for the future. This is of particular concern for the Space Shuttle and ISS because these programs are scheduled to operate well into the next century. In the case of the Space Shuttle, beneficial and mandatory safety and operational upgrades are being delayed because of a lack of sufficient present funding. Likewise, the ISS has

  11. Management of operational safety in nuclear power plants. INSAG-13. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    1999-01-01

    The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. Engineering issues have received close attention from the nuclear community over many years. However, it is only in the last decade or so that organizational and cultural issues have been identified as vital to achieving safe operation. INSAG's publication No. 4 has been widely recognized as a milestone in advancing thinking about safety culture in the nuclear community and more widely. The present report deals with the framework for safety management that is necessary in organizations in order to promote safety culture. It deals with the general principles underlying the management of operational safety in a systematic way and provides guidance on good practices. It also draws on the results of audits and reviews to highlight how shortfalls in safety management have led to incidents at nuclear power plants. In addition, several specific issues are raised which are particularly topical in view of organizational changes that are taking place in the nuclear industry in various countries. Advice is given on how safety can be managed during organizational change, how safety

  12. Management of Operational Safety in Nuclear Power Plants. INSAG-13. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. Engineering issues have received close attention from the nuclear community over many years. However, it is only in the last decade or so that organizational and cultural issues have been identified as vital to achieving safe operation. INSAG's publication No. 4 has been widely recognized as a milestone in advancing thinking about safety culture in the nuclear community and more widely. The present report deals with the framework for safety management that is necessary in organizations in order to promote safety culture. It deals with the general principles underlying the management of operational safety in a systematic way and provides guidance on good practices. It also draws on the results of audits and reviews to highlight how shortfalls in safety management have led to incidents at nuclear power plants. In addition, several specific issues are raised which are particularly topical in view of organizational changes that are taking place in the nuclear industry in various countries. Advice is given on how safety can be managed during organizational change, how

  13. 75 FR 21338 - Subcommittee for Dose Reconstruction Reviews (SDRR), Advisory Board on Radiation and Worker...

    Science.gov (United States)

    2010-04-23

    ... period. Background: The Advisory Board was established under the Energy Employees Occupational Illness... employees at any Department of Energy facility who were exposed to radiation but for whom it is not feasible...: selection of individual radiation dose reconstruction cases to be considered for review by the Advisory...

  14. Advisory material for the IAEA regulations for the safe transport of radioactive material. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    Since the first edition in 1961, the Regulations for the Safe Transport of Radioactive Material of the IAEA (IAEA Regulations) have served as the basis of safety for the transport of radioactive material worldwide. In the discussions leading to the first edition of the IAEA Regulations, it was realized that there was need for a publication to supplement the Regulations which could give information of individual provisions as to their purpose, their scientific background and how to apply them in practice. In response, the Agency published Safety Series No. 7, entitled, in its first edition in 1961, 'Notes on Certain Aspects of the Regulations'. An additional source of information on the Regulations, providing advice on 'how' the user should comply with them which could be augmented from time to time in the light of latest experience, was provided by the Agency, initially in relation to the 1973 edition of the Regulations. This was entitled 'Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material' and designated Safety Series No. 37. This document is the result of combining the two Safety Series in a single publication. Thus the primary purpose of this publication is to provide guidance to users on proven and acceptable ways of complying with the Regulations. This Advisory Material is not a stand-alone text and it only has significance when used as a companion to the IAEA Safety Standards Series No. ST-1, Regulations for the Safe Transport of Radioactive Material (1996 edition)

  15. Maximum tolerable radiation doses recommended by the Israel Advisory Committee on nuclear safety

    International Nuclear Information System (INIS)

    Tadmor, J.; Litai, D.; Lubin, E.

    1978-01-01

    Maximum tolerable doses have been recommended by the Israel Advisory Committee on Nuclear Safety. The recommendations which are based on a comparison with risks tolerated in other human activities, are for doses to radiation workers, for individual members of the population at the fence of a nuclear installation, and for the population at large, for both normal operating and accident conditions. Tolerable whole-body doses and doses to different critical organs are listed

  16. Aerospace Safety Advisory Panel Annual Report for 1999

    Science.gov (United States)

    Blomberg, Richard D.

    2000-01-01

    This report covers the activities of the Aerospace Safety Advisory Panel (ASAP) for the calendar year 1999.This was a year of notable achievements and significant frustrations. Both the Space Shuttle and International Space Station (ISS) programs were delayed.The Space Shuttle prudently postponed launches after the occurrence of a wiring short during ascent of the STS-93 mission. The ISS construction schedule slipped as a result of the Space Shuttle delays and problems the Russians experienced in readying the Service Module and its launch vehicle. Each of these setbacks was dealt with in a constructive way. The STS-93 short circuit led to detailed wiring inspections and repairs on all four orbiters as well as analysis of other key subsystems for similar types of hidden damage. The ISS launch delays afforded time for further testing, training, development, and contingency planning. The safety consciousness of the NASA and contractor workforces, from hands-on labor to top management, continues high. Nevertheless, workforce issues remain among the most serious safety concerns of the Panel. Cutbacks and reorganizations over the past several years have resulted in problems related to workforce size, critical skills, and the extent of on-the-job experience. These problems have the potential to impact safety as the Space Shuttle launch rate increases to meet the demands of the ISS and its other customers. As with last year's report, these work- force-related issues were considered of sufficient import to place them first in the material that follows. Some of the same issues of concern for the Space Shuttle and ISS arose in a review of the launch vehicle for the Terra mission that the Panel was asked by NASA to undertake. Other areas the Panel was requested to assess included the readiness of the Inertial Upper Stage for the deployment of the Chandra X-ray Observatory and the possible safety impact of electromagnetic effects on the Space Shuttle. The findings and

  17. Safety codes and guides for nuclear power plants

    International Nuclear Information System (INIS)

    Iansiti, E.

    1976-01-01

    The Codes of Practice and Safety Guides that are being developed by the International Atomic Energy Agency are divided in five topical areas: Governmental Organization, Siting, Design, Operation and Quality Assurance. In each area, a scientific secretary is responsible for developing the documents and five Technical Review Committees composed of 10 to 12 experts from various Members Countries revise the drafts at different stages. A Senior Advisory Group supervises the entire programme and revises the document. A scientific co-ordinator is responsible for the co-ordination within the programme with other sections of the IAEA, and with other international organizations. In preparing a document, information on the practice adopted by Member States is collected, a group of experts is convened for preparing a preliminary draft on the basis of this material and the draft is then reviewed by the appropriate Technical Review Committee. The document is translated into various languages, reviewed by the Senior Advisory Group and sent to Member States for comments. After the comments of Member States have been received, the Technical Review Committee and then the Senior Advisory Group are convened again for the final revision of the document. Some 25 drafts, are in different stages of development. The preparation of a document in its final form takes about two years. The programme started in 1975 and to date most of the safety codes and a few safety guides have been sent to Member States for comments. These documents will have gone through the entire development procedure by early 1977. The Senior Advisory Groups and the Technical Review Committees meet on the average four times a year for a week at a time. Until now these meetings have been mainly concerned with the development of new documents or with that part of the procedure which precedes the transmission of the draft to Member States for comments. The next series of meetings will deal with the revisions needed to

  18. Key issues for passive safety

    International Nuclear Information System (INIS)

    Hayns, M.R.

    1996-01-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ''review paper'' as such and only record the highlights. (author)

  19. Key issues for passive safety

    Energy Technology Data Exchange (ETDEWEB)

    Hayns, M R [AEA Technology, Harwell, Didcot (United Kingdom). European Institutions; Hicken, E F [Forschungszentrum Juelich GmbH (Germany)

    1996-12-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ``review paper`` as such and only record the highlights. (author).

  20. Development of Safety Review Guide for the Periodic Safety Review of Reactor Vessel Internals

    International Nuclear Information System (INIS)

    Park, Jeongsoon; Ko, Hanok; Kim, Seonjae; Jhung, Myungjo

    2013-01-01

    Aging management of the reactor vessel internals (RVIs) is one of the important issues for long-term operation of nuclear power plants (NPPs). Safety review on the assessment and management of the RVI aging is conducted through the process of a periodic safety review (PSR). The regulatory body should check that reactor facilities sustain safety functions in light of degradation due to aging and that the operator of a nuclear power reactor establishes and implements management program to deal with degradation due to aging in order to guarantee the safety functions and the safety margin as a result of PSR. KINS(Korea Institute of Nuclear Safety) has utilized safety review guides (SRG) which provide guidance to KINS staffs in performing safety reviews in order to assure the quality and uniformity of staff safety reviews. The KINS SRGs for the continued operation of pressurized water reactors (PWRs) published in 2006 contain areas of review regarding aging management of RVIs in chapter 2 (III.2.15, Appendix 2.0.1). However unlike the SRGs for the continued operation, KINS has not officially published the SRGs for the PSR of PWRs, but published them as a form of the research report. In addition to that, the report provides almost same review procedures for aging assessment and management of RVIs with the ones provided in the SRGs for the continued operation, it cannot provide review guidance specific to PSRs. Therefore, a PSR safety review guide should be developed for RVIs in PWRs. In this study, a draft PSR safety review guide for reactor vessel internals in PWRs is developed and provided. In this paper, a draft PSR safety review guide for reactor vessel internals (PSR SRG-RVIs) in PWRs is introduced and main contents of the draft are provided. However, since the PSR safety review guides for areas other than RVIs in the pressurized water reactors (PWRs) are expected to be developed in the near future, the draft PSR SRG-RVIs should be revisited to be compatible with

  1. SCART guidelines. Reference report for IAEA Safety Culture Assessment Review Team (SCART)

    International Nuclear Information System (INIS)

    2008-01-01

    The IAEA Director General stressed the role of safety culture in his concluding remarks at the Meeting of the Contracting Parties to the Convention on Nuclear Safety in 2002: 'As we have learned in other areas, it is not enough simply to have a structure; it is not enough to say that we have the necessary laws and the appropriate regulatory bodies. All these are important, but equally important is that we have in place a safety culture that gives effect to the structure that we have developed. To me, effectiveness and transparency are keys. So, it is an issue which I am pleased to see, you are giving the attention it deserves and we will continue to work with you in clarifying, developing and applying safety culture through our programmes and through our technical cooperation activities.' The concept of safety culture was initially developed by the International Nuclear Safety Advisory Group (INSAG) after the Chernobyl accident in 1986. Since then the IAEA's perspective of safety culture has expanded with time as its recognition of the complexities of the concept developed. Safety culture is considered to be specific organizational culture in all types of organizations with activities that give rise to radiation risks. The aim is to make safety culture strong and sustainable, so that safety becomes a primary focus for all activities in such organizations, even for those, which might not look safety-related at first. SCART (Safety Culture Assessment Review Team) is a safety review service, which reflects the expressed interest of Members States for methods and tools for safety culture assessment. It is a replacement for the earlier service ASCOT (Assessment of Safety Culture in Organizations Team). The IAEA Safety Fundamentals, Requirements and Guides (Safety Standards) are the basis for the SCART Safety Review Service. The reports of INSAG, identifying important current nuclear safety issues, serve also as references during a SCART mission. SCART missions are based

  2. Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group

    International Nuclear Information System (INIS)

    2002-01-01

    This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

  3. 16 CFR 1018.43 - Comprehensive review.

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Comprehensive review. 1018.43 Section 1018.43 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL ADVISORY COMMITTEE MANAGEMENT Records, Annual Reports and Audits § 1018.43 Comprehensive review. A comprehensive review of all...

  4. IAEA safety glossary. Terminology used in nuclear, radiation, radioactive waste and transport safety. Version 1.0. Working material

    International Nuclear Information System (INIS)

    2000-04-01

    The IAEA safety standards for nuclear installations, radiation protection, radioactive waste management and the transport of radioactive materials have been historically developed in four separate programmes, each of them developing its own terminology. The purpose was to explain the meaning of technical terms that might be unfamiliar to a reader; to explain any special meanings assigned to common words or terms and to define precisely how terms are used in particular publications to avoid ambiguity concerning some important aspects of their meaning. It is intended primarily to provide guidance to the drafters and reviewers of Agency safety related publications, including IAEA Technical officers, consultants and members of Technical Committees, Advisory Groups and safety standards advisory bodies. It is also likely to be a useful source of information for other Agency staff, notably editors and translators, and for external users of IAEA safety related publications

  5. 76 FR 51364 - Notification of a Public Teleconference of the Science Advisory Board Panel for the Review of the...

    Science.gov (United States)

    2011-08-18

    ... Science Advisory Board Panel for the Review of the Great Lakes Restoration Initiative Action Plan AGENCY... Agency) Science Advisory Board (SAB) Staff Office announces a public teleconference of the SAB Panel to... information concerning the EPA Science Advisory Board can be found at the EPA SAB Web site at http://www.epa...

  6. Regulatory review of NPP Krsko Periodic Safety Review

    International Nuclear Information System (INIS)

    Lovincic, D.; Muehleisen, A.; Persic, A.

    2004-01-01

    At the request of the Slovenian Nuclear Safety Administration (SNSA), Krsko NPP prepared a Periodic Safety Review (PSR) program in January 2001. This is the first PSR of NPP Krsko, the only nuclear power plant in Slovenia. The program was reviewed by the IAEA mission in May 2001 and approved by SNSA in July 2001. The program is made in accordance with the IAEA Safety Guide 'Periodic Safety Review of Operational Nuclear Power Plants' No. 50-SG-012 and with European practice. It contains a systematic review of operation of the NPP Krsko, including the review of the changes as a result of the modernization of the facility. The main tasks of PSR are review of plant status for each safety factor, development of aging and life cycle management program, review of seismic design and PSHA analysis and update of regulatory compliance program. The prioritization process of findings and action plan are also important tasks of PSR. The basic safety factors of the PSR review are: Operational Experience, Safety Assessment and Analyses, Equipment Qualification and Ageing Management, Safety Culture, Emergency Planing, Environmental Impact and Radioactive Waste, Compliance with license requirements and Prioritization. It had been agreed that SNSA will have reviewed all PSR reports generated during the PSR process. At the end of 2003 the PSR Summary Report with selected recommendations for action plan was completed and delivered to SNSA for review. The paper presents regulatory review of NPP Krsko PSR with emphasis on the evaluation of the PSR issues ranking process. (author)

  7. Assessment of IAEA safety series no. 75-INSAG-3 - ''basic safety principles for nuclear power plants''

    International Nuclear Information System (INIS)

    1989-01-01

    The International Atomic Energy Agency Safety Series No. 75-INSAG--3, 'Basic Safety Principles for Nuclear Power Plants' is reviewed in the light of the Advisory Committee on Nuclear Safety reports ACNS--2, 'Safety Objectives for Nuclear Activities in Canada', and ACNS--4, 'Recommended General Safety Requirements for Nuclear Power Plants'. The INSAG safety objectives are consistent with the safety objectives stated in ACNS--2 but are less general, applying only to nuclear power plants. The INSAG safety principles are, in general, consistent with the requirements stated in ACNS--4 but put more emphasis on 'safety culture'. They give little attention to reactor plant effluents, waste management, or decommissioning. (fig., 5 refs.)

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  9. Nuclear Safety Review 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

  10. Nuclear Safety Review 2013

    International Nuclear Information System (INIS)

    2013-07-01

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis

  11. Current safety issues related to research reactor operation

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.

    2000-01-01

    The Agency has included activities on research reactor safety in its Programme and Budget (P and B) since its inception in 1957. Since then, these activities have traditionally been oriented to fulfil the Agency's functions and obligations. At the end of the decade of the eighties, the Agency's Research Reactor Safety Programme (RRSP) consisted of a limited number of tasks related to the preparation of safety related publications and the conduct of safety missions to research reactor facilities. It was at the beginning of the nineties when the RRSP was upgraded and expanded as a subprogramme of the Agency's P and B. This subprogramme continued including activities related to the above subjects and started addressing an increasing number of issues related to the current situation of research reactors (in operation and shut down) around the world such as reactor ageing, modifications and decommissioning. The present paper discusses some of the above issues as recognised by various external review or advisory groups (e.g., Peer Review Groups under the Agency's Performance Programme Appraisal System (PPAS) or the standing International Nuclear Safety Advisory Group (INSAG)) and the impact of their recommendations on the preparation and implementation of the part of the Agency's P and B relating to the above subject. (author)

  12. IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

    International Nuclear Information System (INIS)

    2014-01-01

    The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

  13. Periodic safety review of the HTR-10 safety analysis

    International Nuclear Information System (INIS)

    Chen Fubing; Zheng Yanhua; Shi Lei; Li Fu

    2015-01-01

    Designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first modular High Temperature Gas-cooled Reactor (HTGR) in China. According to the nuclear safety regulations of China, the periodic safety review (PSR) of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration (NNSA) of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper, the main contents in the review of safety analysis are summarized; meanwhile, the internal evaluation on the review results is presented by INET. (authors)

  14. OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

    International Nuclear Information System (INIS)

    2005-01-01

    when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

  15. OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

    International Nuclear Information System (INIS)

    2007-01-01

    when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

  16. OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

    International Nuclear Information System (INIS)

    2008-01-01

    when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

  17. Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group [Russian Edition

    International Nuclear Information System (INIS)

    2015-01-01

    This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

  18. IAEA safety glossary. Terminology used in nuclear safety and radiation protection, multilingual 2007 edition, including the IAEA safety fundamentals [no. SF-1

    International Nuclear Information System (INIS)

    2008-10-01

    The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage.The publication is multilingual and covers the six official IAEA languages,, Arabic, Chinese, English, French, Russian and Spanish. It has been in use since April 2000. The 2007 Edition is a revised and updated version. The primary purpose of the publication is to harmonize terminology and usage in the IAEA Safety Standards. It is a source of information for users of the IAEA Safety Standards and other safety related IAEA publications and provides guidance for the drafters and reviewers of publications, including IAEA technical officers and consultants, and members of technical committees, advisory groups, working groups and bodies for the endorsement of safety standards

  19. KHNP special safety review

    International Nuclear Information System (INIS)

    Lee, Tae-Ho; Lee, Bang-Jin; Lee, Soung-Hee; Park, Goon-Cherl

    2009-01-01

    Commemorating the 30 year anniversary of commercial nuclear power plant operation in KOREA, Korea Hydro and Nuclear Power Co., Ltd. (KHNP) has conducted a Special Safety Review (SSR) of its 20 operating units to understand their safety performance and to identify any areas that need improvement. The SSR reviewed all 20 operating units for 2 weeks per site. Areas that were reviewed are Safety Margins, Plant Performance, Employee Safety, Employee Performance and Performance Improvement Process. Each review team consisted of international and domestic members. The international reviewers were from IAEA, WANO and INPO. The domestic reviewers consisted of professors, Engineering Company, Research Institute and KHNP experts. The review confirmed safe and reliable operations of the 20 nuclear units. The common understanding resulted from the SSR is as follows. Firstly, KHNP corporate and its plants confirmed and shared mutual understanding on recurring areas for improvements, especially in the areas of Organizational Effectiveness, Industrial Safety, Human Performance, Configuration Management, Operations, Equipment Performance and Material Condition. Secondly, KHNP understood that plant and department level performances are directly related to the leadership and competency of the management team including supervisors. Thirdly, the strengths of individual stations that consistently have produced good results need to be shared with the other KHNP stations. Finally, KHNP learned that strong corporate leadership and support are needed to resolve most of the areas for improvement since they are common to all KHNP stations. (author)

  20. 76 FR 7199 - Science Advisory Board Staff Office; Notification of a Public Meeting of the Science Advisory...

    Science.gov (United States)

    2011-02-09

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9264-5] Science Advisory Board Staff Office; Notification of a Public Meeting of the Science Advisory Board Panel for the Review of EPA's Hydraulic Fracturing...-2098 or via e-mail at [email protected] . General information concerning the EPA Science Advisory...

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

    International Nuclear Information System (INIS)

    Nys, V.

    2003-01-01

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

  2. 76 FR 40355 - Science Advisory Board Staff Office; Notification of a Public Meeting of the Science Advisory...

    Science.gov (United States)

    2011-07-08

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9431-7] Science Advisory Board Staff Office; Notification of a Public Meeting of the Science Advisory Board Panel for the Review of Great Lakes Restoration... information concerning the EPA Science Advisory Board can be found at the EPA SAB Web site at http://www.epa...

  3. Safety review advisor

    International Nuclear Information System (INIS)

    Boshers, J.A.; Uhrig, R.E.; Alguindigue, I.A.; Burnett, C.G.

    1991-01-01

    The University of Tennessee's Nuclear Engineering department, in cooperation with the Tennessee Valley Authority (TVA), is evaluating the feasibility of utilizing an expert system to aid in 10CFR50.59 evaluations. This paper discusses the history of 10CFR50.59 reviews, and details the development approach used in the construction of a prototype Safety Review Advisor (SRA). The goals for this expert system prototype are to aid the engineer in the evaluation process by directing his attention to the appropriate critical issues, increase the efficiency, consistency, and thoroughness of the evaluation process, and provide a foundation of appropriate Safety Analysis Report (SAR) references for the reviewer

  4. 78 FR 58536 - Notification of a Public Meeting of the Science Advisory Board Panel for the Review of the EPA...

    Science.gov (United States)

    2013-09-24

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL--9901-26-OA] Notification of a Public Meeting of the Science Advisory Board Panel for the Review of the EPA Water Body Connectivity Report AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces...

  5. US nuclear safety review and experience

    International Nuclear Information System (INIS)

    Gilinsky, V.

    1977-01-01

    The nuclear safety review of commercial nuclear power reactors has changed over the years from the relatively simple review of Dresden 1 in 1955 to the highly complex and sophisticated regulatory process which characterizes today's reviews. Four factors have influenced this evolution: (1) maturing of the technology and industry; (2) development of the regulatory process and associated staff; (3) feedback of operating experience; and (4) public awareness and participation. The NRC's safety review responsibilities start before an application is tendered and end when the plant is decommissioned. The safety review for reactor licensing is a comprehensive, two-phase process designed to assure that all the established conservative acceptance criteria are satisfied. Operational safety is assured through a strong inspection and enforcement program which includes shutting down operating facilities when necessary to protect the health and safety of the public. The safety of operating reactors is further insured through close regulation of license changes and selective backfitting of new regulatory requirements. An effective NRC standards development program has been implemented and coordinates closely with the national standards program. A confirmatory safety research program has been developed. Both of these efforts are invaluable to the nuclear safety review because they provide the staff with key tools needed to carry out its regulatory responsibilities. Both have been given increased emphasis since the formation of the NRC in 1975. The safety review process will continue to evolve, but changes will be slower and more deliberate. It will be influenced by standardization, early site reviews and development of advanced reactor concepts. New legislation may make possible changes which will simplify and shorten the regulatory process. Certainly the experience provided by the increasing number and types of operating plants will have a very strong impact on future trends in the

  6. 77 FR 47067 - Notification of Two Public Quality Review Teleconferences of the Chartered Science Advisory Board

    Science.gov (United States)

    2012-08-07

    ... Assessment in Environmental Decision- Making'' (EPA-SAB-08-002). Background information about this advisory... ecological assessment action plan and (2) an SAB draft review report on EPA's accounting framework for... ``SAB Review (7-26-12 Draft) of EPA's Accounting Framework for Biogenic CO 2 Emissions from Stationary...

  7. NPP Krsko Periodic Safety Review action plan

    International Nuclear Information System (INIS)

    Bilic Zabric, T.

    2006-01-01

    In the current, internationally accepted, safety philosophy Periodic Safety Reviews (PSRs) are comprehensive reviews aimed at the verification that an operating NPP remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain an acceptable level of safety. These reviews are complementary to the routine and special safety reviews. They are long time-scale reviews intended to deal with the cumulative effects of plant ageing, modifications, operating experience and technical developments, which are not so easily comprehended over the shorter time-scale routine of safety reviews. The review was completed in 2005 and the next period will see the implementation of the action plan including some plant upgrades. The action plan lists issues that should be implemented at NPP Krsko together with associated milestones. The milestones were assumed based on best estimate resource availability and their ends can be potentially floated. In some cases, multiple corrective measures may be postulated to provide resolution for a given safety issue. The Slovenian Nuclear Safety Administration by decree approved the first periodic safety review and the implementation plan of activities arising from it. The entire implementation plan must be carried out by 15 October 2010. Report on the second periodic safety review must be submitted by the NEK not later than 15 December 2013. (author)

  8. Safety review advisor

    International Nuclear Information System (INIS)

    Boshers, J.A.; Alguindigue, I.E.; Uhrig, R.E.

    1989-01-01

    The University of Tennessee's Nuclear Engineering Department, in cooperation with the Tennessee Valley Authority (TVA), is evaluating the feasibility of utilizing an expert system to aid in 10CFR50.59 evaluations. This paper discusses the history of 10CFR50.59 reviews, and details the development approach used in the construction of a prototype Safety Review Advisor (SRA). The goals for this expert system prototype are to (1) aid the engineer in the evaluation process by directing his attention to the appropriate critical issues, (2) increase the efficiency, consistency, and thoroughness of the evaluation process, and (3) provide a foundation of appropriate Safety Analysis Report (SAR) references for the reviewer. 6 refs., 2 figs

  9. ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

    International Nuclear Information System (INIS)

    2000-01-01

    The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

  10. Reviewing industrial safety in nuclear power plants

    International Nuclear Information System (INIS)

    1990-02-01

    This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

  11. 75 FR 56548 - Joint Meeting of the Peripheral and Central Nervous System Drugs Advisory Committee and the Drug...

    Science.gov (United States)

    2010-09-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Peripheral and Central Nervous System Drugs Advisory Committee and the Drug Safety... and Central Nervous System Drugs Advisory Committee and the Drug Safety and Risk Management Advisory...

  12. Assessment of phthalates/phthalate alternatives in children's toys and childcare articles: Review of the report including conclusions and recommendation of the Chronic Hazard Advisory Panel of the Consumer Product Safety Commission.

    Science.gov (United States)

    Lioy, Paul J; Hauser, Russ; Gennings, Chris; Koch, Holger M; Mirkes, Philip E; Schwetz, Bernard A; Kortenkamp, Andreas

    2015-01-01

    The Consumer Product Safety Commission (CPSC) convened a Chronic Hazard Advisory Panel (CHAP) on Phthalates found in children's toys, and childcare products, and in products used by women of childbearing age. The CHAP conducted a risk assessment on phthalates and phthalate substitutes, and made recommendations to either ban, impose an interim ban, or allow the continued use of phthalates and phthalate substitutes in the above products. After a review of the literature, the evaluation included toxic end points of primary concern, biomonitoring results, extant exposure reconstruction, and epidemiological results. The health end points chosen were associated with the rat phthalate syndrome, which is characterized by malformations of the epididymis, vas deferens, seminal vesicles, prostate, external genitalia (hypospadias), and by cryptorchidism (undescended testes), retention of nipples/areolae, and demasculinization (~incomplete masculinization) of the perineum, resulting in reduced anogenital distance. Risk assessment demonstrated that some phthalates should be permanently banned, removed from the banned list, or remain interim banned. Biomonitoring and toxicology data provided the strongest basis for a mixture risk assessment. In contrast, external exposure data were the weakest and need to be upgraded for epidemiological studies and risk assessments. Such studies would focus on routes and sources. The review presents recommendations and uncertainties.

  13. A global nuclear safety culture

    International Nuclear Information System (INIS)

    1996-01-01

    The article discusses three components characterizing the infrastructure of a global nuclear safety culture, each one satisfying special needs. These are: (a) legally binding international agreements, which were drawn up at an accelerated pace in the 1980s following the Chernobyl accident, with its transboundary implications; (b) non-binding common safety standards, which were developed rapidly during the 1960s and 1970s, a period which saw a desire for harmonized safety approaches as nuclear power and the use of radiation and radioactive materials expanded globally; and (c) review and advisory services, which are provided by international experts, the need for which was underscored by the accident at Chernobyl. 5 refs, 1 fig

  14. NPP Krsko periodic safety review. Safety assessment and analyses

    International Nuclear Information System (INIS)

    Basic, I.; Spiler, J.; Thaulez, F.

    2002-01-01

    Definition of a PSR (Periodic Safety Review) project is a comprehensive safety review of a plant after ten years of operation. The objective is a verification by means of a comprehensive review using current methods that the plant remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. The overall goals of the NEK PSR Program are defined in compliance with the basic role of a PSR and the current practice typical for most of the countries in EU. This practice is described in the related guides and good practice documents issued by international organizations. The overall goals of the NEK PSR are formulated as follows: to demonstrate that the plant is as safe as originally intended; to evaluate the actual plant status with respect to aging and wear-out identifying any structures, systems or components that could limit the life of the plant in the foreseeable future, and to identify appropriate corrective actions, where needed; to compare current level of safety in the light of modern standards and knowledge, and to identify where improvements would be beneficial for minimizing deviations at justifiable costs. The Krsko PSR will address the following safety factors: Operational Experience, Safety Assessment, EQ and Aging Management, Safety Culture, Emergency Planning, Environmental Impact and Radioactive Waste.(author)

  15. 75 FR 80515 - National Boating Safety Advisory Council

    Science.gov (United States)

    2010-12-22

    ... Advisory Council (NBSAC) and its subcommittees will meet on January 14-16, 2011, in Orlando, Florida. NBSAC... Suites Orlando--Downtown, 191 East Pine Street, Orlando, FL 32801. Please send written material, comments...

  16. Recommendations relating to safety-critical real-time software in nuclear power plants

    International Nuclear Information System (INIS)

    1992-01-01

    The Advisory Committee on Nuclear Safety (ACNS) has reviewed safety issues associated with the software for the digital computers in the safety shutdown systems for the Darlington NGS. From this review the ACNS has developed four recommendations for safety-critical real-time software in nuclear power plants. These recommendations cover: the completion of the present efforts to develop an overall standard and sub-tier standards for safety-critical real-time software; the preparation of schedules and lists of responsibilities for this development; the concentration of AECB efforts on ensuring the scrutability of safety-critical real-time software; and, the collection of data on reliability and causes of failure (error) of safety-critical real-time software systems and on the probability and causes of common-mode failures (errors). (9 refs.)

  17. Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

    International Nuclear Information System (INIS)

    Neles, Julia Mareike; Schmidt, Gerhard

    2014-01-01

    Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

  18. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2001

    CERN Multimedia

    Seamus Hegarty / HR; Tel. 74128

    2001-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows : Senior Staff Advancement Committee (SSAC) David O. Williams/it (Convener) Cristoforo Benvenuti/est David Plane/ep Technical Engineers & Administrative Careers Committee (TEACC) Sverre Jarp/it (Chairman) Flemming Pedersen/ps Robin Lauckner/sl Christian Roche/ett Lars Leistam/est Dietrich Schinzel/ep Long-term contract Boards (LTCBs) LTCB 1 (Categories 2 & 5a) Tiziano Camporesi/ep [Convener] - Florence Ranjard/ep [Alternate] Jacques Gruber/ps - Peter Sievers/lhc [Alternate] Thomas Pettersson/est - Michel Mayoud/est [Alternate] Sue Foffano/as - Thierry Lagrange/spl [Alternate] Werner Zapf/hr (Secretary) LTCB 2 (Categories 3, 4, 5b & 5c) Véronique Paris/sl [Convener] - Fabien Perriollat/ps [Alternate] Mats Wilhelmsson/st - Véronique Fassnacht/tis [Alternate] Lucie Linssen/ep - Alfredo Placci/ep [Alternate] Patrick Geeraert/fi - John Cuthb...

  19. Composition of Staff Review Advisory Bodies - 2003

    CERN Multimedia

    2003-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows : Senior Staff Advancement Committee (SSAC) David Plane/EP [Convener] Enrico Chiaveri/AB Peter Schmid/EP Technical Engineers & Administrative Careers Committee (TEACC) Robin Lauckner/AB [Chairman]Marcel Mottier/EST Michael Letheren/EP Louis Walckiers/AT Lucie Linssen/EP Mats Wilhelmsson/ST Long-term contract Boards (LTCBs) LTCB 1 (Categories 2 & 5a) Tiziano Camporesi/EP [Convener]Florence Ranjard/EP [Alternate] Roger Bailey/ABPeter Sievers/AT " " Doris Forkel-Wirth/TISPierre Ninin/ST " " Rob Rayson/HRMaarten Wilbers/DSU " " Seamus Hegarty/HR [Secretary] LTCB 2 (Categories 3, 4, 5b & 5c) Véronique Paris/AB [Convener]Fabien Perriollat/AB [Alternate] Christian Lasseur/ESTRamon Folch/EST " " Lucie Linssen/EP Alfredo Placci/EP " " Mats Møller/ASLaszlo Abel/SPL " " Seamus Hegarty/HR [Secretary] Human Resources Division Tel. 74128

  20. Nuclear safety review for the year 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-01

    The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. The final version of the Nuclear Safety Review for the Year 2002 was prepared in the light of the discussion by the Board of Governors in March 2002. This report presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety at the end of 2002. This overview is supported by a more detailed factual account of safety-related events and issues worldwide during 2002. National authorities and the international community continued to reflect and act upon the implications of the events of II September 2001 for nuclear, radiation, transport and waste safety. In the light of this, the Agency has decided to transfer the organizational unit on nuclear security from the Department of Safeguards to the Department of Nuclear Safety (which thereby becomes the Department of Nuclear Safety and Security). By better exploiting the synergies between safety and security and promoting further cross-fertilization of approaches, the Agency is trying to help build up mutually reinforcing global regimes of safety and security. However, the Nuclear Safety Review for the Year 2002 addresses only those areas already in the safety programme. This short analytical overview is supported by a second part (corresponding to Part I of the Nuclear Safety Reviews of previous years), which describes significant safety-related events and issues worldwide during 2002. A Draft Nuclear Safety Review for the Year 2002 was submitted to the March 2003 session of the Board of Governors in document GOV/2003/6.

  1. Nuclear safety review for the year 2002

    International Nuclear Information System (INIS)

    2003-08-01

    The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. The final version of the Nuclear Safety Review for the Year 2002 was prepared in the light of the discussion by the Board of Governors in March 2002. This report presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety at the end of 2002. This overview is supported by a more detailed factual account of safety-related events and issues worldwide during 2002. National authorities and the international community continued to reflect and act upon the implications of the events of II September 2001 for nuclear, radiation, transport and waste safety. In the light of this, the Agency has decided to transfer the organizational unit on nuclear security from the Department of Safeguards to the Department of Nuclear Safety (which thereby becomes the Department of Nuclear Safety and Security). By better exploiting the synergies between safety and security and promoting further cross-fertilization of approaches, the Agency is trying to help build up mutually reinforcing global regimes of safety and security. However, the Nuclear Safety Review for the Year 2002 addresses only those areas already in the safety programme. This short analytical overview is supported by a second part (corresponding to Part I of the Nuclear Safety Reviews of previous years), which describes significant safety-related events and issues worldwide during 2002. A Draft Nuclear Safety Review for the Year 2002 was submitted to the March 2003 session of the Board of Governors in document GOV/2003/6

  2. Safety of vaccines used for routine immunization of U.S. children: a systematic review.

    Science.gov (United States)

    Maglione, Margaret A; Das, Lopamudra; Raaen, Laura; Smith, Alexandria; Chari, Ramya; Newberry, Sydne; Shanman, Roberta; Perry, Tanja; Goetz, Matthew Bidwell; Gidengil, Courtney

    2014-08-01

    Concerns about vaccine safety have led some parents to decline recommended vaccination of their children, leading to the resurgence of diseases. Reassurance of vaccine safety remains critical for population health. This study systematically reviewed the literature on the safety of routine vaccines recommended for children in the United States. Data sources included PubMed, Advisory Committee on Immunization Practices statements, package inserts, existing reviews, manufacturer information packets, and the 2011 Institute of Medicine consensus report on vaccine safety. We augmented the Institute of Medicine report with more recent studies and increased the scope to include more vaccines. Only studies that used active surveillance and had a control mechanism were included. Formulations not used in the United States were excluded. Adverse events and patient and vaccine characteristics were abstracted. Adverse event collection and reporting was evaluated by using the McHarm scale. We were unable to pool results. Strength of evidence was rated as high, moderate, low, or insufficient. Of 20 478 titles identified, 67 were included. Strength of evidence was high for measles/mumps/rubella (MMR) vaccine and febrile seizures; the varicella vaccine was associated with complications in immunodeficient individuals. There is strong evidence that MMR vaccine is not associated with autism. There is moderate evidence that rotavirus vaccines are associated with intussusception. Limitations of the study include that the majority of studies did not investigate or identify risk factors for AEs; and the severity of AEs was inconsistently reported. We found evidence that some vaccines are associated with serious AEs; however, these events are extremely rare and must be weighed against the protective benefits that vaccines provide. Copyright © 2014 by the American Academy of Pediatrics.

  3. Krsko periodic safety review project prioritization process

    International Nuclear Information System (INIS)

    Basic, I.; Vrbanic, I.; Spiler, J.; Lambright, J.

    2004-01-01

    Definition of a Krsko Periodic Safety Review (PSR) project is a comprehensive safety review of a plant after last ten years of operation. The objective is a verification by means of a comprehensive review using current methods that Krsko NPP remains safety when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. This objective encompasses the three main criteria or goals: confirmation that the plant is as safe as originally intended, determination if there are any structures, systems or components that could limit the life of the plant in the foreseeable future, and comparison the plant against modern safety standards and to identify where improvements would be beneficial at justifiable cost. Krsko PSR project is structured in the three phases: Phase 1: Preparation of Detailed 10-years PSR Program, Phase 2: Performing of 10-years PSR Program and preparing of associated documents (2001-2003), and Phase 3: Implementation of the prioritized compensatory measures and modifications (development of associated EEAR, DMP, etc.) after agreement with the SNSA on the design, procedures and time-scales (2004-2008). This paper presents the NEK PSR results of work performed under Phase 2 focused on the ranking of safety issues and prioritization of corrective measures needed for establishing an efficient action plan. Safety issues were identified in Phase 2 during the following review processes: Periodic Safety Review (PSR) task; Krsko NPP Regulatory Compliance Program (RCP) review; Westinghouse Owner Group (WOG) catalog items screening/review; SNSA recommendations (including IAEA RAMP mission suggestions/recommendations).(author)

  4. 77 FR 75118 - National Advisory Committee on Meat and Poultry Inspection

    Science.gov (United States)

    2012-12-19

    ... Advisory Committee on Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... Inspection Service (FSIS) is announcing a meeting of the National Advisory Committee on Meat and Poultry... strengthening Agency verification activities and guidance concerning sanitary dressing and antimicrobial...

  5. Safety evaluation report related to the construction of the Clinch River Breeder Reactor Plant. Docket No. 50-537. Suppl. 1

    International Nuclear Information System (INIS)

    1983-05-01

    Since the preparation of the Safety Evaluation Report the Advisory Committee on Reactor Safeguards considered the Clinch River construction permit license application at its 276th meeting and subsequently issued a favorable report, dated April 19, 1983 to the Commission (See Appendix I of this report). Additional documents associated with the application have been reviewed and a number of meetings have been held with the applicants. These events and documents are identified in Appendix E to this supplement. This supplement, SSER-1, to the Safety Evaluation Report, provides an evaluation of additional information received from the applicants since preparation of the SER regarding previously identified outstanding review items, and our response to the comments made by the Advisory Committee on Reactor Safeguards in its report

  6. Nuclear Safety Review for the Year 2003

    International Nuclear Information System (INIS)

    2004-08-01

    The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. In line with the suggestions made by the Board of Governors in March 2002, the first part is more analytical and less descriptive. This short analytical overview is supported by a second part, which describes significant safety related events and issues worldwide during 2003. A Draft Nuclear Safety Review for the Year 2003 was submitted to the March 2004 session of the Board of Governors in document GOV/2004/3. The final version of the Nuclear Safety Review for the Year 2003 was prepared in the light of the discussion by the Board.

  7. Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

    2009-04-01

    In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

  8. Krsko NPP Periodic Safety Review program

    International Nuclear Information System (INIS)

    Basic, I.; Spiler, J.; Novsak, M.

    2001-01-01

    The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)

  9. 77 FR 51789 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2012-08-27

    ... management and related activities. Tentative Agenda Call to Order, Introductions, Review of Agenda... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act...

  10. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2002

    CERN Multimedia

    Human Resources Division

    2002-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows: Senior Staff Advancement Committee (SSAC) Cristoforo BENVENUTI/EST [Convener] David PLANE/EP Peter SCHMID/EP Technical Engineers & Administrative Careers Committee (TEACC) Robin LAUCKNER/SL [Chairman] Flemming PEDERSEN/PS Lucie LINSSEN/EP Dietrich SCHINZEL/EP Marcel MOTTIER/EST Louis WALCKIERS/LHC Long-term contract Boards (LTCBs) (Categories 2 & 5a) Tiziano CAMPORESI/EP [Convener] Florence RANJARD/EP [Alternate] Jacques GRUBER/PS [until 30.6.2002] Roger BAILEY/SL [from 1.7. 2002] Peter SIEVERS/LHC [Alternate] Doris FORKEL-WIRTH/TIS Pierre NININ/ST [Alternate] Sue FOFFANO/AS Maarten WILBERS/DSU [Alternate] Werner ZAPF/HR[Secretary] LTCB 2 Categories 3, 4, 5b & 5c) Véronique PARIS/SL [Convener] Fabien PERRIOLLAT/PS [Alternate] Mats WILHELMSSON/ST Charles NUTTALL/TIS [Alternate] Lucie LINSSEN/EP Alfredo PLACCI/EP [Alternate] Patrick GEERAER...

  11. The review of online maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    Yamamoto, Tetsuya

    2009-01-01

    The Nuclear and Industrial Safety Agency (NISA) has begun the review of online maintenance in nuclear power plants in its advisory committee. The experts in the committee study the necessary actions in the regulation and safe and secure measure to implement the online maintenance. This paper explains the current progress of the review. (author)

  12. Periodic safety reviews of nuclear power plants

    International Nuclear Information System (INIS)

    Toth, Csilla

    2009-01-01

    Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

  13. Lift truck safety review

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, L.C.

    1997-03-01

    This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.

  14. Lift truck safety review

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1997-03-01

    This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter's Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given

  15. DOE Advanced Scientific Computing Advisory Committee (ASCAC) Report: Exascale Computing Initiative Review

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Daniel [University of Iowa; Berzins, Martin [University of Utah; Pennington, Robert; Sarkar, Vivek [Rice University; Taylor, Valerie [Texas A& M University

    2015-08-01

    On November 19, 2014, the Advanced Scientific Computing Advisory Committee (ASCAC) was charged with reviewing the Department of Energy’s conceptual design for the Exascale Computing Initiative (ECI). In particular, this included assessing whether there are significant gaps in the ECI plan or areas that need to be given priority or extra management attention. Given the breadth and depth of previous reviews of the technical challenges inherent in exascale system design and deployment, the subcommittee focused its assessment on organizational and management issues, considering technical issues only as they informed organizational or management priorities and structures. This report presents the observations and recommendations of the subcommittee.

  16. Periodic safety review of the experimental fast reactor JOYO. Review of the activity for safety

    International Nuclear Information System (INIS)

    Maeda, Yukimoto; Kashimura, Youichi; Suzuki, Toshiaki; Isozaki, Kazunori; Hoshiba, Hideaki; Kitamura, Ryoichi; Nakano, Tomoyuki; Takamatsu, Misao; Sekine, Takashi

    2005-02-01

    Periodic safety review (Review of the activity for safety) which consisted of 'Comprehensive evaluation of operation experience' and Incorporation of the latest technical knowledge' was carried out up to January 2005. 1. Comprehensive evaluation of operation experience. It was confirmed that the effectual activities for safety through the operation of JOYO were carried out in terms of (1) Operation management, (2) Maintenance management, (3) Fuel management, (4) Radiation management, (5) Radioactive waste management, (6) Emergency planning and (7) Feedback of incidents and failures. 2. Reflection of the latest technical knowledge. It was confirmed that the latest technical knowledge including regulation and guide line established by Nuclear Safety Commission of Japan until March 31st. 2003 were properly reflected in impressing the safety of the reactor. As a result, it was evaluated that the activity for safety was carried out effectually, and no additional measure was identified continual safe operation of the reactor. (author)

  17. 49 CFR 659.27 - Internal safety and security reviews.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 7 2010-10-01 2010-10-01 false Internal safety and security reviews. 659.27... State Oversight Agency § 659.27 Internal safety and security reviews. (a) The oversight agency shall... safety and security reviews in its system safety program plan. (b) The internal safety and security...

  18. 78 FR 41804 - NASA Advisory Council; Meeting.

    Science.gov (United States)

    2013-07-11

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: (13-077)] NASA Advisory Council; Meeting... Space Administration announces a meeting of the NASA Advisory Council (NAC). DATES: Wednesday, July 31... ADDRESSES: NASA Headquarters, Room 9H40, Program Review Center, 300 E Street SW., Washington, DC 20456 FOR...

  19. 78 FR 77643 - National Advisory Committee of Meat and Poultry Inspection

    Science.gov (United States)

    2013-12-24

    ... Advisory Committee of Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... of the National Advisory Committee on Meat and Poultry Inspection (NACMPI). The Committee is being... label on meat and poultry packages. With this input, the Agency will consider whether or not the current...

  20. Development of Safety Review Guidance for Research and Training Reactors

    International Nuclear Information System (INIS)

    Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

    2007-01-01

    The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

  1. Conducting organizational safety reviews - requirements, methods and experience

    International Nuclear Information System (INIS)

    Reiman, T.; Oedewald, P.; Wahlstroem, B.; Rollenhagen, C.; Kahlbom, U.

    2008-03-01

    Organizational safety reviews are part of the safety management process of power plants. They are typically performed after major reorganizations, significant incidents or according to specified review programs. Organizational reviews can also be a part of a benchmarking between organizations that aims to improve work practices. Thus, they are important instruments in proactive safety management and safety culture. Most methods that have been used for organizational reviews are based more on practical considerations than a sound scientific theory of how various organizational or technical issues influence safety. Review practices and methods also vary considerably. The objective of this research is to promote understanding on approaches used in organizational safety reviews as well as to initiate discussion on criteria and methods of organizational assessment. The research identified a set of issues that need to be taken into account when planning and conducting organizational safety reviews. Examples of the issues are definition of appropriate criteria for evaluation, the expertise needed in the assessment and the organizational motivation for conducting the assessment. The study indicates that organizational safety assessments involve plenty of issues and situations where choices have to be made regarding what is considered valid information and a balance has to be struck between focus on various organizational phenomena. It is very important that these choices are based on a sound theoretical framework and that these choices can later be evaluated together with the assessment findings. The research concludes that at its best, the organizational safety reviews can be utilised as a source of information concerning the changing vulnerabilities and the actual safety performance of the organization. In order to do this, certain basic organizational phenomena and assessment issues have to be acknowledged and considered. The research concludes with recommendations on

  2. Conducting organizational safety reviews - requirements, methods and experience

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, T.; Oedewald, P.; Wahlstroem, B. [Technical Research Centre of Finland, VTT (Finland); Rollenhagen, C. [Royal Institute of Technology, KTH, (Sweden); Kahlbom, U. [RiskPilot (Sweden)

    2008-03-15

    Organizational safety reviews are part of the safety management process of power plants. They are typically performed after major reorganizations, significant incidents or according to specified review programs. Organizational reviews can also be a part of a benchmarking between organizations that aims to improve work practices. Thus, they are important instruments in proactive safety management and safety culture. Most methods that have been used for organizational reviews are based more on practical considerations than a sound scientific theory of how various organizational or technical issues influence safety. Review practices and methods also vary considerably. The objective of this research is to promote understanding on approaches used in organizational safety reviews as well as to initiate discussion on criteria and methods of organizational assessment. The research identified a set of issues that need to be taken into account when planning and conducting organizational safety reviews. Examples of the issues are definition of appropriate criteria for evaluation, the expertise needed in the assessment and the organizational motivation for conducting the assessment. The study indicates that organizational safety assessments involve plenty of issues and situations where choices have to be made regarding what is considered valid information and a balance has to be struck between focus on various organizational phenomena. It is very important that these choices are based on a sound theoretical framework and that these choices can later be evaluated together with the assessment findings. The research concludes that at its best, the organizational safety reviews can be utilised as a source of information concerning the changing vulnerabilities and the actual safety performance of the organization. In order to do this, certain basic organizational phenomena and assessment issues have to be acknowledged and considered. The research concludes with recommendations on

  3. Nuclear Safety Review for 2015

    International Nuclear Information System (INIS)

    2015-06-01

    The Nuclear Safety Review 2015 focuses on the dominant nuclear safety trends, issues and challenges in 2014. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: improving radiation, transport and waste safety; strengthening safety in nuclear installations; enhancing emergency preparedness and response (EPR); and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the Agency’s safety standards. The global nuclear community continued to make steady progress in improving nuclear safety throughout the world in 2014; and, the Agency and its Member States continued to implement the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”), which was endorsed by the General Conference in 2011 after the Fukushima Daiichi accident in March 2011. • Significant progress has been made in reviewing and revising various Agency’s safety standards in areas such as management of radioactive waste, design basis hazard levels, protection of nuclear power plants (NPPs) against severe accidents, design margins to avoid cliff edge effects, multiple facilities at one site, and strengthening the prevention of unacceptable radiological consequences to the public and the environment, communications and EPR. In addition, the Guidelines for Drafting IAEA Safety Standards and Nuclear Security Series Publications was issued in July 2014.• The Agency continued to analyse the relevant technical aspects of the Fukushima Daiichi accident and to share and disseminate lessons learned to the wider nuclear community. In 2014, the Agency organized two international experts’ meetings (IEMs), one on radiation protection and one on severe accident management. Reports from previous IEMs were also published in 2014: IAEA Report on Human and Organizational Factors in Nuclear

  4. Internal safety review team at Comanche Peak SES

    Energy Technology Data Exchange (ETDEWEB)

    Davis, D [Comanche Peak Steam Electric Staion, Texas Utilities, TX (United States)

    1997-09-01

    The presentations describes the following issues: levels of defense in depth; internal safety review organizations; methods used to perform safety assessment; safety committee review; quality verification; root cause analysis; human performance program; industry operating experience.

  5. Safety Review Services, Site Review Services and IRRS

    International Nuclear Information System (INIS)

    Yllera, Javier

    2010-01-01

    The selection and the evaluation of the site for a nuclear power plant are crucial parts of establishing a nuclear power programme and can be significantly affected by costs, public acceptance and safety considerations. Siting is the process of selecting a suitable site for a facility. This is area containing the plant, defined by a boundary and under effective control of the Plant Management. For safety related issues comparison within topics is generally quite straightforward. For example, sites with relatively higher seismic hazard would be penalized in comparison with those in more stable areas. The site for the NPP is generally chosen at a relatively ‘aseismic’ part of the country. This generally means that well known seismogenic sources are more than at least 50 kms from the site. The proposed sites for nuclear installations shall be examined with respect to the frequency and the severity of natural and human induced events and phenomena that could affect the safety of the installation. The Events unconnected with the operation of a facility or activity which could have an effect on the safety of the facility or activity. The relationship between the site and the design for the nuclear installation shall be examined to ensure that the radiological risk to the public and the environment arising from releases defined by the source terms is acceptably low. The Nuclear Regulatory Authority should issue a document that sets out the technical safety and security criteria against which the Site Permit Application for a new NPP will be reviewed. The objective of the Site Safety Review Services (SSRS) is provided upon request from a Member State. An independent review and assessment of the site and nuclear installation safety in relation to external natural and man induced hazards. This is to make recommendations on additional analysis or plant modifications to be carried out in order to comply with the IAEA Safety Standards and to enhance safety

  6. Nuclear Safety Review for the Year 2012

    International Nuclear Information System (INIS)

    2012-07-01

    The Nuclear Safety Review for the Year 2012 contains an analytical overview of the dominant trends, issues and challenges worldwide in 2011 and the Agency's efforts to strengthen the global nuclear safety framework. This year's report also highlights issues and activities related to the accident at the Fukushima Daiichi nuclear power plant. The analytical overview is supported by the Appendix at the end of this document, entitled: The IAEA Safety Standards: Activities during 2011. A draft version of the Nuclear Safety Review for the Year 2012 was submitted to the March 2012 session of the Board of Governors in document GOV/2012/6. The final version of the Nuclear Safety Review for the Year 2012 was prepared in light of the discussions held during the Board of Governors and also of the comments received.

  7. Radiation and waste safety: Strengthening national capabilities

    International Nuclear Information System (INIS)

    Barretto, P.; Webb, G.; Mrabit, K.

    1997-01-01

    For many years, the IAEA has been collecting information on national infrastructures for assuring safety in applications of nuclear and radiation technologies. For more than a decade, from 1984-95, information relevant to radiation safety particularly was obtained through more than 60 expert missions undertaken by Radiation Protection Advisory Teams (RAPATs) and follow-up technical visits and expert missions. The RAPAT programme documented major weaknesses and the reports provided useful background for preparation of national requests for IAEA technical assistance. Building on this experience and subsequent policy reviews, the IAEA took steps to more systematically evaluate the needs for technical assistance in areas of nuclear and radiation safety. The outcome was the development of an integrated system designed to more closely assess national priorities and needs for upgrading their infrastructures for radiation and waste safety

  8. Effects of an educational patient safety campaign on patients' safety behaviours and adverse events.

    Science.gov (United States)

    Schwappach, David L B; Frank, Olga; Buschmann, Ute; Babst, Reto

    2013-04-01

    Rationale, aims and objectives  The study aims to investigate the effects of a patient safety advisory on patients' risk perceptions, perceived behavioural control, performance of safety behaviours and experience of adverse incidents. Method  Quasi-experimental intervention study with non-equivalent group comparison was used. Patients admitted to the surgical department of a Swiss large non-university hospital were included. Patients in the intervention group received a safety advisory at their first clinical encounter. Outcomes were assessed using a questionnaire at discharge. Odds ratios for control versus intervention group were calculated. Regression analysis was used to model the effects of the intervention and safety behaviours on the experience of safety incidents. Results  Two hundred eighteen patients in the control and 202 in the intervention group completed the survey (75 and 77% response rates, respectively). Patients in the intervention group were less likely to feel poorly informed about medical errors (OR = 0.55, P = 0.043). There were 73.1% in the intervention and 84.3% in the control group who underestimated the risk for infection (OR = 0.51, CI 0.31-0.84, P = 0.009). Perceived behavioural control was lower in the control group (meanCon  = 3.2, meanInt  = 3.5, P = 0.010). Performance of safety-related behaviours was unaffected by the intervention. Patients in the intervention group were less likely to experience any safety-related incident or unsafe situation (OR for intervention group = 0.57, CI 0.38-0.87, P = 0.009). There were no differences in concerns for errors during hospitalization. There were 96% of patients (intervention) who would recommend other patients to read the advisory. Conclusions  The results suggest that the safety advisory decreases experiences of adverse events and unsafe situations. It renders awareness and perceived behavioural control without increasing concerns for safety and

  9. 75 FR 1831 - Seeks Qualified Candidates for the Advisory Committee on Reactor Safeguards

    Science.gov (United States)

    2010-01-13

    ... NUCLEAR REGULATORY COMMISSION Seeks Qualified Candidates for the Advisory Committee on Reactor... Regulatory Commission (NRC) seeks qualified candidates for the Advisory Committee on Reactor Safeguards (ACRS... amended. ACRS provides independent expert advice on matters related to the safety of existing and proposed...

  10. Advisory group on transport package test standards. Vienna, 19-23 December 1977

    International Nuclear Information System (INIS)

    Ek, P.; Taylor, W.R.

    1978-03-01

    The IAEA convened the Advisory Group to (1) consider any available data on transport accidents and any risk assessments performed in Member States, with a view to making a critical study of the continuing adequacy of the package test requirements included in the current version of the IAEA Regulations for the Safe Transport of Radioactive Materials (Safety Series No.6, 1973 Revised Edition), and (2) make recommendations concerning the future planning and conduct of this study. The reports and recommendations are presented of the four working groups assigned, i.e., Statistical Data on Accidents and ''Near Accidents'', Incidents of Accidents and Risk Assessments, Review Package Testing Requirements, and Review Basis for the Radiation Levels for Packages

  11. Existing and future international standards for the safety of radioactive waste disposal

    International Nuclear Information System (INIS)

    Linsley, G.

    1999-01-01

    In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

  12. Nuclear safety review for 1984

    International Nuclear Information System (INIS)

    1985-08-01

    This publication is based on the fourth Nuclear Safety Review prepared by the IAEA Secretariat for presentation to the Board of Governors. It discusses relevant international activities in 1984 and the current status of nuclear safety and radiation protection, and looks ahead to anticipated developments

  13. Safety Review Committee - Annual Report 1991-1992

    International Nuclear Information System (INIS)

    1993-01-01

    During the year under review. The Safety Review Committee (SRC) assessed the safety of ANSTO's operations. This was done by site visits, examination of documentation and briefing by ANSTO officers responsible for particular operations, and includes HIFAR and Moata reactors, radioisotope production, packing and dispatch, radioactive waste management practices, occupational health and safety activities and ANSTO's arrangements for public health and safety beyond the site. This report describes the activities and findings of the SRC during the year ending 30 June 1992. 8 figs., ills

  14. Developing safety culture in nuclear activities. Practical suggestions to assist progress

    International Nuclear Information System (INIS)

    2000-01-01

    The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by the IAEA as Safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety Principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

  15. Developing safety culture in nuclear activities. Practical suggestions to assist progress

    International Nuclear Information System (INIS)

    1998-01-01

    The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by IAEA as safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

  16. 77 FR 17475 - Notification of Public Teleconferences of the Science Advisory Board; Environmental Economics...

    Science.gov (United States)

    2012-03-26

    ... Advisory Board; Environmental Economics Advisory Committee AGENCY: Environmental Protection Agency (EPA... Office announces public teleconferences of the SAB Environmental Economics Advisory Committee to conduct... Economics Advisory Committee (EEAC) will hold a public teleconferences to review the EPA draft report...

  17. ITER technical advisory committee meeting at Garching

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

    The ITER Technical Advisory Committee meeting took place on 24-27 February at the Garching Joint Work Site. According to the discussions at the ITER meeting in Yokohama in October 1998, the Technical Advisory Committee was requested to conduct a thorough review of the document 'Options for the reduced technical objectives / reduced cost ITER'

  18. International policy and advisory response regarding children's exposure to radio frequency electromagnetic fields (RF-EMF).

    Science.gov (United States)

    Redmayne, Mary

    2016-01-01

    Radiofrequency electromagnetic field (RF-EMF) exposure regulations/guidelines generally only consider acute effects, and not chronic, low exposures. Concerns for children's exposure are warranted due to the amazingly rapid uptake of many wireless devices by increasingly younger children. This review of policy and advice regarding children's RF-EMF exposure draws material from a wide variety of sources focusing on the current situation. This is not a systematic review, but aims to provide a representative cross-section of policy and advisory responses within set boundaries. There are a wide variety of approaches which I have categorized and tabulated ranging from ICNIRP/IEEE guidelines and "no extra precautions needed" to precautionary or scientific much lower maxima and extensive advice to minimize RF-EMF exposure, ban advertising/sale to children, and add exposure information to packaging. Precautionary standards use what I term an exclusion principle. The wide range of policy approaches can be confusing for parents/carers of children. Some consensus among advisory organizations would be helpful acknowledging that, despite extensive research, the highly complex nature of both RF-EMF and the human body, and frequent technological updates, means simple assurance of long-term safety cannot be guaranteed. Therefore, minimum exposure of children to RF-EMF is recommended. This does not indicate need for alarm, but mirrors routine health-and-safety precautions. Simple steps are suggested. ICNIRP guidelines need to urgently publish how the head, torso, and limbs' exposure limits were calculated and what safety margin was applied since this exposure, especially to the abdomen, is now dominant in many children.

  19. Internet Safety and Security Surveys - A Review

    DEFF Research Database (Denmark)

    Sharp, Robin

    This report gives a review of investigations into Internet safety and security over the last 10 years. The review covers a number of surveys of Internet usage, of Internet security in general, and of Internet users' awareness of issues related to safety and security. The focus and approach...... of the various surveys is considered, and is related to more general proposals for investigating the issues involved. A variety of proposals for how to improve levels of Internet safety and security are also described, and they are reviewed in the light of studies of motivational factors which affect the degree...

  20. The impact of patient advisors on healthcare outcomes: a systematic review

    Directory of Open Access Journals (Sweden)

    Anjana E. Sharma

    2017-10-01

    Full Text Available Abstract Background Patient advisory councils are a way for healthcare organizations to promote patient engagement. Despite mandates to implement patient advisory councils through programs like the Patient-Centered Medical Home (PCMH, there is a paucity of data measuring the impact of patients functioning in advisory roles. Our objective is to investigate whether patient engagement in patient advisory councils is linked to improvements in clinical quality, patient safety or patient satisfaction. Methods We searched PubMed, SCOPUS, CINAHL and Google Scholar for English language publications between November 2002 to August 2015, using a combination of “patient advisor” and “care outcomes” search terms. Article selection utilized dual screening facilitated by DistillerSR software, with group discussion to resolve discordance. Observational studies, randomized controlled trials, and case studies were included that described patients serving in an advisory role where primary outcomes were mentioned. Reference lists of included studies and grey literature searches were conducted. Qualitative thematic analysis was performed to synthesize results. Results Database searching yielded 639 articles total after removing duplicates, with 129 articles meeting full text inclusion criteria. 32 articles were identified for final review, 16 of which were case studies. Advisory roles included patient advisory councils, ad-hoc patient committees, community advisory councils, experience-based co-design, and other. Four practice-based studies from one research group, involving community advisors in the design of public health interventions, found improved clinical outcomes. No prospective experimental studies assessed the impact of patient advisors on patient safety or patient satisfaction. One cluster-randomized RCT showed that patient advisors helped health care planning efforts identify priorities more aligned with the PCMH. Ten case studies reported

  1. Report of the safety and wholesomeness of irradiated foods by the advisory committee on irradiated and novel foods

    International Nuclear Information System (INIS)

    1986-01-01

    Following the conclusions of the Joint Expert Committee on the wholesomeness of Irradiated Foods(JECFI) an Advisory Committee on Irradiated and Novel Foods (ACINF) was set up to review the position relating to the irradiation of food and to report and advise on its findings to the Ministries of Health and Agriculture, with a view to changing legislation in the U.K. The advisory committee concluded that there were no justifications, on public health grounds, for the present U.K. regulations not to be amended and that the irradiation of foods up to an overall average dose of 10 Gy by X-rays and γ-rays up to 5 MeV, or for electrons up to 10 MeV, should be permitted. The committee recommended that food irradiation procedures and consumption patterns should be monitored. (UK)

  2. The safe management of sources of radiation: Principles and strategies. INSAG-11. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    1999-01-01

    The IAEA activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring safety of nuclear power plants, the IAEA established the International Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating commonly shared safety principles. The present report deals with the general principles governing the safety of all sources of radiation and with application of these principles. It intends to show that, at the conceptual level, the distinction traditionally made between nuclear safety and radiation protection is hardly justifiable. It is intended primarily for those non-specialists who need to take decisions about safe management of sources of radiation and who wish to gain a better understanding of the approach followed in managing the safety of these sources

  3. The Interagency Nuclear Safety Review Panel's Galileo safety evaluation report

    International Nuclear Information System (INIS)

    Nelson, R.C.; Gray, L.B.; Huff, D.A.

    1989-01-01

    The safety evaluation report (SER) for Galileo was prepared by the Interagency Nuclear Safety Review Panel (INSRP) coordinators in accordance with Presidential directive/National Security Council memorandum 25. The INSRP consists of three coordinators appointed by their respective agencies, the Department of Defense, the Department of Energy (DOE), and the National Aeronautics and Space Administration (NASA). These individuals are independent of the program being evaluated and depend on independent experts drawn from the national technical community to serve on the five INSRP subpanels. The Galileo SER is based on input provided by the NASA Galileo Program Office, review and assessment of the final safety analysis report prepared by the Office of Special Applications of the DOE under a memorandum of understanding between NASA and the DOE, as well as other related data and analyses. The SER was prepared for use by the agencies and the Office of Science and Technology Policy, Executive Office of the Present for use in their launch decision-making process. Although more than 20 nuclear-powered space missions have been previously reviewed via the INSRP process, the Galileo review constituted the first review of a nuclear power source associated with launch aboard the Space Transportation System

  4. Safety Review related to Commercial Grade Digital Equipment in Safety System

    International Nuclear Information System (INIS)

    Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

    2013-01-01

    The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

  5. Nuclear Safety Review for 2014

    International Nuclear Information System (INIS)

    2014-07-01

    The Nuclear Safety Review 2014 focuses on the dominant nuclear safety trends, issues and challenges in 2013. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: strengthening safety in nuclear installations; improving radiation, transport and waste safety; enhancing emergency preparedness and response (EPR); improving regulatory infrastructure and effectiveness; and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards, and activities relevant to the Agency’s safety standards. The global nuclear community has made steady and continuous progress in strengthening nuclear safety in 2013, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”) and reported in Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2013/8-GC(57)/INF/5), and the Supplementary Information to that report and Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2014/2). • Significant progress continues to be made in several key areas, such as assessments of safety vulnerabilities of nuclear power plants (NPPs), strengthening of the Agency’s peer review services, improvements in EPR capabilities, strengthening and maintaining capacity building, and protecting people and the environment from ionizing radiation. The progress that has been made in these and other areas has contributed to the enhancement of the global nuclear safety framework. • Significant progress has also been made in reviewing the Agency’s safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on vitally important areas such as design and operation of NPPs, protection of NPPs against severe accidents, and EPR. • The Agency continued to

  6. Periodic safety review of the experimental fast reactor JOYO. Review of aging management

    International Nuclear Information System (INIS)

    Isozaki, Kazunori; Ogawa, To-ru; Nishino, Kazunari

    2005-05-01

    Periodic safety review (Review of the aging management) which consisted of ''Technical review on aging for the safety related structures, systems and components'' and ''Establishment a long term maintenance program'' was carried out up to April 2005. 1. Technical review on aging for the safety related structures, systems and components. It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them. 2. Establishment of long term maintenance program. The long term maintenance during JFY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection and renewal based on the long term maintenance program, in addition to the spontaneous inspection of the long term voluntary long-term inspection plan, could prevent the loss of function of the safety related structures, systems and components. (author)

  7. ITER management advisory committee meeting

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    2001-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held on 23 February in Garching, Germany. The main topics were: the consideration of the report by the Director on the ITER EDA Status, the review of the Work Programme, the review of the Joint Fund, the review of a schedule of ITER meetings, and the arrangements for termination and wind-up of the EDA

  8. Travelers' Health: Injuries and Safety

    Science.gov (United States)

    ... Safety Road Safety - 8 Steps MERS Health Advisory poster MERS Pictogram CDC Guide for Healthy Travel Website ... possible, fly on larger planes (>30 seats), in good weather, during the daylight hours, and with experienced ...

  9. Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

    International Nuclear Information System (INIS)

    Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

    2009-01-01

    In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

  10. Material presented to advisory committee on reactor safeguards, subcommittee on extreme external phenomena, January 29-30, 1981, Los Angeles, California. Seismic safety margins research program

    International Nuclear Information System (INIS)

    Smith, P.D.; Bernreuter, D.L.; Bohn, M.P.; Chuang, T.Y.; Cummings, G.E.; Dong, R.G.; Johnson, J.J.; Wells, J.E.

    1981-01-01

    The January 29-30, 1981, meeting of the Advisory Committee on Reactor Safeguards (ACRS), Subcommittee on Extreme External Phenomena, mark the close of Phase I efforts on the Seismic Safety Margins Research Program (SSMRP). Presentations at the meeting focused on results produced. These included computer codes, response computations, failure and release probabilities, data bases, and fragilities and parameter characteristics

  11. Review of licensee event reports, 1976 to 1978

    International Nuclear Information System (INIS)

    1979-09-01

    This report was prepared in response to a request by the Chairman of the US Nuclear Regulatory Commission for the Advisory Committee on Reactor Safeguards to review, with specific objectives, the Licensee Event Reports (LERs) issued fom 1976 through 1978. A principal objective of the present study was to identify those events which have implications for improved reactor safety. Approximately 8,700 LERs were filed during the three-year period under review. These described events ranging from the trivial to those of major safety significance. This study has confirmed that LERs represent a source of valuable data and information. However, it must be recognized that a detailed review of LERs will not identify all safety problems likely to be encountered in the operation of nuclear power plants. As a result of this review, a number of classes of events were identified. These classes were subsequently categorized into three groups: (a) those having potentially serious safety implications, (b) events that must be regarded as matters of concern, and (c) events of lower safety significance but with excessive frequency

  12. Lessons learned from the Galileo and Ulysses flight safety review experience

    International Nuclear Information System (INIS)

    Bennett, Gary L.

    1998-01-01

    In preparation for the launches of the Galileo and Ulysses spacecraft, a very comprehensive aerospace nuclear safety program and flight safety review were conducted. A review of this work has highlighted a number of important lessons which should be considered in the safety analysis and review of future space nuclear systems. These lessons have been grouped into six general categories: (1) establishment of the purpose, objectives and scope of the safety process; (2) establishment of charters defining the roles of the various participants; (3) provision of adequate resources; (4) provision of timely peer-reviewed information to support the safety program; (5) establishment of general ground rules for the safety review; and (6) agreement on the kinds of information to be provided from the safety review process

  13. Safety evaluation review of the prototype license application safety analysis report

    International Nuclear Information System (INIS)

    1991-08-01

    The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the belowground vault (BGV) alternative method of low-level radioactive waste disposal. In Volume 1 of NUREG-1375, the NRC staff provided the safety review results for an earth-mounded concrete bunker PLASAR. In the current report, the staff focused its review on the design, construction, and operational aspects of the BGV PLASAR. The staff developed review comments and questions using the Standard Review Plan (SRP), Rev. 1 (NUREG-1200) as the basis for evaluating the acceptability of the information provided in the BGV PLASAR. The detailed review comments provided in this report are intended to be useful guidance to facility developers and State regulators in addressing issues likely to be encountered in the review of a license application for a low-level-waste disposal facility. 44 refs

  14. Periodic Safety Review of Nuclear Power Plants: Experience of Member States

    International Nuclear Information System (INIS)

    2010-04-01

    Routine reviews of nuclear power plant operation (including modifications to hardware and procedures, operating experience, plant management and personnel competence) and special reviews following major events of safety significance are the primary means of safety verification. In addition, many Member States of the IAEA have initiated systematic safety reassessments, termed periodic safety reviews, of nuclear power plants, to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments and siting aspects. The reviews include an assessment of plant design and operation against current safety standards and practices, and they have the objective of ensuring a high level of safety throughout the plant's operating lifetime. They are complementary to the routine and special safety reviews and do not replace them. Periodic safety reviews of nuclear power plants are considered an effective way to obtain an overall view of actual plant safety, and to determine reasonable and practical modifications that should be made in order to maintain a high level of safety. They can be used as a means of identifying time limiting features of the plant in order to determine nuclear power plant operation beyond the designed lifetime. The periodic safety review process can be used to support the decision making process for long term operation or licence renewal. Since 1994, the use of periodic safety reviews by Member States has substantially broadened and confirmed its benefits. Periodic safety review results have, for example, been used by some Member States to help provide a basis for continued operation beyond the current licence term, to communicate more effectively with stakeholders regarding nuclear power plant safety, and to help identify changes to plant operation that enhance safety. This IAEA-TECDOC is intended to assist Member States in the implementation of a periodic safety review. This publication complements the

  15. Task Force Report, Safety of Personnel in LHC underground areas following the accident of 19th September 2008

    CERN Document Server

    Delille, B; Inigo-Golfin, J; Lindell, G; Roy, G; Tavian, L; Thomas, E; Trant, R; Völlinger, C

    2009-01-01

    In January 2009, the Task Force on Safety of Personnel in the LHC underground areas following the accident in sector 3-4 of 19th September 2008 (Safety Task Force) received from the CERN Director General the mandate to investigate the impact of the accident of 19th September 2008 on the safety of personnel working in the LHC underground areas. This mandate includes the elaboration of preventive and/or corrective measures, if deemed necessary. This report gives the conclusions and recommendations of the Safety Task Force which have been reviewed by an external advisory committee of safety experts.

  16. A literature review of safety culture.

    Energy Technology Data Exchange (ETDEWEB)

    Cole, Kerstan Suzanne; Stevens-Adams, Susan Marie; Wenner, Caren A.

    2013-03-01

    Workplace safety has been historically neglected by organizations in order to enhance profitability. Over the past 30 years, safety concerns and attention to safety have increased due to a series of disastrous events occurring across many different industries (e.g., Chernobyl, Upper Big-Branch Mine, Davis-Besse etc.). Many organizations have focused on promoting a healthy safety culture as a way to understand past incidents, and to prevent future disasters. There is an extensive academic literature devoted to safety culture, and the Department of Energy has also published a significant number of documents related to safety culture. The purpose of the current endeavor was to conduct a review of the safety culture literature in order to understand definitions, methodologies, models, and successful interventions for improving safety culture. After reviewing the literature, we observed four emerging themes. First, it was apparent that although safety culture is a valuable construct, it has some inherent weaknesses. For example, there is no common definition of safety culture and no standard way for assessing the construct. Second, it is apparent that researchers know how to measure particular components of safety culture, with specific focus on individual and organizational factors. Such existing methodologies can be leveraged for future assessments. Third, based on the published literature, the relationship between safety culture and performance is tenuous at best. There are few empirical studies that examine the relationship between safety culture and safety performance metrics. Further, most of these studies do not include a description of the implementation of interventions to improve safety culture, or do not measure the effect of these interventions on safety culture or performance. Fourth, safety culture is best viewed as a dynamic, multi-faceted overall system composed of individual, engineered and organizational models. By addressing all three components of

  17. Safety review and approval process for the TFTR

    International Nuclear Information System (INIS)

    Levine, J.D.; Howe, H.J.; Howe, K.E.

    1983-01-01

    The design, construction, and operation of the Tokamak Fusion Test Reactor (TFTR) has undergone an extensive safety and enviromental analysis involving Princeton Plasma Physics Laboratory (PPPL), the U.S. Department of Energy (DOE), the Ebasco/Grumman Industrial Subcontractor Team, and other organizations. This analysis, which is continuing during the TFTR operational phase, has been facilitated by the preparation, review and approval of several documents, including an Environmental Statement (Draft and Final), a Preliminary Safety Analysis Report (PSAR), a Final Safety Analysis Report (FSAR), Operations Safety Requirements (OSRs) and Safety Requirements (SRs), and various Operating and Maintenance Manuals. Through TFTR Safety Group participation in formal system design evaluations, change control boards, and reviews of project procurement and installation documentation, the TFTR Management Configuration Control System assures that all aspects of the project, including proposed design, installation and operational changes, receive prompt and thorough safety analyses. These efforts will continue as the TFTR Program moves into the neutral beam and D-T operational phases. The safety review and approval experience that has been acquired on the TFTR Project should serve as a foundation for similar efforts on future fusion devices

  18. Medication safety programs in primary care: a scoping review.

    Science.gov (United States)

    Khalil, Hanan; Shahid, Monica; Roughead, Libby

    2017-10-01

    Medication safety plays an essential role in all healthcare organizations; improving this area is paramount to quality and safety of any wider healthcare program. While several medication safety programs in the hospital setting have been described and the associated impact on patient safety evaluated, no systematic reviews have described the impact of medication safety programs in the primary care setting. A preliminary search of the literature demonstrated that no systematic reviews, meta-analysis or scoping reviews have reported on medication safety programs in primary care; instead they have focused on specific interventions such as medication reconciliation or computerized physician order entry. This scoping review sought to map the current medication safety programs used in primary care. The current scoping review sought to examine the characteristics of medication safety programs in the primary care setting and to map evidence on the outcome measures used to assess the effectiveness of medication safety programs in improving patient safety. The current review considered participants of any age and any condition using care obtained from any primary care services. We considered studies that focussed on the characteristics of medication safety programs and the outcome measures used to measure the effectiveness of these programs on patient safety in the primary care setting. The context of this review was primary care settings, primary healthcare organizations, general practitioner clinics, outpatient clinics and any other clinics that do not classify patients as inpatients. We considered all quantitative studied published in English. A three-step search strategy was utilized in this review. Data were extracted from the included studies to address the review question. The data extracted included type of medication safety program, author, country of origin, aims and purpose of the study, study population, method, comparator, context, main findings and outcome

  19. The IAEA safety standards

    International Nuclear Information System (INIS)

    Karbassioun, Ahmad

    1995-01-01

    During the development of the NUSS standards, wide consultation was carried out with all the Member States to obtain a consensus and the programme was supervised by a Senior Advisory Group consisting of senior safety experts from 13 countries. This group of senior regulators later became what is now known as the Nuclear Safety Standards Advisory Group (NUSSAG) and comprises of senior regulatory experts from 16 countries. The standards that were developed comprise of four types of documents: safety fundamentals; codes of practice; safety guides; and safety practices. The safety fundamentals set out the basic objectives, concepts and principles for nuclear safety in nuclear power plants. The codes of practice, are of a legislative nature, and establish the general objectives that must be fulfilled to ensure adequate nuclear power plant safety. They cover five areas: governmental organization; siting, design, operation and quality assurance. The safety guides, administrative in character, recommend procedures and acceptable technical solutions to implement the codes and guides by presenting further details gained from Member States, on the application and interpretation of individual concepts in the NUSS codes and guides. In total in the NUSS series there is currently one Fundamentals document, five Codes of Practice and fifty-six Safety Guides

  20. 75 FR 67807 - Pipeline Safety: Emergency Preparedness Communications

    Science.gov (United States)

    2010-11-03

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... is issuing an Advisory Bulletin to remind operators of gas and hazardous liquid pipeline facilities... Gas Pipeline Systems. Subject: Emergency Preparedness Communications. Advisory: To further enhance the...

  1. 75 FR 63862 - Meeting of the CJIS Advisory Policy Board

    Science.gov (United States)

    2010-10-18

    ... notice is to announce the meeting of the Criminal Justice Information Services (CJIS) Advisory Policy... DEPARTMENT OF JUSTICE Federal Bureau of Investigation Meeting of the CJIS Advisory Policy Board.... The CJIS APB is responsible for reviewing policy issues and appropriate technical and operational...

  2. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  3. ITER management advisory committee meeting

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    2001-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held in Vienna on 16 July 2001. It was the last MAC Meeting and the main topics were consideration of the report by the Director on the ITER EDA status, review of the Work Programme, review of the Joint Fund and arrangements for termination and wind-up of the EDA

  4. 49 CFR 659.29 - Oversight agency safety and security reviews.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 7 2010-10-01 2010-10-01 false Oversight agency safety and security reviews. 659... Role of the State Oversight Agency § 659.29 Oversight agency safety and security reviews. At least... safety program plan and system security plan. Alternatively, the on-site review may be conducted in an on...

  5. 77 FR 34408 - Meeting of the Advisory Committee; Meeting

    Science.gov (United States)

    2012-06-11

    ... examinations in actuarial mathematics and methodology referred to in 29 U.S.C. 1242(a)(1)(B) and to review the... meeting of the Advisory Committee on Actuarial Examinations (a portion of which will be open to the public.... SUPPLEMENTARY INFORMATION: Notice is hereby given that the Advisory Committee on Actuarial Examinations will...

  6. Third meeting of the advisory group for the comprehensive review of the IAEA regulations for the safe transport of radioactive materials, Vienna, 7-11 November 1983

    International Nuclear Information System (INIS)

    Rawl, R.R.

    This meeting was the third and final planned stage in the process to revise the Agency's Regulations for the Safe Transport of Radioactive Materials, Safety Series No. 6. Its task was to consider comments which had been submitted in response to the Agency's circulation of the third draft revision of Safety Series No. 6 and to make any necessary changes to the draft that the Advisory Group felt were necessary

  7. 76 FR 67715 - Science Advisory Board

    Science.gov (United States)

    2011-11-02

    ... Administration (NOAA) science programs are of the highest quality and provide optimal support to resource... Advisory Board in Reviewing NOAA's Research and Development Portfolio-Presentation and Discussion; (6) NOAA...

  8. 78 FR 69991 - Advisory Committee; Veterinary Medicine Advisory Committee; Termination

    Science.gov (United States)

    2013-11-22

    .... FDA-2013-N-1380] Advisory Committee; Veterinary Medicine Advisory Committee; Termination AGENCY: Food... announcing the termination of the Veterinary Medicine Advisory Committee. This document removes the Veterinary Advisory Committee from the Agency's list of standing advisory committees. DATES: This rule is...

  9. Enhancing operational nuclear safety

    International Nuclear Information System (INIS)

    Sengoku, Katsuhisa

    2008-01-01

    's safety standards and program which provides the safety objective following the 10 fundamental safety principles. The safety requirements defines the functional conditions required for safety and the safety guides provides user-friendly and up-to-date practical guidance representing good/best practices to fulfill the requirements. The IAEA provides safety review services and fields safety review teams upon request of member states for the regulatory, the International Regulatory Review Team (IRRT) and Operational Safety Review Team (OSART) and Peer Review of the Operational and Safety Performance Experience Review (PROSPER). The OSART programme's purpose is to assist member states in enhancing the operational safety of individual nuclear power plants and to promote the continuous development of operational safety within all member states by the dissemination of information on good practice. The OSART Mission Results (OSMIR) database contains the results from 73 OSART missions and 54 follow up visits from 1991 and its continually updated. The Asian Nuclear Safety Network (ANSN) was established to pool and share existing and new technical knowledge and practical experience to further improve the safety of nuclear installation in Asia. In summary, the enhancement of the GNSR is anchored in the recognition that all the states are in the same boat and the increasing importance of sharing and mutual learning, sharing knowledge and experience through regional and global networking. It requires joint and coordinated strategy by all states. The IAEA is willing and ready to support the GNSR through the establishment and application of safety standards, and safety review and advisory services and international instruments. (Author)

  10. Nuclear safety review for the year 1997

    International Nuclear Information System (INIS)

    1998-12-01

    The Nuclear Safety Review attempts to summarize the global nuclear safety scene during 1997. It starts with discussion of significant safety related events worldwide: International cooperation; reactor facilities; radioactive waste management; medical uses of radiation sources; events at other facilities and transport of radioactive material. This is followed by a description of principal IAEA activities that contributed to global nuclear safety, namely: legally binding international agreements; non-binding safety standards and their application. The third part highlights developments in Member States as they reported them. The review closes with a description of issues that are likely to be prominent in the coming year(s). A draft version was submitted to the March 1998 session of the IAEA Board of Governors, and this final version has been prepared in light of the discussion in the Board and was submitted for information to the 42nd session of the IAEA General Conference

  11. The safe management of sources of radiation: Principles and strategies. INSAG-11. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    The IAEA activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring safety of nuclear power plants, the IAEA established the International Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating commonly shared safety principles. The present report deals with the general principles governing the safety of all sources of radiation and with application of these principles. It intends to show that, at the conceptual level, the distinction traditionally made between nuclear safety and radiation protection is hardly justifiable. It is intended primarily for those non-specialists who need to take decisions about safe management of sources of radiation and who wish to gain a better understanding of the approach followed in managing the safety of these sources

  12. 77 FR 68103 - National Construction Safety Team Advisory Committee Meeting

    Science.gov (United States)

    2012-11-15

    ... Standards and Technology (NIST) Disaster and Failure Studies Program, receive NIST's response to the... posted on the NIST Web site at http://www.nist.gov/el/disasterstudies/ncst/ . DATES: The NCST Advisory.... FOR FURTHER INFORMATION CONTACT: Eric Letvin, Director, Disaster and Failure Studies Program, 100...

  13. 77 FR 31071 - Research Advisory Committee on Gulf War Veterans' Illnesses, Notice of Meeting

    Science.gov (United States)

    2012-05-24

    ... DEPARTMENT OF VETERANS AFFAIRS Research Advisory Committee on Gulf War Veterans' Illnesses, Notice... Advisory Committee Act) that the Research Advisory Committee on Gulf War Veterans' Illnesses will meet on... Asia theater of operations during the Gulf War. The Committee will review VA program activities related...

  14. 75 FR 28686 - Research Advisory Committee on Gulf War Veterans' Illnesses; Notice of Meeting

    Science.gov (United States)

    2010-05-21

    ... DEPARTMENT OF VETERANS AFFAIRS Research Advisory Committee on Gulf War Veterans' Illnesses; Notice... Advisory Committee Act) that the Research Advisory Committee on Gulf War Veterans' Illnesses will meet on... Asia theater of operations during the Gulf War. The Committee will review VA program activities related...

  15. 76 FR 9407 - Research Advisory Committee on Gulf War Veterans' Illnesses; Notice of Meeting

    Science.gov (United States)

    2011-02-17

    ... DEPARTMENT OF VETERANS AFFAIRS Research Advisory Committee on Gulf War Veterans' Illnesses; Notice... Advisory Committee Act) that the Research Advisory Committee on Gulf War Veterans' Illnesses will meet on... Southwest Asia theater of operations during the Gulf War. The Committee will review VA program activities...

  16. 75 FR 65405 - Research Advisory Committee on Gulf War Veterans' Illnesses; Notice of Meeting

    Science.gov (United States)

    2010-10-22

    ... DEPARTMENT OF VETERANS AFFAIRS Research Advisory Committee on Gulf War Veterans' Illnesses; Notice... Advisory Committee Act) that the Research Advisory Committee on Gulf War Veterans' Illnesses will meet on... Asia theater of operations during the Gulf War. The Committee will review VA program activities related...

  17. Safeguards Culture: Analogies from Safety Culture and Security Culture

    International Nuclear Information System (INIS)

    Naito, K.

    2013-01-01

    The terminology of 'safeguards culture' has been used loosely by safeguards experts as an essential element for establishing an organizational environment of stakeholders for the effective and efficient implementation of international safeguards. However, unlike the other two triplet brothers/ sisters of 3S's (Safety, Security, Safeguards), there is no formally established definition of safeguards culture. In the case of safety culture, INSAG (the International Nuclear Safety Advisory Group) has extensively dealt with its concept, elaborating its definition and key characteristics, and published its report, INSAG-4, as the IAEA Safety Series 75. On the other hand, security culture has also been defined by AdSec (the Advisory Group on Nuclear Security). In this paper, a provisional definition of safeguards culture is made on the analogies of safety culture and security culture, and an effort is made to describe essential elements of safeguards culture. It is proposed for SAGSI (the Standing Advisory Group on Safeguards Implementation) to formally consider the definition of safeguards culture and its characteristics. The paper is followed by the slides of the presentation. (author)

  18. Operational safety review programmes for nuclear power plants. Guidelines for assessment

    International Nuclear Information System (INIS)

    2002-01-01

    The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

  19. Improving the safety of future nuclear fission power plants

    International Nuclear Information System (INIS)

    Frisch, W.; Gros, G.

    2001-01-01

    The main objectives and principles in nuclear fission reactor safety are presented, e.g. the defence in depth strategy and technical principles such as redundancy, diversity and physical separation. After a brief historical review of the continuous development of safety improvement, the most recent international discussion is presented. This includes mainly the international activities within IAEA and its International Nuclear Safety Advisory Group (INSAG). The safety improvement, presented in recommendations of IAEA and INSAG is expressed as an improvement of all elements and all levels of the defence in depth concept. Special emphasis is put on improvement of the highest level, which requires the implementation of means to mitigate consequences of accidents with severe core damage. The different future concepts are briefly characterised. Some examples from the French-German safety approach are taken to demonstrate how requirements for safety improvement by means of an enhancement of the defence in depth principle are developed

  20. Safety culture

    International Nuclear Information System (INIS)

    1991-01-01

    The response to a previous publication by the International Nuclear Safety Advisory Group (INSAG), indicated a broad international interest in expansion of the concept of Safety Culture, in such a way that its effectiveness in particular cases may be judged. This report responds to that need. In its manifestation, Safety Culture has two major components: the framework determined by organizational policy and by managerial action, and the response of individuals in working within and benefiting by the framework. 1 fig

  1. Safety reviews of next-generation light-water reactors

    International Nuclear Information System (INIS)

    Kudrick, J.A.; Wilson, J.N.

    1997-01-01

    The Nuclear Regulatory Commission (NRC) is reviewing three applications for design certification under its new licensing process. The U.S. Advanced Boiling Water Reactor (ABWR) and System 80+ designs have received final design approvals. The AP600 design review is continuing. The goals of design certification are to achieve early resolution of safety issues and to provide a more stable and predictable licensing process. NRC also reviewed the Utility Requirements Document (URD) of the Electric Power Research Institute (EPRI) and determined that its guidance does not conflict with NRC requirements. This review led to the identification and resolution of many generic safety issues. The NRC determined that next-generation reactor designs should achieve a higher level of safety for selected technical and severe accident issues. Accordingly, NRC developed new review standards for these designs based on (1) operating experience, including the accident at Three Mile Island, Unit 2; (2) the results of probabilistic risk assessments of current and next-generation reactor designs; (3) early efforts on severe accident rulemaking; and (4) research conducted to address previously identified generic safety issues. The additional standards were used during the individual design reviews and the resolutions are documented in the design certification rules. 12 refs

  2. 75 FR 8789 - Research Advisory Committee on Gulf War Veterans' Illnesses; Notice of Meeting

    Science.gov (United States)

    2010-02-25

    ... DEPARTMENT OF VETERANS AFFAIRS Research Advisory Committee on Gulf War Veterans' Illnesses; Notice... Advisory Committee Act) that the Research Advisory Committee on Gulf War Veterans' Illnesses will meet on... theater of operations during the Gulf War. The Committee will review VA program activities related to Gulf...

  3. 78 FR 77205 - Research Advisory Committee on Gulf War Veterans' Illnesses; Notice of Meeting

    Science.gov (United States)

    2013-12-20

    ... DEPARTMENT OF VETERANS AFFAIRS Research Advisory Committee on Gulf War Veterans' Illnesses; Notice... Advisory Committee Act) that the Research Advisory Committee on Gulf War Veterans' Illnesses will meet on... service in the Southwest Asia theater of operations during the Gulf War. The Committee will review VA...

  4. 75 FR 8038 - Fruit and Vegetable Industry Advisory Committee

    Science.gov (United States)

    2010-02-23

    ... Agricultural Commodities Act program, marketing agreements, food safety, local farmer/education initiatives... DEPARTMENT OF AGRICULTURE Agricultural Marketing Service [Doc. No. AMS-FV-10-0017; FV-09-378] Fruit and Vegetable Industry Advisory Committee AGENCY: Agricultural Marketing Service, USDA. ACTION...

  5. On some aspects of nuclear safety surveillance and review

    International Nuclear Information System (INIS)

    Li Ganjie; Zhu Hong; Zhou Shanyuan

    2004-01-01

    Five aspects of the nuclear safety surveillance and review are discussed: Strict implementation of nuclear safety regulation, making the nuclear safety surveillance and review more normalization, procedurization, scientific decision-making; Strictly requiring the applicant to comply with the requirements of codes, do not allowing the utilization of mixing of codes; Properly controlling the strictness for the review on significant non-conformance; Strengthening the co-operation between regional offices and technical support units, Properly treat the relations between administrational management unit and technical support units. (authors)

  6. A review of models relevant to road safety.

    Science.gov (United States)

    Hughes, B P; Newstead, S; Anund, A; Shu, C C; Falkmer, T

    2015-01-01

    It is estimated that more than 1.2 million people die worldwide as a result of road traffic crashes and some 50 million are injured per annum. At present some Western countries' road safety strategies and countermeasures claim to have developed into 'Safe Systems' models to address the effects of road related crashes. Well-constructed models encourage effective strategies to improve road safety. This review aimed to identify and summarise concise descriptions, or 'models' of safety. The review covers information from a wide variety of fields and contexts including transport, occupational safety, food industry, education, construction and health. The information from 2620 candidate references were selected and summarised in 121 examples of different types of model and contents. The language of safety models and systems was found to be inconsistent. Each model provided additional information regarding style, purpose, complexity and diversity. In total, seven types of models were identified. The categorisation of models was done on a high level with a variation of details in each group and without a complete, simple and rational description. The models identified in this review are likely to be adaptable to road safety and some of them have previously been used. None of systems theory, safety management systems, the risk management approach, or safety culture was commonly or thoroughly applied to road safety. It is concluded that these approaches have the potential to reduce road trauma. Copyright © 2014 Elsevier Ltd. All rights reserved.

  7. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 10, March 2009

    International Nuclear Information System (INIS)

    2009-03-01

    The current issue contains information about the following meetings: Application of the Code of Conduct on the Safety of Research Reactors (the 'Code'). Environmental Modelling for Radiation Safety (EMRAS II); Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The document also gives an overview on International Nuclear Security Advisory Service (INSServ)

  8. 76 FR 21936 - Aviation Rulemaking Advisory Committee-New Task

    Science.gov (United States)

    2011-04-19

    ... assignment for the Aviation Rulemaking Advisory Committee (ARAC). SUMMARY: The FAA assigned the Aviation... the evolving transportation needs, challenges and opportunities of the United States and global... influence the need to consider rulemaking; e.g., safety, capacity, cost, environmental impacts...

  9. IRSN safety research carried out for reviewing geological disposal safety case

    International Nuclear Information System (INIS)

    Serres, Christophe; Besnus, Francois; Gay, Didier

    2010-01-01

    The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

  10. Domestic Regulation for Periodic Safety Review of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Daesik; Ahn, Seunghoon; Auh, Geunsun; Lee, Jonghyeok

    2015-01-01

    The so-called Periodic Safety Review (PSR) has been carried out such safety assessment throughout its life, on a periodic basis. In January 2001, the Atomic Energy Act and related regulations were amended to adopt the PSR institutional scheme from IAEA Nuclear Safety Guide 50-SG-O12. At that time the safety assessment was made to review the plant safety on 10 safety factors, such as aging management and emergency planning, where the safety factor indicates the important aspects of safety of an operating NPP to be addressed in the PSR. According to this legislation, the domestic utility, the KHNP has conducted the PSR for the operating NPP of 10 years coming up from operating license date, starting since May 2000. Some revisions in the PSR rule were made to include the additional safety factors last year. This paper introduces the current status of the PSR review and regulation, in particular new safety factors and updated technical regulation. Comprehensive safety assessment for Korea Nuclear Power Plants have performed a reflecting design and procedure changes and considering the latest technology every 10 years. This paper also examined the PSR system changes in Korea. As of July 2015, reviews for PSR of 18 units have been completed, with 229 nuclear safety improvement items. And implementation have been completed for 165 of them. PSR system has been confirmed that it has contributed to improvement of plant safety. In addition, this paper examined the PSR system change in Korea

  11. Nuclear safety review for the year 2001

    International Nuclear Information System (INIS)

    2002-07-01

    The Nuclear Safety Review for the Year 2001 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts. Part 1 describes those events in 2001 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety. Part 2 describes some of the IAEA's efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2001. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2001. Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2001 was presented to the March 2002 session of IAEA's Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2002 that were considered pertinent to the discussion of events during 2001

  12. Interagency Nuclear Safety Review Panel Power System Subpanel review for the Ulysses mission

    International Nuclear Information System (INIS)

    McCulloch, W.H.

    1991-01-01

    As part of the Interagency Nuclear Safety Review Panel's assessment of the nuclear safety of NASA's Ulysses Mission to investigate properties of the sun, the Power System Subpanel has reviewed the safety analyses and risk evaluations done for the General Purpose Heat Source-Radioisotope Thermoelectric Generator which provides on-board electrical power for the spacecraft. This paper summarizes the activities and results of that review. In general, the approach taken in the primary analysis, executed by the General Electric Company under contract to the Department of Energy, and the resulting conclusions were confirmed by the review. However, the Subpanel took some exceptions and modified the calculations accordingly, producing an independent evaluation of potential releases of radioactive fuel in launch and reentry accidents. Some of the more important of these exceptions are described briefly

  13. Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    1997-01-01

    In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

  14. Aging evaluation methodology of periodic safety review in Korea

    International Nuclear Information System (INIS)

    Park, Heung-Bae; Jung, Sung-Gyu; Jin, Tae-Eun; Jeong, Ill-Seok

    2002-01-01

    In Korea plant lifetime management (PLIM) study for Kori Unit 1 has been performed since 1993. Meanwhile, periodic safety review (PSR) for all operating nuclear power plants (NPPs) has been started with Kori Unit 1 since 2000 per IAEA recommendation. The evaluation period is 10 years, and safety (evaluation) factors are 11 per IAEA guidelines as represented in table 1. The relationship between PSR factors and PLIM is also represented. Among these factors evaluation of 'management of aging' is one of the most important and difficult factor. This factor is related to 'actual condition of the NPP', 'use of experience from other nuclear NPPs and of research findings', and 'management of aging'. The object of 'management of aging' is to obtain plant safety through identifying actual condition of system, structure and components (SSCs) and evaluating aging phenomena and residual life of SSCs using operating experience and research findings. The paper describes the scope and procedure of valuation of 'management of aging', such as, screening criteria of SSCs, Code and Standards, evaluation of SSCs and safety issues as represented. Evaluating SSCs are determined using final safety analysis report (FSAR) and power unit maintenance system for Nuclear Ver. III (PUMAS/N-III). The screening criteria of SSCs are safety-related items (quality class Q), safety-impact items (quality class T), backfitting rule items (fire protection (10CFR50.48), environmental qualification (10CFR50.49), pressurized thermal shock (10CFR50.61), anticipated transient without scram (10CFR50.62), and station blackout (10CFR50.63)) and regulating authority requiring items[1∼3]. The purpose of review of Code and Standards is identifying actual condition of the NPP and evaluating aging management using effective Code and Standards corresponding to reactor facilities. Code and Standards is composed of regulating laws, FSAR items, administrative actions, regulating actions, agreement items, and other

  15. Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    2013-01-01

    The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

  16. Post Chernobyl safety review at Ontario Hydro

    International Nuclear Information System (INIS)

    Frescura, G.M.; Luxat, J.C.; Jobe, C.

    1991-01-01

    It is generally recognized that the Chernobyl Unit 4 accident did not reveal any new phenomena which had not been previously identified in safety analyses. However, the accident provided a tragic reminder of the potential consequences of reactivity initiated accidents (RIAs) and stimulated nuclear plant operators to review their safety analyses, operating procedures and various operational and management aspects of nuclear safety. Concerning Ontario Hydro, the review of the accident performed by the corporate body responsible for nuclear safety policy and by the Atomic Energy Control Board (the Regulatory Body) led to a number of specific recommendations for further action by various design, analysis and operation groups. These recommendations are very comprehensive in terms of reactor safety issues considered. The general conclusion of the various studies carried out in response to the recommendations, is that the CANDU safety design and the procedures in place to identify and mitigate the consequences of accidents are adequate. Improvements to the reliability of the Pickering NGSA shutdown system and to some aspects of safety management and staff training, although not essential, are possible and would be pursued. In support of this conclusion, the paper describes some of the studies that were carried out and discusses the findings. The first part of the paper deals with safety design aspects. While the second is concerned with operational aspects

  17. Safety evaluation report related to the license renewal and power increase for the National Bureau of Standards reactor (Docket No. 50-184)

    International Nuclear Information System (INIS)

    Bernard, H.

    1984-03-01

    Supplement 1 to the Safety Evaluation Report (SER) related to the renewal of the operating license and for a power increase (10 MWt to 20 MWt) for the research reactor at the National Bureau of Standards (NBS) facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports on the review of the licensee's emergency plan, which had not been reviewed at the time the Safety Evaluation Report (NUREG-1007) was published, and the review of the NBS application by the Advisory Committee on Reactor Safeguards, which was completed subsequent to the publication of the SER

  18. IRIS Toxicological Review of Tert-Butyl Alcohol (Tert-Butanol) (External Review Draft)

    Science.gov (United States)

    The IRIS Toxicological Review of tert-Butyl Alcohol (tert-Butanol) was released for external peer review in June 2017. EPA’s Science Advisory Board’s (SAB) Chemical Assessment Advisory Committee (CAAC) will conduct a peer review of the scientific basis supporting ...

  19. Review of Public Safety in Viewpoint of Complex Networks

    International Nuclear Information System (INIS)

    Gai Chengcheng; Weng Wenguo; Yuan Hongyong

    2010-01-01

    In this paper, a brief review of public safety in viewpoint of complex networks is presented. Public safety incidents are divided into four categories: natural disasters, industry accidents, public health and social security, in which the complex network approaches and theories are need. We review how the complex network methods was developed and used in the studies of the three kinds of public safety incidents. The typical public safety incidents studied by the complex network methods in this paper are introduced, including the natural disaster chains, blackouts on electric power grids and epidemic spreading. Finally, we look ahead to the application prospects of the complex network theory on public safety.

  20. Queensland Energy Advisory Council's, annual review and energy statistics, 1982

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    Queensland Energy Advisory Council (QEAC) role covers all forms of energy including renewable, non-renewable, commercialised and non-commercialised energy forms or proposals. While coal developments and electricity matters are discussed and monitored at meetings, the Mines Department and the State Electricity Commission, respectively, retain responsibility for most aspects in these energy sectors. In such cases QEAC's expertise and role is limited and is advisory. In other areas such as energy conservation, management of liquid fuel emergencies, natural gas supply and demand, solar energy, coal conversion, and ethanol production, QEAC made a significant contribution to policy development in 1981/82.

  1. The necessity of periodic fire safety review

    International Nuclear Information System (INIS)

    Mowrer, D.S.

    1998-01-01

    Effective fire safety requires the coordinated integration of many diverse elements. Clear fire safety objectives are defined by plant management and/or regulatory authorities. Extensive and time-consuming systematic analyses are performed. Fire safety features (both active and passive) are installed and maintained, and administrative programs are established and implemented to achieve the defined objectives. Personnel are rigorously trained. Given the time, effort and monetary resources expended to achieve a specific level of fire safety, conducting periodic assessments to verify that the specified level of fire safety has been achieved and is maintained is a matter of common sense. Periodic fire safety reviews and assessment play an essential role in assuring continual nuclear safety in the world's power plants

  2. Nuclear safety review for the year 2000

    International Nuclear Information System (INIS)

    2001-06-01

    The nuclear safety review for the year 2000 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts: Part 1 describes those events in 2000 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety; Part 2 describes some of the IAEA efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2000. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2000; Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2000 was presented to the March 2001 session of the IAEA Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2001 that were considered pertinent to the discussion of events during 2000. In such cases, a note containing the more recent information has been provided in the form of a footnote

  3. Intergrated plant safety assessment. Systematic evaluation program. Palisades plant, Consumers Power Company, Docket No. 50-255. Final report

    International Nuclear Information System (INIS)

    1982-10-01

    The Nuclear Regulatory Commission (NRC) has published its Final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0820), under the scope of the Systematic Evaluation Program (SEP), for Consumers Power Company's Palisades Plant located in Covert, Van Buren County, Michigan. The SEP was initiated by the NRC to review the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed under the SEP for the Palisades Plant. The review has provided for (1) as assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when all supplements to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in April 1982

  4. 76 FR 16842 - National Endowment for the Arts; Arts Advisory Panel

    Science.gov (United States)

    2011-03-25

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES National Endowment for the Arts; Arts Advisory..., notice is hereby given that one meeting of the Arts Advisory Panel to the National Council on the Arts... (ending time is approximate): Arts Education (application review): April 14, 2011, by teleconference. This...

  5. 76 FR 70510 - National Endowment for the Arts; Arts Advisory Panel

    Science.gov (United States)

    2011-11-14

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES National Endowment for the Arts; Arts Advisory..., notice is hereby given that ten meetings of the Arts Advisory Panel to the National Council on the Arts... (ending times are approximate): Arts Education (application review): November 29-December 2, 2011 in Room...

  6. IRIS Toxicological Review of Ethyl Tertiary Butyl Ether (ETBE) (External Review Draft)

    Science.gov (United States)

    The IRIS Toxicological Review of Ethyl Tertiary Butyl Ether (ETBE) was released for external peer review in June 2017. EPA’s Science Advisory Board’s (SAB) Chemical Assessment Advisory Committee (CAAC) will conduct a peer review of the scientific basis supporting the ETB...

  7. Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 1. Project Reviews A-F

    International Nuclear Information System (INIS)

    1985-04-01

    This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume contains project reviews arranged alphabetically from A to F

  8. Occupational Safety Review of High Technology Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee Cadwallader

    2005-01-31

    This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

  9. IAEA Operational Safety Team Reviews Cattenom Nuclear Power Plant

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has reviewed operational safety at France's Cattenom Nuclear Power Plant (NPP) noting a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled an international team of experts at the request of the Government of France to conduct an Operational Safety Review (OSART) of Cattenom NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 14 November to 1 December 2011. The team was made up of experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Japan, Russia, Slovakia, South Africa, Sweden, Ukraine, the United Kingdom and the IAEA. The team at Cattenom conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. Cattenom is the first plant in Europe to voluntarily undertake a Severe Accident Management review during an OSART review. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: Sheets are displayed in storage areas where combustible material is present - these sheets are updated readily and accurately by the area owner to ensure that the fire limits are complied with; A simple container is attached to the neutron source handling device to ensure ease and safety of operations and reduce possible radiation exposure during use

  10. Desonide: a review of formulations, efficacy and safety.

    Science.gov (United States)

    Kahanek, Nr; Gelbard, Cg; Hebert, Aa

    2008-07-01

    Desonide is a low-potency topical corticosteroid that has been used for decades in the treatment of steroid-responsive dermatoses. The favorable safety profile of this topical agent makes it ideal for patients of all ages. This article provides a review of desonide's history, pharmacodynamic properties, vehicle technology, efficacy and safety. Randomized controlled trials, as well as open-label and non-comparative studies, case series and reports, experimental models, and data from the Galderma pharmacovigiliance program were reviewed in order to address the clinical efficacy and safety of desonide. Clinical efficacy and safety have been proven in multiple clinical trials. In addition to cream, lotion and ointment formulations, the recently developed hydrogel and foam preparations have increased desonide's versatility and patient tolerability.

  11. IAEA activities to prepare safety codes and guides for thermal neutron nuclear power plants

    International Nuclear Information System (INIS)

    Iansiti, E.

    1977-01-01

    In accordance with the programme presented to, and endorsed by, the eighteenth General Conference in September 1974, the IAEA is now developing a complete set of safety codes and guides that will represent recommendations for the safety of thermal neutron power plants. The safety codes outline the minimum requirements for achieving this safety, and the safety guides set forth the criteria, procedures and methods to implement the safety codes. The whole programme is directed towards the five areas of Governmental Organization, Siting, Design, Operation, and Quality Assurance. One Scientific Secretary from the Agency Secretariat is responsible for each of these areas and a Co-ordinator takes care of common problems. For the development of each of these documents a working group of a few world experts is first convened which prepare a preliminary draft. This draft is then reviewed by a larger, international Technical Review Committee (one for each of the five areas) and a subsequent review by the Senior Advisory Group - with representatives from 20 states - ensures that the document is well coordinated within the programme. At this stage, it is sent to Member States for comments. The Technical Review Committee concerned is reconvened to integrate these comments into the document, and, after a final review by the Senior Advisory Group, the document is ready for transmission to the Director General of the Agency for endorsement and publication. A preliminary to this procedure is the collation by the Secretariat of large amounts of information submitted by Member States so that the first draft is really based on a very complete knowledge of what is done in each area all over the world. This collation frequently reveals differences in approach which are not random but due, rather, to the local conditions and the types of reactors. These differences must be harmonized in the documents produced without detracting from the effectiveness of the code or guide. The whole

  12. 76 FR 28218 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2011-05-16

    ...: Red Lion Hotel, 1101 North Columbia Center Boulevard, Kennewick, WA 99336. FOR FURTHER INFORMATION... Committee; Health, Safety and Environmental Protection Committee; Public Involvement Committee; and Budgets... Priorities. [cir] Hanford Advisory Board Budget. [cir] Process Discussions: [dec222] Issue Managers. [dec222...

  13. 76 FR 81542 - National Endowment for the Arts; Arts Advisory Panel

    Science.gov (United States)

    2011-12-28

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES National Endowment for the Arts; Arts Advisory..., notice is hereby given that a meeting of the Arts Advisory Panel to the National Council on the Arts will... (ending times are approximate): Media Arts (application review): January 24-26, 2012 in Room 716. A...

  14. 78 FR 11902 - Review of Gun Safety Technologies

    Science.gov (United States)

    2013-02-20

    ... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1615] Review of Gun Safety...'s Plan to reduce gun violence released on January 16, 2013, the U.S. Department of Justice, Office... emerging gun safety technologies and plans to issue a report on the availability and use of those...

  15. Packaging review guide for reviewing safety analysis reports for packagings: Revision 1

    International Nuclear Information System (INIS)

    Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

    1988-10-01

    The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs

  16. Safety review of experiments at Albuquerque Operations Office

    International Nuclear Information System (INIS)

    Elliott, K.

    1984-01-01

    The Department of Energy (DOE) Albuquerque Operations Office is responsible for the safety overview of nuclear reactor and critical assembly facilities at Sandia National Laboratories, Los Alamos National Laboratory, and the Rocky Flats Plant. The important safety concerns with these facilities involve the complex experiments that are performed, and that is the area emphasized. A determination is made by the Albuquerque Office (AL) with assistance from DOE/OMA whether or not a proposed experiment is an unreviewed safety question. Meetings are held with the contractor to resolve and clarify questions that are generated during the review of the proposed experiment. The AL safety evaluation report is completed and any recommendations are discussed. Prior to the experiment a preoperational appraisal is performed to assure that personnel, procedures, and equipment are in readiness for operations. During the experiment, any abnormal condition is reviewed in detail to determine any safety concerns

  17. Review of the Fusion Theory and Computing Program. Fusion Energy Sciences Advisory Committee (FESAC)

    International Nuclear Information System (INIS)

    Antonsen, Thomas M.; Berry, Lee A.; Brown, Michael R.; Dahlburg, Jill P.; Davidson, Ronald C.; Greenwald, Martin; Hegna, Chris C.; McCurdy, William; Newman, David E.; Pellegrini, Claudio; Phillips, Cynthia K.; Post, Douglass E.; Rosenbluth, Marshall N.; Sheffield, John; Simonen, Thomas C.; Van Dam, James

    2001-01-01

    At the November 14-15, 2000, meeting of the Fusion Energy Sciences Advisory Committee, a Panel was set up to address questions about the Theory and Computing program, posed in a charge from the Office of Fusion Energy Sciences (see Appendix A). This area was of theory and computing/simulations had been considered in the FESAC Knoxville meeting of 1999 and in the deliberations of the Integrated Program Planning Activity (IPPA) in 2000. A National Research Council committee provided a detailed review of the scientific quality of the fusion energy sciences program, including theory and computing, in 2000.

  18. Standard review plan for reviewing safety analysis reports for dry metallic spent fuel storage casks

    International Nuclear Information System (INIS)

    1988-01-01

    The Cask Standard Review Plan (CSRP) has been prepared as guidance to be used in the review of Cask Safety Analysis Reports (CSARs) for storage packages. The principal purpose of the CSRP is to assure the quality and uniformity of storage cask reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The CSRP also sets forth solutions and approaches determined to be acceptable in the past by the NRC staff in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a CSAR does not have to follow the solutions or approaches presented in the CSRP. However, applicants should recognize that the NRC staff has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches

  19. Packaging review guide for reviewing safety analysis reports for packagings: Revision 0

    International Nuclear Information System (INIS)

    Fischer, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

    1987-09-01

    The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. These certification review policies and procedures are established to ensure that DOE packaging designs and operations meet safety criteria at least equivalent to the standards prescribed by the Nuclear Regulatory Commission (NRC) certification process for packaging. The Packaging Review Guide (PRG) is not a DOE order, but has been prepared as guidance for the Packaging Certification Staff (PCS) under the Certifying Official, Office of Security Evaluations, or designated representatives. The principal purpose of the PRG is to assure the quality and uniformity of PCS reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The PRG also sets forth solutions and approaches determined to be acceptable in the past by the PCS in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented in the PRG. However, applicants should recognize that the PCS has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches. Finally, it is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 7 refs., 15 figs., 14 tabs

  20. Safe management of the operating lifetimes of nuclear power plants. INSAG-14. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    2014-01-01

    The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. The present report by INSAG deals with a general approach to the safe management of the operating lifetimes of nuclear power plants. It responds to the concerns about maintaining adequate safety levels at ageing plants, even beyond their design lifetimes. Maintaining adequate safety levels implies first and foremost stringent control of equipment ageing, consistent with the design safety bases of the plants. However, as stated in the 75-INSAG-3 report, 'Basic Safety Principles for Nuclear Power Plants', nuclear safety requires a continuing quest for excellence; this implies enhancinuest for excellence; this implies enhancing the safety levels of operating nuclear power plants as far as reasonably practicable, with due account taken of experience and advancement in knowledge. Moreover, in view of the present situation of the nuclear industry, it may become difficult to maintain adequate competences in many countries with nuclear power programmes. These topics are considered in this latest INSAG report and released to a wider audience

  1. Safe management of the operating lifetimes of nuclear power plants. INSAG-14. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    1999-01-01

    The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. The present report by INSAG deals with a general approach to the safe management of the operating lifetimes of nuclear power plants. It responds to the concerns about maintaining adequate safety levels at ageing plants, even beyond their design lifetimes. Maintaining adequate safety levels implies first and foremost stringent control of equipment ageing, consistent with the design safety bases of the plants. However, as stated in the 75-INSAG-3 report, 'Basic Safety Principles for Nuclear Power Plants', nuclear safety requires a continuing quest for excellence; this implies enhancing the safety levels of operating nuclear power plants as far as reasonably practicable, with due account taken of experience and advancement in knowledge. Moreover, in view of the present situation of the nuclear industry, it may become difficult to maintain adequate competences in many countries with nuclear power programmes. These topics are considered in this latest INSAG report and released to a wider audience

  2. 76 FR 22394 - Science Advisory Board Staff Office; Notification of a Public Teleconferences of the Science...

    Science.gov (United States)

    2011-04-21

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9298-6] Science Advisory Board Staff Office; Notification of a Public Teleconferences of the Science Advisory Board Panel for Review of Hydraulic Fracturing... EPA Science Advisory Board can be found at the EPA SAB Web site at http://www.epa.gov/sab . Any...

  3. 76 FR 34139 - Northeast Corridor Safety Committee; Meeting Postponement

    Science.gov (United States)

    2011-06-10

    .... 2] Northeast Corridor Safety Committee; Meeting Postponement AGENCY: Federal Railroad Administration... announced the first meeting of the Northeast Corridor Safety Committee, a Federal Advisory Committee... future date. DATES: The meeting of the Northeast Corridor Safety Committee scheduled to commence on...

  4. Review on JMTR safety design for LEU core conversion

    International Nuclear Information System (INIS)

    Komori, Yoshihiro; Yokokawa, Makoto; Saruta, Toru; Inada, Seiji; Sakurai, Fumio; Yamamoto, Katsumune; Oyamada, Rokuro; Saito, Minoru

    1993-12-01

    Safety of the JMTR was fully reviewed for the core conversion to low enriched uranium fuel. Fundamental policies for the JMTR safety design were reconsidered based on the examination guide for safety design of test and research reactors, and safety of the JMTR was confirmed. This report describes the safety design of the JMTR from the viewpoint of major functions for reactor safety. (author)

  5. [Improving patient safety through voluntary peer review].

    Science.gov (United States)

    Kluge, S; Bause, H

    2015-01-01

    The intensive care unit (ICU) is one area of the hospital in which processes and communication are of primary importance. Errors in intensive care units can lead to serious adverse events with significant consequences for patients. Therefore quality and risk-management are important measures when treating critically ill patients. A pragmatic approach to support quality and safety in intensive care is peer review. This approach has gained significant acceptance over the past years. It consists of mutual visits by colleagues who conduct standardised peer reviews. These reviews focus on the systematic evaluation of the quality of an ICU's structure, its processes and outcome. Together with different associations, the State Chambers of Physicians and the German Medical Association have developed peer review as a standardized tool for quality improvement. The common goal of all stakeholders is the continuous and sustainable improvement in intensive care with peer reviews significantly increasing and improving communication between professions and disciplines. Peer reviews secure the sustainability of planned change processes and consequently lead the way to an improved culture of quality and safety.

  6. 76 FR 29722 - Elko Resource Advisory Committee

    Science.gov (United States)

    2011-05-23

    ... (Pub. L. 110-343) (the Act) and operates in compliance with the Federal Advisory Committee Act. The...- Determination Act; (2) Review roles of RAC committee members and Committee Chairman; (3) Overview of project...

  7. Using systematic review in occupational safety and health.

    Science.gov (United States)

    Howard, John; Piacentino, John; MacMahon, Kathleen; Schulte, Paul

    2017-11-01

    Evaluation of scientific evidence is critical in developing recommendations to reduce risk. Healthcare was the first scientific field to employ a systematic review approach for synthesizing research findings to support evidence-based decision-making and it is still the largest producer and consumer of systematic reviews. Systematic reviews in the field of occupational safety and health are being conducted, but more widespread use and adoption would strengthen assessments. In 2016, NIOSH asked RAND to develop a framework for applying the traditional systematic review elements to the field of occupational safety and health. This paper describes how essential systematic review elements can be adapted for use in occupational systematic reviews to enhance their scientific quality, objectivity, transparency, reliability, utility, and acceptability. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

  8. Development and Validation of a Short-Form Safety Net Medical Home Scale.

    Science.gov (United States)

    Nocon, Robert S; Gunter, Kathryn E; Gao, Yue; Lee, Sang Mee; Chin, Marshall H

    2017-12-01

    To develop a short-form Safety Net Medical Home Scale (SNMHS) for assessing patient-centered medical home (PCMH) capability in safety net clinics. National surveys of federally qualified health centers (FQHCs). Interviews with FQHC directors. We constructed three short-form SNMHS versions and examined correlations with full SNMHS and related primary care assessments. We tested usability with FQHC directors and reviewed scale development with an advisory group. Federally qualified health center surveys were administered in 2009 and 2013, by mail and online. Usability testing was conducted through telephone interviews with FQHC directors in 2013. Six-, 12-, and 18-question short-form SNMHS versions had Pearson correlations with full scale of 0.84, 0.92, and 0.96, respectively. All versions showed a level of convergent validity with other primary care assessment scales comparable to the full SNMHS. User testers found short forms to be low-burden, though missing some PCMH concepts. Advisory group members expressed caution over missing concepts and appropriate use of short-form self-assessments. Short-form versions of SNMHS showed strong correlations with full scale and may be useful for brief assessment of safety net PCMH capability. Each short-form SNMHS version may be appropriate for different research, quality improvement, and assessment purposes. © Health Research and Educational Trust.

  9. 78 FR 60884 - Vaccines and Related Biological Products Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2013-10-02

    ...] Vaccines and Related Biological Products Advisory Committee; Notice of Meeting AGENCY: Food and Drug... public. Name of Committee: Vaccines and Related Biological Products Advisory Committee. General Function... Immunoregulation, Division of Viral Products, Office of Vaccines Research and Review, Center for Biologics...

  10. 76 FR 13646 - Vaccines and Related Biological Products Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2011-03-14

    ...] Vaccines and Related Biological Products Advisory Committee; Notice of Meeting AGENCY: Food and Drug... public. Name of Committee: Vaccines and Related Biological Products Advisory Committee. General Function... Polysaccharides, Division of Bacterial, Parasitic, and Allergenic Products, Office of Vaccines Research and Review...

  11. 76 FR 44016 - Vaccines and Related Biological Products Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2011-07-22

    ...] Vaccines and Related Biological Products Advisory Committee; Notice of Meeting AGENCY: Food and Drug... public. Name of Committee: Vaccines and Related Biological Products Advisory Committee. General Function... Allergenic Products, Office of Vaccines Research and Review, Center for Biologics Evaluation and Research...

  12. 76 FR 6784 - Science Advisory Board Staff Office; Notification of Two Public Teleconferences of the Science...

    Science.gov (United States)

    2011-02-08

    ... Two Public Teleconferences of the Science Advisory Board Dioxin Review Panel AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces... concerning the EPA Science Advisory Board can be found on the EPA Web site at http://www.epa.gov/sab...

  13. 76 FR 22100 - Notification of a Public Teleconference of the Science Advisory Board; Drinking Water Committee...

    Science.gov (United States)

    2011-04-20

    ... Science Advisory Board; Drinking Water Committee Augmented for the Review of the Effectiveness of Partial...: The EPA Science Advisory Board (SAB) Staff Office announces a public teleconference of the SAB... EPA Science Advisory Board can be found on the EPA Web site at http://www.epa.gov/sab . SUPPLEMENTARY...

  14. 76 FR 4660 - Science Advisory Board Staff Office; Notification of a Public Teleconference of the Science...

    Science.gov (United States)

    2011-01-26

    ... a Public Teleconference of the Science Advisory Board Lead Review Panel AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces... information concerning the EPA Science Advisory Board can be found on the EPA Web site at http://www.epa.gov...

  15. Standard Review Plan for the review of safety analysis reports for nuclear power plants: LWR edition

    International Nuclear Information System (INIS)

    1987-06-01

    The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The safety review is primarily based on the information provided by an applicant in a Safety Analysis Report (SAR). The SAR must be sufficiently detailed to permit the staff to determine whether the plant can be built and operated without undue risk to the health and safety of the public. The SAR is the principal document in which the applicant provides the information needed to understand the basis upon which this conclusion has been reached. The individual SRP sections address, in detail, who performs the review, the matters that are reviewed, the basis for review, how the review is accomplished, and the conclusions that are sought. The safety review is performed by 25 primary branches. One of the objectives of the SRP is to assign the review responsibilities to the various branches and to define the sometimes complex interfaces between them. Each SRP section identifies the branch that has the primary review responsibility for that section. In some review areas the primary branch may require support, and the branches that are assigned these secondary review responsibilities are also identified for each SRP section

  16. Immunization safety review: influenza vaccines and neurological complications

    National Research Council Canada - National Science Library

    Stratton, Kathleen R

    ..., unlike other vaccines. The Immunization Safety Review committee reviewed the data on influenza vaccine and neurological conditions and concluded that the evidence favored rejection of a causal relationship...

  17. 75 FR 26284 - National Endowment for the Arts; Arts Advisory Panel

    Science.gov (United States)

    2010-05-11

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES National Endowment for the Arts; Arts Advisory..., notice is hereby given that nine meetings of the Arts Advisory Panel to the National Council on the Arts... meeting, from 3 p.m. to 3:30 p.m. EDT, will be closed. Folk and Traditional Arts (application review...

  18. IAEA Completes First Ever Corporate Safety Review, at Czech Republic's CEZ

    International Nuclear Information System (INIS)

    2013-01-01

    Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of corporate safety performance at CEZ a.s., the largest national electricity company in the Czech Republic. For the first time since the Agency launched its Operational Safety Review Team (OSART) missions in 1982, the team addressed corporate aspects of a company in relation to nuclear safety. The team noted a series of good practices and proposed recommendations to strengthen some safety measures. Assembled at the request of the Government of the Czech Republic, the first ''Corporate OSART'' review, which ran from 30 September to 9 October 2013, addressed corporate aspects necessary to ensure the safe operation of the Dukovany and Temelin Nuclear Power Plants (NPPs). The mission included experts from Finland, France, Romania, USA and the IAEA. OSART services aim to improve operational safety at nuclear facilities by objectively assessing safety performance using the IAEA's Safety Standards and proposing recommendations for improvement where appropriate. The missions serve as a channel to exchange information and experience and provide Member States with good practices. A ''Corporate OSART'' is an OSART mission organized to review those centralized functions of the corporate organization of a utility with multiple nuclear plant sites and conventional plant sites that affect all the operational safety aspects of the nuclear power plants of this utility. ''OSART missions are one of the most important tools of the Agency to ensure better and wider implementation of the IAEA Safety Standards,'' said Denis Flory, Deputy Director General in the IAEA Department of Nuclear Safety and Security. ''Since 1982, we have conducted close to 200 safety review missions around the globe; however, this mission is the first of its kind because we focused on the corporate performance that is a necessity for a safe operation of NPPs,'' Flory added

  19. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    International Nuclear Information System (INIS)

    Oh, Kyemin; Kang, Myoung-suk; Heo, Gyunyoung; Kim, Hyoung-chan

    2014-01-01

    's viewpoint in interactive manner: qualitative safety features review (QSR), phenomena identification and ranking table (PIRT), objective provision tree (OPT), probabilistic safety assessment (PSA), and deterministic and phenomenological analysis (DPA). Considering the design phase of K-DEMO, the current study focused on the PIRT process with the fusion safety advisory group in South Korea

  20. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Kyemin; Kang, Myoung-suk [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Kim, Hyoung-chan [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of)

    2014-10-15

    's viewpoint in interactive manner: qualitative safety features review (QSR), phenomena identification and ranking table (PIRT), objective provision tree (OPT), probabilistic safety assessment (PSA), and deterministic and phenomenological analysis (DPA). Considering the design phase of K-DEMO, the current study focused on the PIRT process with the fusion safety advisory group in South Korea.

  1. 77 FR 3780 - Vaccines and Related Biological Products Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-01-25

    ...] Vaccines and Related Biological Products Advisory Committee; Notice of Meeting AGENCY: Food and Drug... public. Name of Committee: Vaccines and Related Biological Products Advisory Committee. General Function... Products, Office of Vaccines Research and Review, Center for Biologics Evaluation and Research, FDA. The...

  2. 78 FR 20663 - Vaccines and Related Biological Products Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2013-04-05

    ...] Vaccines and Related Biological Products Advisory Committee; Notice of Meeting AGENCY: Food and Drug... public. Name of Committee: Vaccines and Related Biological Products Advisory Committee. General Function..., Office of Vaccines Research and Review, Center for Biologics Evaluation and Research, FDA. FDA intends to...

  3. 76 FR 55397 - Vaccines and Related Biological Products Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2011-09-07

    ...] Vaccines and Related Biological Products Advisory Committee; Notice of Meeting AGENCY: Food and Drug... public. Name of Committee: Vaccines and Related Biological Products Advisory Committee. General Function... Laboratory of Method Development, Division of Viral Products, Office of Vaccines Research and Review, Center...

  4. 76 FR 37371 - Ocean Energy Safety Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2011-06-27

    ... Advisory Committee will meet at the Astor Crowne Plaza Hotel in New Orleans, Louisiana. DATES: Wednesday...: The Astor Crowne Plaza Hotel, 739 Canal Street, New Orleans, Louisiana 70130, telephone (504) 962-0500... Budget's Circular No. A-63, Revised. Dated: June 22, 2011. Michael R. Bromwich, Director, Bureau of Ocean...

  5. Nuclear safety education and training network

    International Nuclear Information System (INIS)

    Bastos, J.; Ulfkjaer, L.

    2004-01-01

    In March 2001, the Secretariat convened an Advisory Group on Education and Training in nuclear safety. The Advisory Group considered structure, scope and means related to the implementation of an IAEA Programme on Education and Training . A strategic plan was agreed and the following outputs were envisaged: 1. A Training Support Programme in nuclear safety, including a standardized and harmonized approach for training developed by the IAEA and in use by Member States. 2. National and regional training centres, established to support sustainable national nuclear safety infrastructures. 3. Training material for use by lecturers and students developed by the IAEA in English and translated to other languages. The implementation of the plan was initiated in 2002 emphasizing the preparation of training materials. In 2003 a pilot project for a network on Education and Training in Asia was initiated

  6. Review of probabilistic safety assessments by regulatory bodies

    International Nuclear Information System (INIS)

    2002-01-01

    This report provides guidance to assist regulatory bodies in carrying out reviews of the PSAs produced by utilities. In following this guidance, it is important that the regulatory body is able to satisfy itself that the PSA has been carried out to an acceptable standard and that it can be used for its intended applications. The review process becomes an important phase in determining the acceptability of the PSA since this provides a degree of assurance of the PSA scope, validity and limitations, as well as a better understanding of plants themselves. This report is also intended to assist technical experts managing or performing PSA reviews. A particular aim is to promote a standardized framework, terminology and form of documentation for the results of PSA reviews. The information presented in this report supports IAEA Safety Guide No. GS-G-1.2. Recommendations on the scope and methods to be used by the utility in the preparation of a PSA study is provided in IAEA Safety Guide No. NSG- 1.2. Information on these Safety Guides and other IAEA safety standards for nuclear power plants can be found on the following Internet site: http://www.iaea.org/ns/coordinet. The scope of this report covers the review of Level 1, 2 and 3 PSAs for event sequences occurring in all modes of plant operation (including full power, low power and shutdown). Where the scope of the analysis is narrower than this, a subset of the guidance can be identified and used. Information is provided on carrying out the review of a PSA throughout the PSA production process, i.e. from the initial decision to carry out the PSA through to the completion of the study and the production of the final PSA report. However, the same procedure can be applied to a completed PSA or to one already in progress. As a result of the performance of a PSA, changes to the design or operation of the plant are often identified that would increase the level of safety. This might include the addition of further safety

  7. Plan for research to improve the safety of light-water nuclear power plants

    International Nuclear Information System (INIS)

    1978-03-01

    This is the U.S. Nuclear Regulatory Commission's first annual report to Congress on recommendations for research on improving the safety of light-water nuclear power plants. Suggestions for reactor safety research were identified in, or received from, various sources, including the Advisory Committee on Reactor Safeguards, the NRC regulatory staff, and the consultants to the Research Review Group. After an initial screening to eliminate those not related to improved reactor safety, all the suggestions were consolidated into research topics. It is recommended that the following research projects be carried out: alternate containment concepts, especially vented containments; alternate decay heat removal concepts, especially add-on bunkered systems; alternate emergency core cooling concepts; improved in-plant accident response; and advanced seismic designs

  8. A compilation of reports of the Advisory Committee on Reactor Safeguards, 1990 annual

    International Nuclear Information System (INIS)

    1991-04-01

    This compilation contains 31 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission or to the Executive Director for Operations during calendar year 1990. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subject. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area

  9. The complications of controlling agency time discretion: FDA review deadlines and postmarket drug safety.

    Science.gov (United States)

    Carpenter, Daniel; Chattopadhyay, Jacqueline; Moffitt, Susan; Nall, Clayton

    2012-01-01

    Public agencies have discretion on the time domain, and politicians deploy numerous policy instruments to constrain it. Yet little is known about how administrative procedures that affect timing also affect the quality of agency decisions. We examine whether administrative deadlines shape decision timing and the observed quality of decisions. Using a unique and rich dataset of FDA drug approvals that allows us to examine decision timing and quality, we find that this administrative tool induces a piling of decisions before deadlines, and that these “just-before-deadline” approvals are linked with higher rates of postmarket safety problems (market withdrawals, severe safety warnings, safety alerts). Examination of data from FDA advisory committees suggests that the deadlines may impede quality by impairing late-stage deliberation and agency risk communication. Our results both support and challenge reigning theories about administrative procedures, suggesting they embody expected control-expertise trade-offs, but may also create unanticipated constituency losses.

  10. IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

  11. Patient safety culture in care homes for older people: a scoping review

    Directory of Open Access Journals (Sweden)

    Emily Gartshore

    2017-11-01

    Full Text Available Abstract Background In recent years, there has been an increasing focus on the role of safety culture in preventing incidents such as medication errors and falls. However, research and developments in safety culture has predominantly taken place in hospital settings, with relatively less attention given to establishing a safety culture in care homes. Despite safety culture being accepted as an important quality indicator across all health and social care settings, the understanding of culture within social care settings remains far less developed than within hospitals. It is therefore important that the existing evidence base is gathered and reviewed in order to understand safety culture in care homes. Methods A scoping review was undertaken to describe the availability of evidence related to care homes’ patient safety culture, what these studies focused on, and identify any knowledge gaps within the existing literature. Included papers were each reviewed by two authors for eligibility and to draw out information relevant to the scoping review. Results Twenty-four empirical papers and one literature review were included within the scoping review. The collective evidence demonstrated that safety culture research is largely based in the USA, within Nursing Homes rather than Residential Home settings. Moreover, the scoping review revealed that empirical evidence has predominantly used quantitative measures, and therefore the deeper levels of culture have not been captured in the evidence base. Conclusions Safety culture in care homes is a topic that has not been extensively researched. The review highlights a number of key gaps in the evidence base, which future research into safety culture in care home should attempt to address.

  12. IAEA Completes Safety Review at Czech Nuclear Power Plant

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: An international team of nuclear safety experts, led by the International Atomic Energy Agency (IAEA), today completed a review of safety practices at Temelin Nuclear Power Station in the Czech Republic. The team highlighted the Power Plant's good practices and also recommended improvements to some safety measures. At the request of the Government of the Czech Republic, the IAEA assembled a team of nuclear installation safety experts to send an Operational Safety Review Team (OSART) to the Power Plant, and the mission was conducted from 5 to 22 November 2012. The team was comprised of experts from Brazil, Hungary, Slovakia, South Africa, Sweden, Ukraine and the United Kingdom. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the Plant's overall safety status. The team at Temelin conducted an in-depth review of the functions essential to the safe operation of the Power Plant, which are under the responsibility of the site's management. The review covered the areas of management, organization and administration; operations; maintenance; technical support; operating experience; radiation protection; chemistry; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of potential application elsewhere. Examples include the following: - The Power Plant has adopted effective computer software to improve the efficiency of the plant to prepare and isolate equipment for maintenance; - The Power Plant undertakes measures to control precisely the chemical parameters that limit corrosion in the reactor's coolant system, which in turn reduce radiation exposure to the workforce; and - The Temelin

  13. 75 FR 49457 - Amador County Resource Advisory Committee

    Science.gov (United States)

    2010-08-13

    ... and Community Self-Determination Act (Pub. L. 110-343) and in compliance with the Federal Advisory Committee Act. The RAC will review project proposals submitted by the Forest Service and the public, listen... meeting the RAC will review project proposals submitted by the Forest Service and the public, listen to...

  14. Independent peer review of nuclear safety computer codes

    International Nuclear Information System (INIS)

    Boyack, B.E.; Jenks, R.P.

    1993-01-01

    A structured, independent computer code peer-review process has been developed to assist the US Nuclear Regulatory Commission (NRC) and the US Department of Energy in their nuclear safety missions. This paper describes a structured process of independent code peer review, benefits associated with a code-independent peer review, as well as the authors' recent peer-review experience. The NRC adheres to the principle that safety of plant design, construction, and operation are the responsibility of the licensee. Nevertheless, NRC staff must have the ability to independently assess plant designs and safety analyses submitted by license applicants. According to Ref. 1, open-quotes this requires that a sound understanding be obtained of the important physical phenomena that may occur during transients in operating power plants.close quotes The NRC concluded that computer codes are the principal products to open-quotes understand and predict plant response to deviations from normal operating conditionsclose quotes and has developed several codes for that purpose. However, codes cannot be used blindly; they must be assessed and found adequate for the purposes they are intended. A key part of the qualification process can be accomplished through code peer reviews; this approach has been adopted by the NRC

  15. 77 FR 26822 - Pipeline Safety: Verification of Records

    Science.gov (United States)

    2012-05-07

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0068] Pipeline Safety: Verification of Records AGENCY: Pipeline and Hazardous Materials... issuing an Advisory Bulletin to remind operators of gas and hazardous liquid pipeline facilities to verify...

  16. Nuclear Installation Safety: General Observations and Trends from IAEA Peer Reviews

    International Nuclear Information System (INIS)

    Rzentkowski, G.

    2016-01-01

    The Safety Review Services (SRSs) for nuclear installations address the needs of Member States at all stages of installations’ lifecycle. SRSs are based on the IAEA Safety Standards and are provided on Member States’ request to peer review national regulatory frameworks and safety provisions for nuclear installations. They result in recommendations and suggestions to improve national regulations and operational safety, and serve to exert peer pressure to ensure that that every Member State with nuclear installations recognizes its safety responsibility and the need to comply with the IAEA Safety Standards. This presentation provides an overview of SRSs for Nuclear Installations, including their structure and main subject areas. The presentation also summarizes general findings and trends which clearly demonstrate that there is continuous improvement in regulation of nuclear installations and in safety of their operation. Nevertheless, there is the need to further enhance the efficiency and effectiveness of SRSs through review of the overall governance model and service delivery to better serve the needs of Member States. The presentation points out some areas of improvements which have already been implemented or are being considered for implementation. Just as important, SRSs are conducted by teams of experts from around the world to strengthening international cooperation, ensure diversity and impartiality, and improve the overall quality of the safety review being conducted. The review team members are also provided with the opportunity for mutual learning and sharing good practices among themselves and with the Member State undergoing the review. As a result, SRAs play an important role in a quest to harmonize regulatory requirements and approaches globally. (author)

  17. Safety-evaluation report related to the final design of the Standard Nuclear Steam Supply Reference System - CESSAR System 80. Docket No. STN 50-470

    International Nuclear Information System (INIS)

    1983-03-01

    Supplement No. 1 to the Safety Evaluation Report for the application filed by Combustion Engineering, Inc. for a Final Design Approval for the Combustion Engineering Standard Safety Analysis Report (STN 50-470) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation by providing: (1) the evaluation of additional information submitted by the applicant since the Safety Evaluation Report was issued, (2) the evaluation of the matters the staff had under review when the Safety Evaluation Report was issued, and (3) the response to comments made by the Advisory Committee on Reactor Safeguards

  18. Deployment and Field Evaluation of In-Vehicle Traffic Signal Advisory System (ITSAS

    Directory of Open Access Journals (Sweden)

    Joyoung Lee

    2017-06-01

    Full Text Available This research evaluates the impact of In-vehicle Signal Advisory System (ITSAS on signalized arterial. ITSAS provides individual drivers equipped with a mobile communication device with advisory speed information enabling to minimize the time delay and fuel consumption when crossing intersection. Given the instantaneous vehicular driving information, such as position, speed, and acceleration rate, ITSAS produces advisory speed information by taking into consideration the traffic signal changes at a downstream intersection. The advisory speed information includes not only an optimal speed range updated every 300-ft for individual drivers but also a descriptive message to warn drivers stop to ensure safety at the downstream intersection. Unlike other similar Connected Vehicles applications for intersection management, ITSAS does not require Roadside Equipment (RSE to disseminate the advisory speed information as it is designed to exploit commercial cellular network service (i.e., 3G and 4G-LTE. Thus, ITSAS can be easily plugged into existing traffic control management system to rapidly conduct its implementation without significant additional cost. This research presents the field evaluations of ITSAS on a signalized corridor in New Jersey, which discovered significant travel time savings for the equipped vehicle.

  19. 75 FR 68022 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2010-11-04

    ...The FAA is issuing this notice to advise the public that a new charter has been issued for the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC). The duties of this advisory committee include: 1. To make recommendations for standardizing, clarifying, and upgrading terminology and procedures, as a result of its review of present ATC procedures and practices. 2. To provide advice and make recommendations concerning: a. New or significantly revised ATC procedural concepts. b. The adequacy of charts, diagrams, and illustrations used to convey information concerning the application of ATC procedures and their relevance to current, revised, or proposed ATC procedures and concepts. c. Aviation regulations that have an impact on present, new, or significantly revised ATC procedures and concepts. 3. To act solely in an advisory capacity to accomplish its duties.

  20. Utilization of a Technical Peer Review to Support the Mission of the Nevada Test Site Community Advisory Board

    International Nuclear Information System (INIS)

    Dixon, Earle C.; Peterson, Kathleen

    2003-01-01

    The U. S. Department of Energy's (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Environmental Management (EM) Underground Test Area (UGTA) project addresses the characterization and needs for long-term monitoring of the subsurface contamination resulting from 828 underground nuclear weapon tests at the Nevada Test Site (NTS). EM promotes, and is required, to include stakeholders in its program. However, UGTA is a very complex program not easily understood by members of the public. The NTS Community Advisory Board (CAB), a federally chartered Site Specific Advisory Board (SSAB), has studied the UGTA project since 1996, and has found it a challenge to completely comprehend and provide NNSA/NV meaningful citizen input. The CAB realized the benefit of a technical peer review and in 2000 recommended to NNSA/NV that a peer review of the UGTA strategy would provide valuable feedback to the program to address underground contamination at the NTS. N NSA agreed to the CAB's recommendation, and moved forward with a scope of work to have the American Society of Mechanical Engineers (ASME) perform the peer review of the UGTA strategy. The ASME began the peer review in June 2001, and their final report was published in November 2001. In January 2002, the CAB devoted their monthly meeting in Las Vegas, Nevada to reporting the results of the peer review of the UGTA strategy to the public. Two public workshops were later held in the community of Amargosa, Nevada during the month of January to help educate and build interest in the CAB February 2002 monthly meeting which was also held in Amargosa. The CAB recommendation to NNSA to utilize a technical peer review has provided valuable information to NNSA, the State of Nevada, and the CAB. At other DOE sites SSABs are challenged by a number of complex, technical programs requiring considerable time and resources for the board to comprehend. It is worth considering the utilization of an independent

  1. Approaches to the safety of future nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-09-01

    The Technical Committee Meeting on Approaches to Safety of Future Nuclear Power Plants in Different Countries, held from 29 May to 2 June 1995, contributed to this process. Experts from 14 different countries and two international organizations participated in the meeting, which provided the opportunity to exchange information and to review the answers developed to date to these issues (primarily form the IAEA's technical document ''Development of Safety Principles for the Design of Future Nuclear Power Plants'' IAEA-TECDOC-801) and the report of the International Nuclear Safety Advisory Group ''Basic Safety Principles for Nuclear Power Plants'' (INSAG-3). These references were then used as a starting point for answering the question ''to what degree does general agreement (or harmonization) exist on these desired safety approaches for future reactors, and what opportunities remain for further harmonization? 11 refs, 1 tab

  2. Organization and conduct of IAEA fire safety reviews at nuclear power plants

    International Nuclear Information System (INIS)

    1998-01-01

    The importance of fire safety in the safe and productive operation of nuclear power plants is recognized worldwide. Lessons learned from experience in nuclear power plants indicate that fire poses a real threat to nuclear safety and that its significance extends far beyond the scope of a conventional fire hazard. With a growing understanding of the close correlation between the fire hazard in nuclear power plants and nuclear safety, backfitting for fire safety has become necessary for a number of operating plants. However, it has been recognized that the expertise necessary for a systematic independent assessment of fire safety of a NPP may not always be available to a number of Member States. In order to assist in enhancing fire safety, the IAEA has already started to offer various services to Member States in the area of fire safety. At the request of a Member State, the IAEA may provide a team of experts to conduct fire safety reviews of varying scope to evaluate the adequacy of fire safety at a specific nuclear power plant during various phases such as construction, operation and decommissioning. The IAEA nuclear safety publications related to fire protection and fire safety form a common basis for these reviews. This report provides guidance for the experts involved in the organization and conduct of fire safety review services to ensure consistency and comprehensiveness of the reviews

  3. Nulcear Safety: Technical progress review, October--December 1988

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-01-01

    Nuclear Safety is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  4. 75 FR 43156 - Federal Advisory Committee; Missile Defense Advisory Committee

    Science.gov (United States)

    2010-07-23

    ... DEPARTMENT OF DEFENSE Office of the Secretary Federal Advisory Committee; Missile Defense Advisory Committee AGENCY: Missile Defense Agency (MDA), DoD. ACTION: Notice of closed meeting. SUMMARY: Under the... Defense announces that the Missile Defense Advisory Committee will meet on August 4 and 5, 2010, in...

  5. International Conference on Human and Organizational Aspects of Assuring Nuclear Safety. Exploring 30 years of Safety Culture. Programme and Abstracts

    International Nuclear Information System (INIS)

    2016-01-01

    Thirty years ago, the International Nuclear Safety Advisory Group concluded, in its investigation of the Chernobyl accident, that one of the key lessons to be learned from that accident was the importance of a strong safety culture to maintain safe operations. Almost five years have now passed since the accident at the Fukushima Daiichi nuclear power plant, and the need to implement a systemic approach to safety that takes into account the complex and dynamic sociotechnical systems comprising nuclear infrastructure is one of the main lessons emerging from investigations. This conference will allow an international audience to take a step back and reflect upon the knowledge accumulated in the areas of human and organizational factors (HOF), safety culture and leadership for safety over the past 30 years. The objectives of the conference are to: • Review the experience gained with regard to HOF, safety culture and leadership for safety; • Share and gather experiences related to current developments, approaches, methods and research in the areas of HOF, safety culture and leadership for safety; and • Identify the future needs for building organizational resilience capabilities in order to further strengthen defence in depth for nuclear facilities and activities. The special focus of the conference will be on safety culture and the past 30 years of developments in this area.

  6. Design review report for modifications to RMCS safety class equipment

    International Nuclear Information System (INIS)

    Corbett, J.E.

    1997-01-01

    This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable

  7. Design review report for modifications to RMCS safety class equipment

    Energy Technology Data Exchange (ETDEWEB)

    Corbett, J.E.

    1997-05-30

    This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable.

  8. Examples of safety culture practices

    International Nuclear Information System (INIS)

    1997-01-01

    This report has been prepared to illustrate the concepts and principles of safety culture produced in 1991 by the International Safety Advisory Group as 75-INSAG-4. It provides a small selection of examples taken from a worldwide collection of safety performance evaluations (e.g. IAEA safety series, national regulatory inspections, utility audits and a plant assessments). These documented evaluations collectively provide a database of safety performance strengths and weakness, and related safety culture observations. The examples which have been selected for inclusion in this report are those which are considered worthy of special mention and which illustrate a specific attribute of safety culture given in 75-INSAG-4

  9. Using an International Medical Advisory Board to guide clinical governance in a corporate refractive surgery model.

    Science.gov (United States)

    Vukich, John A

    2009-07-01

    To describe the role played by the International Medical Advisory Board (IMAB) in clinical and corporate governance at Optical Express, a corporate provider of refractive surgery. A review of goals, objectives, and actions of the IMAB. The IMAB has contributed to study design, data analysis, and selection of instruments and procedures. Through interactions with Optical Express corporate and clinical staff, the IMAB has supported management's effort to craft a corporate culture focused on continuous improvement in the safety and visual outcomes of refractive surgery. The IMAB has fashioned significant changes in corporate policies and procedures and has had an impact on corporate culture at Optical Express.

  10. 49 CFR 209.501 - Review of rail transportation safety and security route analysis.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Review of rail transportation safety and security....820 § 209.501 Review of rail transportation safety and security route analysis. (a) Review of route... establish that the route chosen by the carrier poses the least overall safety and security risk, the...

  11. SALTO Peer Review Guidelines. Guidelines for Peer Review of Safety Aspects of Long Term Operation of Nuclear Power Plants

    International Nuclear Information System (INIS)

    2014-01-01

    International peer review is a useful tool for Member States to exchange experiences, learn from each other and apply good practices in the long term operation (LTO) of nuclear power plants (NPPs). The peer review is also an important mechanism through which the IAEA supports Member States in enhancing the safety of NPPs. The IAEA has conducted various types of safety review that indirectly address aspects of LTO, including safety reviews for design, engineering, operation and external hazards. Operational Safety Review Team (OSART) services include review of ageing management programmes. In addition, several Member States have requested Ageing Management Assessment Team (AMAT) missions. Through these experiences, it was recognized that a comprehensive peer review on LTO would be very useful to Member States. The Safety Aspects of Long Term Operation (SALTO) peer review addresses strategy and key elements for the safe LTO of NPPs, which includes AMAT objectives and complements OSART reviews. The SALTO peer review is designed to assist operating organizations in adopting a proper approach to LTP including implementing appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review can be tailored to focus on ageing management programmes (AMPs) or on other activities related to LTO to support the Member State in enhancing the safety of its NPPs. The SALTO peer review can also support regulators in establishing or improving regulatory and licensing strategies for the LTO of NPPs. The guidelines in this publication are primarily intended for members of a SALTO review team and provide a basic structure and common reference for peer reviews of LTO. Additionally, the guidelines also provide useful information to the operating organizations of NPPs (or technical support organizations) for carrying out their own self-assessments or comprehensive programme reviews. The guidelines are intended to be generic, as there are

  12. 75 FR 39910 - Dixie Resource Advisory Committee

    Science.gov (United States)

    2010-07-13

    ... introductions, review the Federal Advisory Committee Act requirements, brief participants on Payments to States legislative history, discuss the guidelines for Title II and Title III funding and proposals, discuss...., Eastern Standard Time, Monday through Friday. SUPPLEMENTARY INFORMATION: The meetings are open to the...

  13. 75 FR 26918 - Fishlake Resource Advisory Committee

    Science.gov (United States)

    2010-05-13

    ... requirements, brief participants on Payments to States legislative history, discuss the guidelines for Title II... following business will be conducted: (1) Welcome and Committee introductions; (2) Federal Advisory Committee Act overview and powerpoint; (3) review of Payments to States legislative history and discussion...

  14. 77 FR 2766 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-01-19

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice; correction. SUMMARY... and Regional/Folk and Traditional Arts (state folk arts projects review) meeting, scheduled for...

  15. Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 2. Project Reviews G-P

    International Nuclear Information System (INIS)

    1985-04-01

    This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order

  16. Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

  17. 77 FR 46375 - Chippewa National Forest Resource Advisory Committee

    Science.gov (United States)

    2012-08-03

    ... Schools and Community Self-Determination Act (Pub. L. 110-343) (the Act) and operates in compliance with... review with the Chippewa National Forest Resource Advisory Committee members their roles and...

  18. A compilation of reports of the Advisory Committee on Reactor Safeguards: 1991 annual

    International Nuclear Information System (INIS)

    1992-04-01

    This compilation contains 41 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1991. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area

  19. 77 FR 13512 - National Advisory Committee on Meat and Poultry Inspection

    Science.gov (United States)

    2012-03-07

    ... Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION: Notice of committee meeting... Committee Act, that the National Advisory Committee on Meat and Poultry Inspection (NACMPI) will hold a public meeting on Wednesday, March 21, 2012, to discuss the proposed rule on the Modernization of Poultry...

  20. Preparation of NPP Dukovany periodic safety review

    International Nuclear Information System (INIS)

    Dubsky, L.; Vymazal, P.

    2004-01-01

    Dukovany NPP in Czech Republic performs a periodic safety review for the second time after approximately 20 years of operation. The history of the Safety Report and its transformation into an internationally accepted form complying with IAEA standards is described. The deterministic and probabilistic assessment of the plant's safety-related design and state is applied to determine whether and to what extend the relevant protective goals are fulfilled by the existing plant design. A description of the step-by-step process is presented together with the creation of methods and criteria for PSR evaluation prepared by Nuclear Research Institute Rez

  1. IAEA Concludes Safety Review at Chooz Nuclear Power Plant in France

    International Nuclear Information System (INIS)

    2013-01-01

    Full text: An IAEA-led international team of nuclear safety experts noted good practices and made recommendations to reinforce safety measures during a review of operational safety at France's Chooz Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 17 June, focused on aspects essential to the safe operation of the NPP. The team comprised experts from Switzerland, Belgium, Germany, China, India, United Kingdom, Czech Republic, Canada, Hungary and the IAEA. The review covered the areas of management, organization and administration; training and qualification of personnel; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team identified good plant practices that will be shared with the rest of the nuclear industry for consideration. Examples include: The plant has a professional development programme as part of a joint employment effort shared by the plant and its contractors. This enables trainees to develop professional capability, understand practices and gain experience from other nuclear power plants in terms of work planning and coordination; The plant has built a strong relationship between the on-shift response team of the plant and the local fire brigade to improve firefighting and rescue operations; Self-assessment groups discuss and resolve specific issues within operations, empowering operations personnel to take ownership of improvement programmes; and The plant has improved warnings at entrances to all o range zones , areas of elevated dose rates to which only authorized staff have access. The team identified a number of improvements to operational safety at Chooz NPP. Examples include: The plant should review its process for the

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

    International Nuclear Information System (INIS)

    2004-01-01

    The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

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

    International Nuclear Information System (INIS)

    2005-01-01

    The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

  4. Patient Safety and Workplace Bullying: An Integrative Review.

    Science.gov (United States)

    Houck, Noreen M; Colbert, Alison M

    Workplace bullying is strongly associated with negative nursing outcomes, such as work dissatisfaction, turnover, and intent to leave; however, results of studies examining associations with specific patient safety outcomes are limited or nonspecific. This integrative review explores and synthesizes the published articles that address the impact of workplace nurse bullying on patient safety.

  5. 75 FR 11104 - Del Norte Resource Advisory Committee (RAC)

    Science.gov (United States)

    2010-03-10

    ... Schools and Community Self-Determination Act (Pub. L. 110-343) and in compliance with the Federal Advisory...; (4) discussion of Committee member and Designated Federal Official roles and (5) review operational...

  6. Monitoring and reviewing research reactor safety in Australia

    International Nuclear Information System (INIS)

    Cairns, R.C.; Greenslade, G.K.

    1990-01-01

    Th research reactors operated by the Australian Nuclear Science and Technology Organization (ANSTO) comprise the 10 MW reactor HIFAR and the 100 kW reactor Moata. Although there are no power reactors in Australia the problems and issues of public concern which arise in the operation of research reactors are similar to those of power reactors although on a smaller scale. The need for independent safety surveillance has been recognized by the Australian Government and the ANSTO Act, 1987, required the Board of ANSTO to establish a Nuclear Safety Bureau (NSB) with responsibility to the Minister for monitoring and reviewing the safety of nuclear plant operated by ANSTO. The Executive Director of ANSTO operates HIFAR subject to compliance with requirements and arrangements contained in a formal Authorization from the Board of ANSTO. A Ministerial Direction to the Board of ANSTO requires the NSB to report to him, on a quarterly basis, matters relating to its functions of monitoring and reviewing the safety of ANSTO's nuclear plant. Experience has shown that the Authorization provides a suitable framework for the operational requirements and arrangements to be organised in a disciplined and effective manner, and also provides a basis for audits by the NSB by which compliance with the Board's safety requirements are monitored. Examples of the way in which the NSB undertakes its monitoring and reviewing role are given. Moata, which has a much lower operating power level and fission product inventory than HIFAR, has not been subject to a formal Authorization to date but one is under preparation

  7. International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: Senior nuclear regulators today concluded a Workshop on the Lessons Learned from the IAEA Integrated Regulatory Review Service (IRRS) Missions. The U.S. Nuclear Regulatory Commission (NRC) hosted the workshop, in cooperation with the International Atomic Energy Agency, in Washington, DC, from 26 to 28 October 2011. About 60 senior regulators from 22 IAEA Member States took part in this workshop. The IRRS programme is an international peer review service offered by the IAEA to its Member States to provide an objective evaluation of their nuclear safety regulatory framework. The review is based on the internationally recognized IAEA Safety Standards. ''The United States Nuclear Regulatory Commission was pleased to host the IAEA's IRRS meeting this week. The discussions over the past three days have provided an important opportunity for regulators from many countries to come together to strengthen the international peer review process,'' said U.S. NRC Chairman Gregory B. Jaczko. ''Especially after the Fukushima Daiichi accident, the global community recognizes that IRRS missions fill a vital role in strengthening nuclear safety and security programs around the world, and we are proud to be a part of this important effort.'' The IAEA Action Plan on Nuclear Safety includes actions focused towards strengthening the existing IAEA peer reviews, incorporating lessons learned and improving their effectiveness. The workshop provided a platform for the exchange of information, experience and lessons learned from the IRRS missions, as well as expectations for the IRRS programme for the near future. Further improvements in the planning and implementation of the IRRS missions in the longer term were discussed. A strong commitment of all relevant national authorities to the IRRS programme was identified as a key element of an effective regulatory framework. The conclusions of the workshop will be issued in November 2011 and the main results will be reported to the IAEA

  8. Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

    International Nuclear Information System (INIS)

    Wilmot, Roger D.

    2011-02-01

    The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

  9. 77 FR 69869 - National Advisory Council on Alcohol Abuse and Alcoholism, National Advisory Council on Drug...

    Science.gov (United States)

    2012-11-21

    ... Alcohol Abuse and Alcoholism, National Advisory Council on Drug Abuse, and National Cancer Advisory Board... Advisory Council on Alcohol Abuse and Alcoholism, National Advisory Council on Drug Abuse, and National...: National Advisory Council on Alcohol Abuse and Alcoholism, National Advisory Council on Drug Abuse, and...

  10. Safety objectives for nuclear activities in Canada

    International Nuclear Information System (INIS)

    1982-04-01

    This report by the Advisory Committee on Nuclear Safety presents a concise statement of the basic safety objectives which the Committee considers underlie, or should underlie, the regulations and the licensing and compliance practices of the Atomic Energy Control Board. The report also includes a number of general criteria for achieving these objectives

  11. John M. Eisenberg Patient Safety Awards. System innovation: Veterans Health Administration National Center for Patient Safety.

    Science.gov (United States)

    Heget, Jeffrey R; Bagian, James P; Lee, Caryl Z; Gosbee, John W

    2002-12-01

    In 1998 the Veterans Health Administration (VHA) created the National Center for Patient Safety (NCPS) to lead the effort to reduce adverse events and close calls systemwide. NCPS's aim is to foster a culture of safety in the Department of Veterans Affairs (VA) by developing and providing patient safety programs and delivering standardized tools, methods, and initiatives to the 163 VA facilities. To create a system-oriented approach to patient safety, NCPS looked for models in fields such as aviation, nuclear power, human factors, and safety engineering. Core concepts included a non-punitive approach to patient safety activities that emphasizes systems-based learning, the active seeking out of close calls, which are viewed as opportunities for learning and investigation, and the use of interdisciplinary teams to investigate close calls and adverse events through a root cause analysis (RCA) process. Participation by VA facilities and networks was voluntary. NCPS has always aimed to develop a program that would be applicable both within the VA and beyond. NCPS's full patient safety program was tested and implemented throughout the VA system from November 1999 to August 2000. Program components included an RCA system for use by caregivers at the front line, a system for the aggregate review of RCA results, information systems software, alerts and advisories, and cognitive acids. Following program implementation, NCPS saw a 900-fold increase in reporting of close calls of high-priority events, reflecting the level of commitment to the program by VHA leaders and staff.

  12. Healthcare Staff Wellbeing, Burnout, and Patient Safety: A Systematic Review

    Science.gov (United States)

    Hall, Louise H.; Johnson, Judith; Watt, Ian; Tsipa, Anastasia; O’Connor, Daryl B.

    2016-01-01

    Objective To determine whether there is an association between healthcare professionals’ wellbeing and burnout, with patient safety. Design Systematic research review. Data Sources PsychInfo (1806 to July 2015), Medline (1946 to July 2015), Embase (1947 to July 2015) and Scopus (1823 to July 2015) were searched, along with reference lists of eligible articles. Eligibility Criteria for Selecting Studies Quantitative, empirical studies that included i) either a measure of wellbeing or burnout, and ii) patient safety, in healthcare staff populations. Results Forty-six studies were identified. Sixteen out of the 27 studies that measured wellbeing found a significant correlation between poor wellbeing and worse patient safety, with six additional studies finding an association with some but not all scales used, and one study finding a significant association but in the opposite direction to the majority of studies. Twenty-one out of the 30 studies that measured burnout found a significant association between burnout and patient safety, whilst a further four studies found an association between one or more (but not all) subscales of the burnout measures employed, and patient safety. Conclusions Poor wellbeing and moderate to high levels of burnout are associated, in the majority of studies reviewed, with poor patient safety outcomes such as medical errors, however the lack of prospective studies reduces the ability to determine causality. Further prospective studies, research in primary care, conducted within the UK, and a clearer definition of healthcare staff wellbeing are needed. Implications This review illustrates the need for healthcare organisations to consider improving employees’ mental health as well as creating safer work environments when planning interventions to improve patient safety. Systematic Review Registration PROSPERO registration number: CRD42015023340. PMID:27391946

  13. IRIS Toxicological Review of Hexahydro-1,3,5-Trinitro-1,3,5-Triazine (RDX) (External Review Draft)

    Science.gov (United States)

    The IRIS Toxicological Review of Hexahydro-1,3,5-trinitro-1,3,5-triazine (RDX) was released for external peer review in September 2016. The EPA’s Science Advisory Board’s (SAB) Chemical Assessment Advisory Committee (CAAC) will conduct a peer review of the scientific basis suppor...

  14. Nuclear Safety: Technical progress review, January--March 1989

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E. G. [ed.

    1989-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  15. 75 FR 36373 - Federal Advisory Committee; Advisory Council on Dependents' Education

    Science.gov (United States)

    2010-06-25

    ..., the Department of Defense announces that the Advisory Council on Dependents' Education will meet on... response to the stated agenda of the planned meeting of the Advisory Council on Dependents' Education. All... membership for their consideration. For the next meeting of the Advisory Council on Dependents' Education, Dr...

  16. Citizen advisory groups: Improving their effectiveness

    International Nuclear Information System (INIS)

    Peelle, E.

    1990-01-01

    In an age of citizen distrust of government and intense not-in-my-backyard activity when waste management facilities are proposed, the potential of citizen advisory groups (CAGS) to aid the decision-making process is worth exploring. This paper reviews findings from case studies by the author and others to assess the various purposes, pitfalls, advantages and outcomes of CAGs in influencing decisions about controversial waste management actions and facilities. Advantages and disadvantages of the CAG are evaluated as one of several public participation mechanisms. The paper outlines ways in which CAGs can aid the waste management decision process and develop minimum requirements for the successful functioning of citizen advisory groups in decision processes with significant technical components, such as those involving nuclear and hazardous wastes

  17. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  18. Second periodic safety review of Angra Nuclear Power Station, unit 1

    International Nuclear Information System (INIS)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

    2015-01-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  19. Use of FPGA and CPLD in nuclear reactor safety systems and its regulatory review requirements for reactor safety

    International Nuclear Information System (INIS)

    Roy, Suvadip; Biswas, Animesh; Pradhan, S.K.

    2015-01-01

    Field Programmable Gate Arrays (FPGA) and Complex Programmable Logic Devices (CPLD) is being used widely in safety critical and safety related systems in nuclear power plans like in trip logic units, Engineered Safety Feature (ESF) actuation decision logic and neutronic signal processing for their reprogrammability feature and compact design. These HDL Programmable devices (HPD) are complex devices consisting of both hardware and software which is used to implement the logic on the FPGA. It is observed that these Programmable devices suffer from various modes of failure and the major failures in these devices are due to Single Event Upset (SEU), where a highly energetic ionizing radiation may lead to device failure which can even occur in radiologically benign environment. Other failures can occur during steps of developing the hardware using software tools like during Synthesis and placement and routing of the desired hardware. Here a study on use of such devices in Nuclear Reactors, study on mode of failures of these devices, way to tackle such failure and development of review guidelines for review of such devices used in safety critical and safety related systems with special emphasis on choice of software tools, way to mitigate effects of SEU and simulation and hardware testing results to be reviewed by regulatory body during design safety review is done. (author)

  20. SKI's and SSI's review of SKB's safety report SR-Can

    International Nuclear Information System (INIS)

    Dverstorp, Bjoern; Stroemberg, Bo

    2008-03-01

    This report summarises SKI's and SSI's joint review of the Swedish Nuclear Fuel and Waste Management Co's (SKB) safety report SR-Can (SKB TR-06-09). SR-Can is the first assessment of post-closure safety for a KBS-3 spent nuclear fuel repository at the candidate sites Forsmark and Laxemar, respectively. The analysis builds on data from the initial stage of SKB's surface-based site investigations and on data from full-scale manufacturing and testing of buffer and copper canisters. SR-Can can be regarded as a preliminary version of the safety report that will be required in connection with SKB's planned licence application for a final repository in late 2009. The main purpose of the authorities' review is to provide feedback to SKB on their safety reporting as part of the pre-licensing consultation process. However, SR-Can is not part of the formal licensing process. In support of the authorities' review three international peer review teams were set up to make independent reviews of SR-Can from three perspectives, namely integration of site data, representation of the engineered barriers and safety assessment methodology, respectively. Further, several external experts and consultants have been engaged to review detailed technical and scientific issues in SR-Can. The municipalities of Oesthammar and Oskarshamn where SKB is conducting site investigations, as well NGOs involved in SKB's programme, have been invited to provide their views on SR-Can as input to the authorities' review. Finally, the authorities themselves, and with the help of consultants, have used independent models to reproduce part of SKB's calculations and to make complementary calculations. All supporting review documents are published in SKI's and SSI's report series. The main findings of the review are: -SKB's safety assessment methodology is overall in accordance with applicable regulations, but part of the methodology needs to be further developed for the licence application. -SKB's quality

  1. Safety assessment of Olkiluoto NPP units 1 and 2. Decision of the Radiation and Nuclear Safety Authority regarding the periodic safety review of the Olkiluoto NPP

    International Nuclear Information System (INIS)

    2010-02-01

    In this safety assessment the Radiation and Nuclear Safety Authority (STUK) has evaluated the safety of the Olkiluoto Nuclear Power Plant units 1 and 2 in connection with the periodic safety review. This safety assessment provides a summary of the reviews, inspections and continuous oversight carried out by STUK. The issues addressed in the assessment and the related evaluation criteria are set forth in the nuclear energy and radiation safety legislation and the regulations issued thereunder. The provisions of the Nuclear Energy Act concerning the safe use of nuclear energy, security and emergency preparedness arrangements, and waste management are specified in more detail in the Government Decrees and Regulatory Guides issued by STUK. Based on the assessment, STUK consideres that the Olkiluoto Nuclear Power Plant units 1 and 2 meet the set safety requirements for operational nuclear power plants, the emergency preparedness arrangements are sufficient and the necessary control to prevent the proliferation of nuclear weapons has been appropriately arranged. The physical protection of the Olkiluoto nuclear power plant is not yet completely in compliance with the requirements of Government Decree 734/2008, which came into force in December 2008. Further requirements concerning this issue based also on the principle of continuous improvement were included in the decision relating to the periodic safety review. The safety of the Olkiluoto nuclear power plant was assessed in compliance with the Government Decree on the Safety of Nuclear Power Plants (733/2008), which came into force in 2008. The decree notes that existing nuclear power plants need not meet all the requirements set out for new plants. Most of the design bases pertaining to the Olkiluoto 1 and 2 nuclear power plant units were set in the 1970s. Substantial modernisations have been carried out at the Olkiluoto 1 and 2 nuclear power plant units since their commissioning to improve safety. This is in line with

  2. Fuel safety criteria and review by OECD / CSNI task force

    International Nuclear Information System (INIS)

    Van Doesburg, W.

    1999-01-01

    Full text of publication follows: with the advent of advanced fuel and core designs, and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a general feeling that safety margins have been or are being reduced. Historically, fuel safety margins were defined by adding conservatism to the safety limits, which in turn were also fixed in a conservative manner, here, the expression 'conservatism' expresses the fact that bounding or limiting numbers were chosen for model parameters, plant and fuel design data, and fuel operating history values. Unfortunately, as these conservatisms were not quantified (or quantifiable), the amount of safety available or the reduction thereof is difficult to substantiate. For the regulator, it is important to know the margin available with the utilities' request for approval of new fuel or methods; likewise, for the utility and vendor it is important to know what margins exist and what they are based on, to identify in which direction they can make further progress and optimize fuel and fuel cycle cost. Naturally, each party involved will have to decide on how much margin should be in place, to establish operational criteria and ensure that these can actually be met during operation. To assess the margins issue, safety criteria themselves need to be reviewed first. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel available at that time - mostly at zero exposure. Of course, verification was performed as designs progressed in later years, primarily with the aim to be able to prove that safety criteria were adequate as long as the said conservatisms would be retained, and not with the aim to reestablish limits. The mandate to the OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) is to assess the adequacy of existing fuel safety criteria, in view of the 'new design' elements (new

  3. Economic evaluation in patient safety: a literature review of methods.

    Science.gov (United States)

    de Rezende, Bruna Alves; Or, Zeynep; Com-Ruelle, Laure; Michel, Philippe

    2012-06-01

    Patient safety practices, targeting organisational changes for improving patient safety, are implemented worldwide but their costs are rarely evaluated. This paper provides a review of the methods used in economic evaluation of such practices. International medical and economics databases were searched for peer-reviewed publications on economic evaluations of patient safety between 2000 and 2010 in English and French. This was complemented by a manual search of the reference lists of relevant papers. Grey literature was excluded. Studies were described using a standardised template and assessed independently by two researchers according to six quality criteria. 33 articles were reviewed that were representative of different patient safety domains, data types and evaluation methods. 18 estimated the economic burden of adverse events, 3 measured the costs of patient safety practices and 12 provided complete economic evaluations. Healthcare-associated infections were the most common subject of evaluation, followed by medication-related errors and all types of adverse events. Of these, 10 were selected that had adequately fulfilled one or several key quality criteria for illustration. This review shows that full cost-benefit/utility evaluations are rarely completed as they are resource intensive and often require unavailable data; some overcome these difficulties by performing stochastic modelling and by using secondary sources. Low methodological transparency can be a problem for building evidence from available economic evaluations. Investing in the economic design and reporting of studies with more emphasis on defining study perspectives, data collection and methodological choices could be helpful for strengthening our knowledge base on practices for improving patient safety.

  4. Fourteenth meeting of the ITER management advisory committee

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    1998-01-01

    Following the Director's report on the progress made in the ITER Engineering Design Activities, the ITER Management Advisory Committee reviewed the Task Status Summary, Work Program and Task Agreements for EDA Extension, Joint Fund and a schedule of ITER meetings

  5. 78 FR 25476 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2013-05-01

    ... Safety Officer Medal of Valor Review Board AGENCY: Bureau of Justice Assistance (BJA), Department of...) of the Public Safety Officer Medal of Valor Review Board to consider a range of issues of [email protected] . SUPPLEMENTARY INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out...

  6. SRTC criticality safety technical review: Nuclear Criticality Safety Evaluation 93-04 enriched uranium receipt

    International Nuclear Information System (INIS)

    Rathbun, R.

    1993-01-01

    Review of NMP-NCS-930087, open-quotes Nuclear Criticality Safety Evaluation 93-04 Enriched Uranium Receipt (U), July 30, 1993, close quotes was requested of SRTC (Savannah River Technology Center) Applied Physics Group. The NCSE is a criticality assessment to determine the mass limit for Engineered Low Level Trench (ELLT) waste uranium burial. The intent is to bury uranium in pits that would be separated by a specified amount of undisturbed soil. The scope of the technical review, documented in this report, consisted of (1) an independent check of the methods and models employed, (2) independent HRXN/KENO-V.a calculations of alternate configurations, (3) application of ANSI/ANS 8.1, and (4) verification of WSRC Nuclear Criticality Safety Manual procedures. The NCSE under review concludes that a 500 gram limit per burial position is acceptable to ensure the burial site remains in a critically safe configuration for all normal and single credible abnormal conditions. This reviewer agrees with that conclusion

  7. Guide for reviewing safety analysis reports for packaging: Review of quality assurance requirements

    International Nuclear Information System (INIS)

    Moon, D.W.

    1988-10-01

    This review section describes quality assurance requirements applying to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging which are important to safety. The design effort, operation's plans, and quality assurance requirements should be integrated to achieve a system in which the independent QA program is not overly stringent and the application of QA requirements is commensurate with safety significance. The reviewer must verify that the applicant's QA section in the SARP contains package-specific QA information required by DOE Orders and federal regulations that demonstrate compliance. 8 refs

  8. Nuclear Fuel Safety Criteria Technical Review - Second edition

    International Nuclear Information System (INIS)

    Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

    2012-01-01

    Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)

  9. Safety review on unit testing of safety system software of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Le; Zhang Qi

    2013-01-01

    Software unit testing has an important place in the testing of safety system software of nuclear power plants, and in the wider scope of the verification and validation. It is a comprehensive, systematic process, and its documentation shall meet the related requirements. When reviewing software unit testing, attention should be paid to the coverage of software safety requirements, the coverage of software internal structure, and the independence of the work. (authors)

  10. International Expert Review of Sr-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

    International Nuclear Information System (INIS)

    Sagar, Budhi; Egan, Michael; Roehlig, Klaus-Juergen; Chapman, Neil; Wilmot, Roger

    2008-03-01

    In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The purposes of the SR-Can project were stated in the main project report to be: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's research and development (R and D) programme, to further site investigations and to future safety assessments. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. To help inform their review of SKB's proposed approach to development of the longterm safety case, the authorities appointed three international expert review teams to carry out a review of SKB's SR-Can safety assessment report. Comments from one of these teams - the Safety Assessment Methodology (SAM) review team - are presented in this document. The SAM review team's scope of work included an examination of SKB's documentation of the assessment ('Long-term safety for KBS-3 Repositories at Forsmark and Laxemar - a first evaluation' and several supporting reports) and hearings with SKB staff and contractors, held in March 2007. As directed by SKI and SSI, the SAM review team focused on methodological aspects and sought to determine whether SKB's proposed safety assessment methodology is likely to be suitable for use in the future SR-Site and to assess its consistency with the Swedish regulatory framework. No specific evaluation of long-term safety or site acceptability was undertaken by any of the review teams. SKI and SSI's Terms of Reference for the SAM review team requested that consideration be given

  11. 75 FR 22757 - Federal Advisory Committee; Army Education Advisory Committee; Charter Renewal

    Science.gov (United States)

    2010-04-30

    ..., school curriculums, educational philosophy and objectives, program effectiveness, facilities, staff and... DEPARTMENT OF DEFENSE Office of the Secretary Federal Advisory Committee; Army Education Advisory... Defense gives notice that it is renewing the charter for the Army Education Advisory Committee (hereafter...

  12. Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

    Energy Technology Data Exchange (ETDEWEB)

    Wilmot, Roger D. (Galson Sciences Limited (United Kingdom))

    2011-02-15

    The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

  13. Safety review for human factors engineering and control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Yang Mengzhuo

    1998-01-01

    Safety review for human factors engineering and control rooms of nuclear power plants (NPP) is in a forward position of science and technology, which began at American TMI severe accident and had been implemented in China. The importance and the significance of the safety review are expounded, the requirements of its scope and profundity are explained in detail. In addition, the situation of the technical document system for nuclear safety regulation on human factors engineering and control rooms of NPP in China is introduced briefly, on which the safety review is based

  14. 75 FR 45591 - Pipeline Safety: Notice of Technical Pipeline Safety Advisory Committee Meetings

    Science.gov (United States)

    2010-08-03

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part... Committee Meetings AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION... safety standards, risk assessments, and safety policies for natural gas pipelines and for hazardous...

  15. The periodic safety review of nuclear power plants. Practices in OECD countries

    International Nuclear Information System (INIS)

    1992-01-01

    This report gives an overview of the regulatory concepts and practices for the periodic safety review of nuclear power plants in OECD countries with nuclear power programmes. The statutory bases for such reviews, their objectives and the processes adopted are summarised against the background of each country's regulatory practices. Although periodic safety reviews are now, or will soon be, part of the regulatory process in the majority of countries, the national approaches to these reviews still differ considerably. This report includes numerous examples of the different concepts and practices in OECD countries, thereby illustrating the variety of ways adopted to reach the common goal of maintaining and improving nuclear safety

  16. 75 FR 51985 - Federal Advisory Committee; Advisory Council on Dependents' Education (ACDE)

    Science.gov (United States)

    2010-08-24

    ... Advisory Council on Dependents' Education (ACDE) scheduled for September 8, 2010, is cancelled. The meeting... submit written statements to the Advisory Council on Dependents' Education about its mission and... planned meeting of the Advisory Council on Dependents' Education. All written statements shall be...

  17. ITER management advisory committee (MAC) meeting in Naka

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    2000-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held on 28 June 2000 in Moskow, Russia. The main topics were the consideration of the report by the director on the ITER EDA status, the review of the work program, the review of the joint fund, the review of a schedule of ITER meetings and initial discussion and consideration on the disposition of R and D hardware and facilities and other dispositions relating to the termination of the EDA

  18. 29 CFR 2200.108 - Official Seal of the Occupational Safety and Health Review Commission.

    Science.gov (United States)

    2010-07-01

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

  19. IAEA Operational Safety Team Reviews Saint-Alban Nuclear Power Plant, France

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed safety practices at France's Saint-Alban Nuclear Power Plant (NPP) and has highlighted a set of strong practices as well as a series of recommendations to reinforce them. The IAEA assembled the team at the request of the Government of France to conduct an Operational Safety Review (OSART) of the Saint-Alban NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review from 20 September to 6 October 2010. The team was made up of experts from Belgium, Canada, the Czech Republic, Germany, Lithuania, the Netherlands, Slovakia, Sweden and the USA. An OSART mission is designed to review programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Saint-Alban conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely are under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: A safety guideline for outages; The use of remote video surveillance of fuel inspection and handling activities; A motivational tool for plant staff regarding the benefits of operating experience and associated corrective actions; and Use of a sophisticated key control system

  20. IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

  1. 77 FR 55452 - Lynn Canal-Icy Strait Resource Advisory Committee

    Science.gov (United States)

    2012-09-10

    ... Federal Advisory Committee Act. The purpose of the committee is to improve collaborative relationships and... review and recommend project proposals that will meet the purposes of improving or maintaining existing...

  2. 75 FR 80083 - Advisory Committee on the Medical Uses of Isotopes: Meeting Notice

    Science.gov (United States)

    2010-12-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on the Medical Uses of Isotopes: Meeting Notice AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Notice of Meeting. SUMMARY: The U.S. Nuclear... the draft safety culture policy statement for medical licensees. Contingent upon the outcome of the...

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

    International Nuclear Information System (INIS)

    1983-02-01

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

  4. 76 FR 45402 - Advisory Committee; Medical Imaging Drugs Advisory Committee; Re-Establishment

    Science.gov (United States)

    2011-07-29

    .... FDA-2010-N-0002] Advisory Committee; Medical Imaging Drugs Advisory Committee; Re- Establishment... (FDA) is announcing the re- establishment of the Medical Imaging Drugs Advisory Committee in FDA's Center for Drug Evaluation and Research. This rule amends the current language for the Medical Imaging...

  5. 76 FR 23323 - Meeting of the Scientific Advisory Committee on Alternative Toxicological Methods (SACATM)

    Science.gov (United States)

    2011-04-26

    ... the scientific validation and regulatory acceptance of toxicological and safety testing methods that... DEPARTMENT OF HEALTH AND HUMAN SERVICES Meeting of the Scientific Advisory Committee on Alternative Toxicological Methods (SACATM) AGENCY: National Toxicology Program (NTP), National Institute of...

  6. 77 FR 40358 - Meeting of the Scientific Advisory Committee on Alternative Toxicological Methods (SACATM)

    Science.gov (United States)

    2012-07-09

    ..., revised, and alternative safety testing methods with regulatory applicability and promotes the scientific... DEPARTMENT OF HEALTH AND HUMAN SERVICES Meeting of the Scientific Advisory Committee on Alternative Toxicological Methods (SACATM) AGENCY: Division of the National Toxicology Program (DNTP...

  7. Effect of electronic device use on pedestrian safety : a literature review.

    Science.gov (United States)

    2016-04-01

    This literature review on the effect of electronic device use on pedestrian safety is part of a research project sponsored by the Office of Behavioral Safety Research in the National Highway Traffic Safety Administration (NHTSA). An extensive literat...

  8. 76 FR 4659 - Science Advisory Board Staff Office; Notification of a Public Teleconference of the Science...

    Science.gov (United States)

    2011-01-26

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9254-5] Science Advisory Board Staff Office; Notification of a Public Teleconference of the Science Advisory Board Nutrient Criteria Review Panel Correction In notice document 2011-1014 beginning on page 3133 in the issue of Wednesday, January 19, 2011, make the...

  9. Reactor safety review of permanent changes

    International Nuclear Information System (INIS)

    Lam, K.F.

    1997-01-01

    Operational compliance engineers review all changes as part of a change control process. Each change, permanent or temporary, is required to undergo an intricate review process to ensure that the benefits associated with the change outweigh the risk. For permanent changes, it is necessary to ensure that the proposed design meets the nuclear safety requirements, conforms to the licensing requirements and complies with regulatory requirements. In addition, during installation of the permanent change and prior to in-service, a configuration management process is in place to align the change with operating and maintenance documents. (author)

  10. The Ionising Radiations Advisory Committee Open Meeting 10 October 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-12-01

    Full text: The Ionising Radiations Advisory Committee (IRAC) held its first open meeting on 10 October 2001 in response to a request from the Health and Safety Commission (HSC) that all its advisory committees should follow the Commission's example and hold such meetings. Some of the other advisory committees have already held open meetings and others are planning to do so shortly. The aim of the meeting was to enable members of the public to meet IRAC members and to find out more about the Committee - how it worked and the type of issues it dealt with. The first two sessions were devoted to short presentations describing IRAC's work and influences, now and in the future, on radiation protection generally. The third session was a discussion forum. The agenda for the meeting and the presentations are posted on the web at: www.hse.gov.uk/foi/iracopen.htm. Each session of presentations was followed by questions of clarification and the third session of the meeting comprised an open forum. Many of the questions raised were not directly relevant to IRAC but, nevertheless, members provided brief responses and referred questions on to others as appropriate. One question had been notified in advance, asking whether members of IRAC agreed that it is now (regrettably) reasonably foreseeable that a loss of containment of radioactive material may occur at a nuclear facility as a result of impact by an aeroplane or by other hostile acts, and that this should be made clear in published guidance on REPPIR. This question was not within IRAC's remit. The Chairman of the Nuclear Safety Advisory Committee offered to take the question to the Committee's next meeting. Issues discussed included: Concerns that exposure to ionising radiation at low levels is more dangerous than is currently reflected in risk estimates. The European Parliament has adopted a resolution calling on the main international bodies, including the International Commission on Radiological

  11. Perceptions of recreational fishing boat captains: knowledge and effects of fish consumption advisories.

    Science.gov (United States)

    Burger, J; Johnson, B B; Shukla, S; Gochfeld, M

    2003-04-01

    The impacts of fish consumption advisories on recreational and subsistence fishing, particularly in fresh waters, have been examined extensively. By contrast, little attention has focused on organized recreational fishing, such as from party and charter boats, and particularly for salt water fish. We interviewed 93 New Jersey boat captains to determine their knowledge about fish consumption advisories, and whether, in their opinion, clients knew of fish consumption advisories, and whether they thought advisories had an effect on recreational fishing and their businesses. Advisories were ranked by captains as a moderate influence on the success of their business, less so than number of fish caught, strength of the economy, overfishing by commercial boats, and management regulations. Only one boat captain had not heard warnings about eating fish, but what captains said they had heard was mixed in its accuracy and completeness. Clients expect captains to know about fish, and about half of boat captains said clients had asked about the safety of eating fish. Captains who felt advisories were affecting their businesses tended to fish for species without high levels of mercury (except for bluefish) or PCBs, the primary contaminants of concern for state advisories and federal advice. However, these captains worked closer to areas (e.g., Raritan Bay complex and New York Harbor) subject to advisories than did other captains, and were more prone to say that management regulations (e.g., fish size, creel limits, seasons) and marketing and advertising by the industry or state were strong influences on the success of their seasons. Comparing captains who thought advisories had some or great effect (60%) versus those reporting "no effect" (40%), there was no difference in the mean percentage of trips targeting high mercury species such as swordfish and shark. Many captains said they would or might post advisories, but 42% of the boat captains said they would not post consumption

  12. Nuclear Safety: Volume 29, No. 3: Technical progress review

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-07-01

    Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

  13. 76 FR 29752 - The President's Management Advisory Board (PMAB); Notification of Upcoming Public Advisory Meeting

    Science.gov (United States)

    2011-05-23

    ... Management, for the purpose of identifying leading business practices that have the potential to improve...'s Management Advisory Board (PMAB); Notification of Upcoming Public Advisory Meeting AGENCY: Office...: The President's Management Advisory Board, a Federal Advisory Committee established in accordance with...

  14. Citizen advisory groups: Improving their effectiveness

    Energy Technology Data Exchange (ETDEWEB)

    Peelle, E.

    1990-01-01

    In an age of citizen distrust of government and intense NIMBY (not-in-my-backyard) activity when waste management facilities are proposed, the potential of citizen advisory groups (CAGs) to aid the decision-making process is worth exploring. This paper reviews findings from case studies by the author and others to assess the various purposes, pitfalls, advantages and outcomes of CAGs in influencing decisions about controversial waste management actions and facilities. Advantages and disadvantages of the CAG are evaluated as one of several public participation mechanisms. We outline ways in which CAGs can aid the waste management decision process and develop minimum requirements for the successful functioning of citizen advisory groups in decision processes with significant technical components, such as those involving nuclear and hazardous wastes. 18 refs., 1 tab.

  15. X-ray safety in Ontario

    International Nuclear Information System (INIS)

    1980-03-01

    In July 1979 the Ontario Advisory Committee on Radiology was formed to develop a comprehensive strategy for x-ray safety in the province. At its hearings the committee recieved submissions from groups representing physicians, dentists, chiropractors, radiological technicians, physiotherapists, podiatrists, and consumers, among others; these briefs are included as appendices to the report. The report surveys the historical background and the current situation in Ontario, and makes recommendations for an organized safety program. (L.L.)

  16. The work of the Operational Safety Review Team (OSART)

    International Nuclear Information System (INIS)

    Hide, K.W.

    1996-01-01

    The Operational Safety Review Team (OSART) programme was set up by the IAEA in 1982 to assist Member States to enhance the operational safety of nuclear power plants. Each team is staffed by senior experts in the relevant fields. The review team discusses with plant staff the existing operational programmes for plant which may be under construction, being commissioned or already operating. Following a detailed examination of a safety programme, the OSART team lists strengths and weaknesses and makes recommendations on how to overcome the latter. Since their conclusions are based on the best prevailing international practice, they may be more stringent than those based on national criteria. The results of the 77 missions conducted at 62 plants in 28 countries by the end of 1994 are summarised. (UK)

  17. Russian Minatom nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    Royen, J.

    1999-01-01

    An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

  18. Healthcare Staff Wellbeing, Burnout, and Patient Safety: A Systematic Review.

    Science.gov (United States)

    Hall, Louise H; Johnson, Judith; Watt, Ian; Tsipa, Anastasia; O'Connor, Daryl B

    2016-01-01

    To determine whether there is an association between healthcare professionals' wellbeing and burnout, with patient safety. Systematic research review. PsychInfo (1806 to July 2015), Medline (1946 to July 2015), Embase (1947 to July 2015) and Scopus (1823 to July 2015) were searched, along with reference lists of eligible articles. Quantitative, empirical studies that included i) either a measure of wellbeing or burnout, and ii) patient safety, in healthcare staff populations. Forty-six studies were identified. Sixteen out of the 27 studies that measured wellbeing found a significant correlation between poor wellbeing and worse patient safety, with six additional studies finding an association with some but not all scales used, and one study finding a significant association but in the opposite direction to the majority of studies. Twenty-one out of the 30 studies that measured burnout found a significant association between burnout and patient safety, whilst a further four studies found an association between one or more (but not all) subscales of the burnout measures employed, and patient safety. Poor wellbeing and moderate to high levels of burnout are associated, in the majority of studies reviewed, with poor patient safety outcomes such as medical errors, however the lack of prospective studies reduces the ability to determine causality. Further prospective studies, research in primary care, conducted within the UK, and a clearer definition of healthcare staff wellbeing are needed. This review illustrates the need for healthcare organisations to consider improving employees' mental health as well as creating safer work environments when planning interventions to improve patient safety. PROSPERO registration number: CRD42015023340.

  19. 75 FR 70955 - Advisory Committee on the Medical Uses of Isotopes: Meeting Notice

    Science.gov (United States)

    2010-11-19

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on the Medical Uses of Isotopes: Meeting Notice AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Notice of meeting. SUMMARY: The U.S. Nuclear... the draft safety culture policy statement for medical licensees. A copy of the agenda for the meeting...

  20. Patient participation in patient safety and nursing input - a systematic review.

    Science.gov (United States)

    Vaismoradi, Mojtaba; Jordan, Sue; Kangasniemi, Mari

    2015-03-01

    This systematic review aims to synthesise the existing research on how patients participate in patient safety initiatives. Ambiguities remain about how patients participate in routine measures designed to promote patient safety. Systematic review using integrative methods. Electronic databases were searched using keywords describing patient involvement, nursing input and patient safety initiatives to retrieve empirical research published between 2007 and 2013. Findings were synthesized using the theoretical domains of Vincent's framework for analysing risk and safety in clinical practice: "patient", "healthcare provider", "task", "work environment", "organisation & management". We identified 17 empirical research papers: four qualitative, one mixed-method and 12 quantitative designs. All 17 papers indicated that patients can participate in safety initiatives. Improving patient participation in patient safety necessitates considering the patient as a person, the nurse as healthcare provider, the task of participation and the clinical environment. Patients' knowledge, health conditions, beliefs and experiences influence their decisions to engage in patient safety initiatives. An important component of the management of long-term conditions is to ensure that patients have sufficient knowledge to participate. Healthcare providers may need further professional development in patient education and patient care management to promote patient involvement in patient safety, and ensure that patients understand that they are 'allowed' to inform nurses of adverse events or errors. A healthcare system characterised by patient-centredness and mutual acknowledgement will support patient participation in safety practices. Further research is required to improve international knowledge of patient participation in patient safety in different disciplines, contexts and cultures. Patients have a significant role to play in enhancing their own safety while receiving hospital care. This

  1. A LITERATURE REVIEW ON GLOBAL OCCUPATIONAL SAFETY AND HEALTH PRACTICE & ACCIDENTS SEVERITY

    Directory of Open Access Journals (Sweden)

    Kassu Jilcha

    2016-06-01

    Full Text Available This literature review focuses on researches undertaken since 1980s onwards. The purpose of the study is to identify existing gaps on workplace safety and health management and propose future research areas. The review adds value to existing electronic database through integration of researches' results. To identify existing gaps, a systematic literature review approach has been used. The reviews were undertaken through keywords and safety related topics. In the literature, various characteristics of workplace safety and health problems were found emanating from the lack of operational activities of the employees, internal working environment and external environment those impose hazards on employee temporarily, permanently and on working environments. The integration of multidisciplinary approaches and collaborative model of hub and peripheral industries to protect workplace safety hazards to develop multilevel model has been undermined in many researches. The other face of finding is that knowledge transfer mechanism and industrial topology factors are left. Some researches finding showed that they have focused on single problems related to health and health factors leaving universal improving workplace safety. In general, this literature reviews compare various studies output based on their research method and findings to fills gap and add value to a body of knowledge.

  2. Disposal of radioactive waste: can long-term safety be evaluated

    International Nuclear Information System (INIS)

    1991-01-01

    The long-term safety of any hazardous waste disposal system must be convincingly shown prior to its implementation. For radioactive wastes, safety assessments over timescales far beyond the normal horizon of social and technical planning have already been conducted in many countries. These assessments provide the principal means to investigate, quantify, and explain long-term safety of each selected disposal concept and site for the appropriate authorities and the public. Such assessments are based on four main elements: definition of the disposal system and its environment, identification of possible processes and events that may affect the integrity of the disposal system, quantification of the radiological impact by predictive modelling, and description of associated uncertainties. The NEA Radioactive Waste Management Committee and the IAEA International Radioactive Waste Management Advisory Committee have carefully examined the current scientific methods for safety assessments of radioactive waste disposal systems, as briefly summarized in this report. The Committees have also reviewed the experience now available from using safety assessment methods in many countries, for different disposal concepts and formations, and in the framework of both nationally and internationally conducted studies, as referenced in this report [fr

  3. Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 3. Project Reviews Q-Z

    International Nuclear Information System (INIS)

    1985-04-01

    This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Resports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume includes reports arranged alpbabetically from Q to Z

  4. Scientific Advisory Panel to Meet on Cancer Potential of Glyphosate

    Science.gov (United States)

    The Federal Insecticide, Fungicide, and Rodenticide Act Scientific Advisory Panel (SAP) will meet October 18-21, 2016, to consider and review a set of scientific issues being evaluated by the regarding EPA's evaluation

  5. Second review meeting of the Contracting Parties to the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Rafferty, Barbara

    2002-01-01

    The Second Review Meeting of the Contracting Parties to the Convention on Nuclear Safety was held in the Headquarters of the International Atomic Energy Agency in Vienna from 15-26 April 2002, under the chairmanship of the President, Mr Miroslav Gregoric, Director of the Slovenian Nuclear Safety Authority. The Convention on Nuclear Safety entered into force in October 1996, has been signed by sixty-five States and ratified by fifty-four, bringing within its scope 428 of the 448 nuclear reactors worldwide. The Convention aims to achieve and maintain a high level of nuclear safety worldwide, through inter alia enhancement of national measures and international co-operation. Obligations on Contracting Parties in accordance with the Convention include: the establishment and maintenance of a legislative and regulatory framework to govern the safety of land-based civil nuclear installations; the allocation of adequate financial and human resources to support the safety objectives; ensuring that all reasonably practicable improvements to safety are made as a matter of urgency. Adherence to this Convention entails two basic commitments by each Contracting Party: to prepare and make available a national report for review; and to subject its national report to a peer review by the other Contracting Parties. Thus, being a Contracting Party to this Convention involves: including in the national report a self-assessment of steps and measures already taken and in progress to implement the Convention obligations; taking an active part in an open and transparent review of its national report and the Reports of other Contracting Parties; and a commitment to a continuous learning and improving process, something which is a key element of a strong safety culture. The peer review of national reports takes place every three years, the first having been held in 1999. The Second Review Meeting was attended by delegates from 46 contracting parties. During the review certain issues were

  6. Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

  7. A review of the nuclear safety activities in Italy

    International Nuclear Information System (INIS)

    Merelli, A.

    1989-01-01

    A review of research programs carried out in Italy in the field of nuclear reactor safety was done in 1986, in the frame of the activities of the Commission of the European Communities, the International Energy Agency and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The report contains information on these programs, as well as information on the organization of safety research in Italy and the evolution of safety research programs

  8. Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings

    Energy Technology Data Exchange (ETDEWEB)

    DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

    2007-04-12

    This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope

  9. 77 FR 56698 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2012-09-13

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  10. 78 FR 66098 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2013-11-04

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  11. 75 FR 22892 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2010-04-30

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  12. 76 FR 59481 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2011-09-26

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  13. 77 FR 2603 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2012-01-18

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  14. 78 FR 2711 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2013-01-14

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  15. 76 FR 27168 - Air Traffic Procedures Advisory Committee

    Science.gov (United States)

    2011-05-10

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

  16. The standing advisory group on safeguards implementation

    International Nuclear Information System (INIS)

    Jennekens, J.H.F.

    1982-09-01

    In 1975 the Director General of the IAEA called together ten persons from member states with nuclear programs at varying stages of development to form the Standing Advisory Group on Safeguards Implementation. The group was later expanded to twelve. The Director General asked the group to evaluate the technical objectives of Agency safeguards, assess the effectiveness and efficiency of specific safeguards operating methods in meeting these technical objectives, advise on techniques to be employed in safeguards operations, and recommend areas where further work is needed. This paper reviews the work of the Standing Advisory Group on Safeguards Implementation since its formation in 1975, summarizes the subjects that have been examined and the advice rendered, and outlines the problem areas requiring further study

  17. 75 FR 9184 - Federal Advisory Committee; Advisory Council on Dependents' Education; Open Meeting

    Science.gov (United States)

    2010-03-01

    ... 102-3.150, the Department of Defense announces that the Advisory Council on Dependents' Education will... Advisory Council on Dependents' Education about its mission and functions. Written statements may be... Advisory Council on Dependents' Education, Mr. Charles Toth, telephone (703) 588-3105, 4040 North Fairfax...

  18. Healthcare Staff Wellbeing, Burnout, and Patient Safety: A Systematic Review.

    Directory of Open Access Journals (Sweden)

    Louise H Hall

    Full Text Available To determine whether there is an association between healthcare professionals' wellbeing and burnout, with patient safety.Systematic research review.PsychInfo (1806 to July 2015, Medline (1946 to July 2015, Embase (1947 to July 2015 and Scopus (1823 to July 2015 were searched, along with reference lists of eligible articles.Quantitative, empirical studies that included i either a measure of wellbeing or burnout, and ii patient safety, in healthcare staff populations.Forty-six studies were identified. Sixteen out of the 27 studies that measured wellbeing found a significant correlation between poor wellbeing and worse patient safety, with six additional studies finding an association with some but not all scales used, and one study finding a significant association but in the opposite direction to the majority of studies. Twenty-one out of the 30 studies that measured burnout found a significant association between burnout and patient safety, whilst a further four studies found an association between one or more (but not all subscales of the burnout measures employed, and patient safety.Poor wellbeing and moderate to high levels of burnout are associated, in the majority of studies reviewed, with poor patient safety outcomes such as medical errors, however the lack of prospective studies reduces the ability to determine causality. Further prospective studies, research in primary care, conducted within the UK, and a clearer definition of healthcare staff wellbeing are needed.This review illustrates the need for healthcare organisations to consider improving employees' mental health as well as creating safer work environments when planning interventions to improve patient safety.PROSPERO registration number: CRD42015023340.

  19. Analysis of the Convention on Nuclear Safety and Suggestions for Improvement

    International Nuclear Information System (INIS)

    Choi, K. S.; Viet, Phuong Nguyen

    2013-01-01

    The innovative approach of the Convention, which is based on incentive after than legal binding, had been considered successful in strengthening the nuclear safety worldwide. However, the nuclear accident at the Fukushima Dai-ichi Nuclear Power Plant (Japan) in March 2011 has exposed a number of weaknesses of the Convention. Given that context, this paper will analyse the characteristics of the CNS in order to understand the advantages and disadvantages of the Convention, and finally to suggest some possible improvements. The analysis in this paper shows that the incentive approach of the CNS has succeeded in facilitating the active roles of its Contracting Parties in making the National Reports and participating in the peer review of these reports. However, the incoherent quality of the National Reports, the different level of participation in the peer review process by different Contracting Parties, and the lack of transparency of the peer review have undermined the effectiveness of the Convention in strengthening the international safety regime as well as preventing serious regulatory errors that had happened in Japan before the Fukushima accident. Therefore, the peer review process should be reformed into a more transparent and independent direction, while an advisory group of regulators within the CNS might also be useful in improving the effectiveness of the Convention as already proven by the good practice in the European Union. Only with such effective change, the CNS can maintain its pivotal role in the international safety regime

  20. 76 FR 76740 - Secretary's Advisory Committee on Heritable Disorders in Newborns and Children; Notice of Meeting

    Science.gov (United States)

    2011-12-08

    ... (HRSA), and the Maternal and Child Health Bureau; (2) the history of the Advisory Committee; (3) an... Impact Workgroup for further evaluation; (4) reviewing the report on Linking Birth Certificates and..., presentations, and meeting materials can be found at the home page of the Advisory Committee's Web site at http...

  1. Comprehensive review of the maritime safety regimes.

    NARCIS (Netherlands)

    S. Knapp (Sabine); Ph.H.B.F. Franses (Philip Hans)

    2007-01-01

    textabstractThis report presents a comprehensive review of the maritime safety regimes and provides recommendations on how to improve the system. The results show a complex legal framework which generates a high amount of inspections and overlapping of inspection areas where no cross-recognition is

  2. SRTC criticality safety technical review of SRT-CMA-930039

    International Nuclear Information System (INIS)

    Rathbun, R.

    1993-01-01

    Review of SRT-CMA-930039, ''Nuclear Criticality Safety Evaluation (NCSE): DWPF Melter-Batch 1,'' December 1, 1993, has been performed by the Savannah River Technical Center (SRTC) Applied Physics Group. The NCSE is a criticality assessment of the Melt Cell in the DWPF. Additionally, this pertains only to Batch 1 operation, which differs from batches to follow. Plans for subsequent batch operations call for fissile material in the Salt Cell feed-stream, which necessitates a separate criticality evaluation in the future. The NCSE under review concludes that the process is safe from criticality events, even in the event that all lithium and boron neutron poisons are lost, provided uranium enrichments are less than 40%. Furthermore, if all the lithium and as much as 98% of the boron would be lost, uranium enrichments of 100% would be allowable. After a thorough review of the NCSE, this reviewer agrees with that conclusion. This technical review consisted of: an independent check of the methods and models employed, independent calculations application of ANSI/ANS 8.1, verification of WSRC Nuclear Criticality Safety Manual( 2 ) procedures

  3. Plant safety review from mass criticality accident

    International Nuclear Information System (INIS)

    Susanto, B.G.

    2000-01-01

    The review has been done to understand the resent status of the plant in facing postulated mass criticality accident. From the design concept of the plant all the components in the system including functional groups have been designed based on favorable mass/geometry safety principle. The criticality safety for each component is guaranteed because all the dimensions relevant to criticality of the components are smaller than dimensions of 'favorable mass/geometry'. The procedures covering all aspects affecting quality including the safety related are developed and adhered to at all times. Staff are indoctrinated periodically in short training session to warn the important of the safety in process of production. The plant is fully equipped with 6 (six) criticality detectors in strategic places to alert employees whenever the postulated mass criticality accident occur. In the event of Nuclear Emergency Preparedness, PT BATAN TEKNOLOGI has also proposed the organization structure how promptly to report the crisis to Nuclear Energy Control Board (BAPETEN) Indonesia. (author)

  4. 76 FR 1594 - Amador County Resource Advisory Committee

    Science.gov (United States)

    2011-01-11

    ... meeting the RAC will review project proposals submitted by the Forest Service and the public, listen to... and Community Self-Determination Act (Pub. L. 110-343) and in compliance with the Federal Advisory Committee Act. Project proposals will be discussed and voted on to determine which projects will be...

  5. Tank waste remediation system nuclear criticality safety program management review

    International Nuclear Information System (INIS)

    BRADY RAAP, M.C.

    1999-01-01

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

  6. A Review of General Aviation Safety (1984-2017).

    Science.gov (United States)

    Boyd, Douglas D

    2017-07-01

    General aviation includes all civilian aviation apart from operations involving paid passenger transport. Unfortunately, this category of aviation holds a lackluster safety record, accounting for 94% of civil aviation fatalities. In 2014, of 1143 general aviation accidents, 20% were fatal compared with 0 of 29 airline mishaps in the United States. Herein, research findings over the past 30 yr will be reviewed. Accident risk factors (e.g., adverse weather, geographical region, post-impact fire, gender differences) will be discussed. The review will also summarize the development and implementation of stringent crashworthiness designs with multi-axis dynamic testing and head-injury protection and its impact on mitigating occupant injury severity. The benefits and drawbacks of new technology and human factor considerations associated with increased general aviation automation will be debated. Data on the safety of the aging general aviation population and increased drug usage will also be described. Finally, areas in which general aviation occupant survival could be improved and injury severity mitigated will be discussed with the view of equipping aircraft with 1) crash-resistant fuel tanks to reduce post-impact conflagration; 2) after-market ballistic parachutes for older aircraft; and 3) current generation electronic locator beacons to hasten site access by first responders.Boyd DD. A review of general aviation safety (1984-2017). Aerosp Med Hum Perform. 2017; 88(7):657-664.

  7. International experts conclude IAEA peer review of Iran's safety regulation of Bushehr NPP

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of nuclear safety experts today completed an IAEA mission to review the effectiveness of Iran's safety regulation of its first nuclear power plant and to identify possible improvements before the plant begins operation. Upon invitation of the Islamic Republic of Iran, the International Atomic Energy Agency (IAEA) assembled a team of senior regulators from seven Member States for an Integrated Regulatory Review Service (IRRS) mission. The scope of the mission was limited to the safety regulation of Bushehr nuclear power plant (BNPP-1). The IRRS review took place from 20 February to 2 March at the INRA offices in Tehran and included a technical visit to the BNPP-1 site. The mission was an objective peer review based on IAEA safety standards, and was neither an inspection, nor an audit. Ms. Olena Mykolaichuk, IRRS Team Leader and Head of the State Nuclear Regulatory Committee of Ukraine, commended her INRA counterparts: 'The regulatory work performed on the Bushehr construction and in preparation for commissioning has demonstrated significant progress of INRA as a nuclear regulatory authority,' she said. Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division, added: 'Through this IRRS mission, both Iran and the international experts contribute to the enhancement of nuclear safety and worldwide experience sharing.' In the course of its review the IRRS team identified the following strengths: - INRA has a dedicated, conscientious staff, demonstrating clear commitments to further improvements. - INRA clearly recognizes the value of peer reviews and international cooperation regarding nuclear safety. - Despite a shortage of staff, INRA demonstrated strong leadership while performing both review and assessment and inspection tasks during the BNPP-1 construction and pre-commissioning. - INRA has developed an excellent computerized documentation control system. Recommendations and suggestions to improve INRA's regulatory

  8. OSART Guidelines. 2015 Edition. Reference Report for IAEA Operational Safety Review Teams (OSARTs)

    International Nuclear Information System (INIS)

    2016-01-01

    The IAEA works to provide a global nuclear safety and security framework for the protection of people and the environment from the effects of ionizing radiation, the minimization of the likelihood of accidents that could endanger life and property, and effective mitigation of the effects of any such events, should they occur. The strategic approach to achieving such a framework involves continual improvement in four areas: national and international safety infrastructures; the establishment and global acceptance of IAEA safety standards; an integrated approach to the provision for the application of the safety standards; and a global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. Conservative design, careful manufacture and sound construction are all prerequisites for the safe operation of nuclear power plants. However, the safety of the plant also depends ultimately on: sound management, policies, procedures, processes and practices; the capability and reliability of commissioning and operating personnel; comprehensive instructions; sound accident management and emergency preparedness; and adequate resources. Finally, a positive attitude and conscientiousness on the part of all staff in discharging their responsibilities is important to safety. The OSART programme is based on the safety standards applicable to nuclear power plants. IAEA safety standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Group identify important current nuclear safety issues and also serve as references during an OSART review. The publication OSART Guidelines provides overall guidance on the conduct of OSART

  9. Review of actinide nitride properties with focus on safety aspects

    Energy Technology Data Exchange (ETDEWEB)

    Albiol, Thierry [CEA Cadarache, St Paul Lez Durance Cedex (France); Arai, Yasuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-12-01

    This report provides a review of the potential advantages of using actinide nitrides as fuels and/or targets for nuclear waste transmutation. Then a summary of available properties of actinide nitrides is given. Results from irradiation experiments are reviewed and safety relevant aspects of nitride fuels are discussed, including design basis accidents (transients) and severe (core disruptive) accidents. Anyway, as rather few safety studies are currently available and as many basic physical data are still missing for some actinide nitrides, complementary studies are proposed. (author)

  10. 76 FR 52642 - Notice of Advisory Committee Closed Meeting; U.S. Strategic Command Strategic Advisory Group

    Science.gov (United States)

    2011-08-23

    ... DEPARTMENT OF DEFENSE Notice of Advisory Committee Closed Meeting; U.S. Strategic Command Strategic Advisory Group AGENCY: Department of Defense. ACTION: Notice of Advisory Committee closed meeting.... Strategic Command Strategic Advisory Group. DATES: November 1, 2011, from 8 a.m. to 5 p.m. and November 2...

  11. Aviation and healthcare: a comparative review with implications for patient safety.

    Science.gov (United States)

    Kapur, Narinder; Parand, Anam; Soukup, Tayana; Reader, Tom; Sevdalis, Nick

    2016-01-01

    Safety in aviation has often been compared with safety in healthcare. Following a recent article in this journal, the UK government set up an Independent Patient Safety Investigation Service, to emulate a similar well-established body in aviation. On the basis of a detailed review of relevant publications that examine patient safety in the context of aviation practice, we have drawn up a table of comparative features and a conceptual framework for patient safety. Convergence and divergence of safety-related behaviours across aviation and healthcare were derived and documented. Key safety-related domains that emerged included Checklists, Training, Crew Resource Management, Sterile Cockpit, Investigation and Reporting of Incidents and Organisational Culture. We conclude that whilst healthcare has much to learn from aviation in certain key domains, the transfer of lessons from aviation to healthcare needs to be nuanced, with the specific characteristics and needs of healthcare borne in mind. On the basis of this review, it is recommended that healthcare should emulate aviation in its resourcing of staff who specialise in human factors and related psychological aspects of patient safety and staff wellbeing. Professional and post-qualification staff training could specifically include Cognitive Bias Avoidance Training, as this appears to play a key part in many errors relating to patient safety and staff wellbeing.

  12. 75 FR 81268 - Science Advisory Board Staff Office; Notification of Two Public Quality Review Teleconferences of...

    Science.gov (United States)

    2010-12-27

    ... ``Reactive Nitrogen in the United States; an Analysis of Inputs, Flows, Consequences, and Management Options... information concerning the EPA Science Advisory Board can be found on the SAB Web site at http://www.epa.gov... information about this advisory activity can be found on the SAB Web site at http://yosemite.epa.gov/sab...

  13. Classification of antecedents towards safety use of health information technology: A systematic review.

    Science.gov (United States)

    Salahuddin, Lizawati; Ismail, Zuraini

    2015-11-01

    This paper provides a systematic review of safety use of health information technology (IT). The first objective is to identify the antecedents towards safety use of health IT by conducting systematic literature review (SLR). The second objective is to classify the identified antecedents based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model and an extension of DeLone and McLean (D&M) information system (IS) success model. A systematic literature review (SLR) was conducted from peer-reviewed scholarly publications between January 2000 and July 2014. SLR was carried out and reported based on the preferred reporting items for systematic reviews and meta-analyses (PRISMA) statement. The related articles were identified by searching the articles published in Science Direct, Medline, EMBASE, and CINAHL databases. Data extracted from the resultant studies included are to be analysed based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model, and also from the extended DeLone and McLean (D&M) information system (IS) success model. 55 articles delineated to be antecedents that influenced the safety use of health IT were included for review. Antecedents were identified and then classified into five key categories. The categories are (1) person, (2) technology, (3) tasks, (4) organization, and (5) environment. Specifically, person is attributed by competence while technology is associated to system quality, information quality, and service quality. Tasks are attributed by task-related stressor. Organisation is related to training, organisation resources, and teamwork. Lastly, environment is attributed by physical layout, and noise. This review provides evidence that the antecedents for safety use of health IT originated from both social and technical aspects. However, inappropriate health IT usage potentially increases the incidence of errors and produces new safety risks. The review cautions future

  14. 41 CFR 128-1.8009 - Review of Seismic Safety Program.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Review of Seismic Safety Program. 128-1.8009 Section 128-1.8009 Public Contracts and Property Management Federal Property Management Regulations System (Continued) DEPARTMENT OF JUSTICE 1-INTRODUCTION 1.80-Seismic Safety Program...

  15. Waste management advisory missions to developing countries

    International Nuclear Information System (INIS)

    Thomas, K.T.

    1990-01-01

    The IAEA's Waste Management Advisory Programme (WAMAP) was initiated in 1987 as an interregional technical co-operation project to complement other activities in radioactive waste management. Its creation gave greater recognition to the importance of the safe management of radioactive wastes and promotion of long-term waste management technical assistance strategies for developing countries. Over the past 4 years, international experts have reviewed the radioactive waste management programmes of 29 developing countries. Missions have been conducted within the framework of the IAEA's Waste Management Advisory Programme (WAMAP). Ten of these countries have nuclear power plants in operation or under construction or have nuclear fuel cycle facilities. Altogether, 23 have research reactors or centres, eight have uranium or thorium processing programmes or wastes, and nine essentially have only isotope applications involving the use of radiation sources

  16. Status and trends in spent fuel reprocessing. Proceedings of an advisory group meeting

    International Nuclear Information System (INIS)

    1999-08-01

    Spent fuel management has always been an important part of the nuclear fuel cycle and is still one of the most important activities in all countries exploiting the peaceful use of nuclear energy. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to coordinate and encourage closer co-operation among Member States in certain research and developing activities that are of common interest. As part of spent fuel management, reprocessing activities have been reviewed from time to time on a low profile level under the terminology 'spent fuel treatment'. However, spent fuel treatment covers, in broad terms, spent fuel storage (short, interim and long term), fuel rod consolidation, reprocessing and, in case the once-through cycle is selected, conditioning of the spent fuel for disposal. Hence the reprocessing activities under the heading 'spent fuel treatment' were somewhat misleading. Several meetings on spent fuel treatment have been organized during the fast decade: an Advisory Group meeting (AGM) in 1992, a Technical Committee meeting in 1995 and recently an Advisory Group meeting from 7 to 10 September 1998. The objectives of the meetings were to review the status and trends of spent fuel reprocessing, to discuss the environmental impact and safety aspects of reprocessing facilities and to define the most important issues in this field. Notwithstanding the fact that the Summary of the report does not include aspects of military reprocessing, some of the national presentations do refer to some relevant aspects (e.g. experience, fissile stockpiles)

  17. Report of the summative evaluation by the advisory committee on research and development of nuclear energy technology

    International Nuclear Information System (INIS)

    2005-03-01

    The Research Evaluation Committee of the Japan Atomic Energy Research Institute (JAERI) set up an advisory Committee on Research and Development of Nuclear Energy Technology in accordance with the 'Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations. The Advisory Committee on Research and Development of Nuclear Energy Technology evaluated the adequacy of the plans of safety research to be succeeded from JAERI to a new research institute which will be established by integration of JAERI and the Japan Nuclear Cycle Development Institute (JNC). The Advisory Committee consisted of nine specialists from outside the JAERI conducted its activities from July 2004 to August 2004. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Advisory Committee meeting which was held on August 10, 2004, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Advisory Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on December 1, 2004. This report describes the result of the evaluation by the Advisory Committee on Research and Development on Nuclear Energy Technology. (author)

  18. Idaho National Laboratory Integrated Safety Management System FY 2012 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Farren Hunt

    2012-12-01

    Idaho National Laboratory (INL) performed an Annual Effectiveness Review of the Integrated Safety Management System (ISMS), per 48 Code of Federal Regulations (CFR) 970.5223 1, “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and identified target areas for focused improvements and assessments for fiscal year (FY) 2013. Results of the FY 2012 annual effectiveness review demonstrated that the INL’s ISMS program was significantly strengthened. Actions implemented by the INL demonstrate that the overall Integrated Safety Management System is sound and ensures safe and successful performance of work while protecting workers, the public, and environment. This report also provides several opportunities for improvement that will help further strengthen the ISM Program and the pursuit of safety excellence. Demonstrated leadership and commitment, continued surveillance, and dedicated resources have been instrumental in maturing a sound ISMS program. Based upon interviews with personnel, reviews of assurance activities, and analysis of ISMS process implementation, this effectiveness review concludes that ISM is institutionalized and is “Effective”.

  19. Overview of the periodic safety review of nuclear power plants as practised in India

    International Nuclear Information System (INIS)

    Jhamb, N.K.; Chande, S.K.

    1997-01-01

    In India, routine and periodic safety reviews of nuclear facilities are carried out through a multitiered hierarchy of committees at the plant level, the operating organization level and the regulatory body level. In 1993, it was decided by the Atomic Energy Regulatory Board (AERB, the regulatory body) that, as a policy, authorization for operation of nuclear power plants (NPPs) shall have a validity period of 5 years, after which this authorization will have to be renewed. NPPs have to carry out a self-assessment according to an established procedure, prepare a Safety Assessment Report for Renewal of Authorization (SARRA) and submit it to the AERB for review. The procedure defines the objectives of the report and gives guidelines on the required review of the self-assessment of the operational plant safety. The paper discusses the objectives, the elements of the SARRA review, the review process, the SARRA review carried out in 1993-1994, the basis for acceptability of continued plant operation, and the lessons learned for future periodic safety reviews in India and for exchange of operating experience feedback. (author)

  20. 78 FR 21911 - Environmental Technologies Trade Advisory Committee Public Meeting

    Science.gov (United States)

    2013-04-12

    ... DEPARTMENT OF COMMERCE International Trade Administration Environmental Technologies Trade... meeting of the Environmental Technologies Trade Advisory Committee (ETTAC). DATES: The meeting is... review the role of the U.S. government in supporting the early adoption of environmental technologies and...

  1. Compliant flooring to prevent fall-related injuries in older adults: A scoping review of biomechanical efficacy, clinical effectiveness, cost-effectiveness, and workplace safety.

    Science.gov (United States)

    Lachance, Chantelle C; Jurkowski, Michal P; Dymarz, Ania C; Robinovitch, Stephen N; Feldman, Fabio; Laing, Andrew C; Mackey, Dawn C

    2017-01-01

    Compliant flooring, broadly defined as flooring systems or floor coverings with some level of shock absorbency, may reduce the incidence and severity of fall-related injuries in older adults; however, a lack of synthesized evidence may be limiting widespread uptake. Informed by the Arksey and O'Malley framework and guided by a Research Advisory Panel of knowledge users, we conducted a scoping review to answer: what is presented about the biomechanical efficacy, clinical effectiveness, cost-effectiveness, and workplace safety associated with compliant flooring systems that aim to prevent fall-related injuries in healthcare settings? We searched academic and grey literature databases. Any record that discussed a compliant flooring system and at least one of biomechanical efficacy, clinical effectiveness, cost-effectiveness, or workplace safety was eligible for inclusion. Two independent reviewers screened and abstracted records, charted data, and summarized results. After screening 3611 titles and abstracts and 166 full-text articles, we included 84 records plus 56 companion (supplementary) reports. Biomechanical efficacy records (n = 50) demonstrate compliant flooring can reduce fall-related impact forces with minimal effects on standing and walking balance. Clinical effectiveness records (n = 20) suggest that compliant flooring may reduce injuries, but may increase risk for falls. Preliminary evidence suggests that compliant flooring may be a cost-effective strategy (n = 12), but may also result in increased physical demands for healthcare workers (n = 17). In summary, compliant flooring is a promising strategy for preventing fall-related injuries from a biomechanical perspective. Additional research is warranted to confirm whether compliant flooring (i) prevents fall-related injuries in real-world settings, (ii) is a cost-effective intervention strategy, and (iii) can be installed without negatively impacting workplace safety. Avenues for future research are

  2. Assessment of basic safety issues

    International Nuclear Information System (INIS)

    Queniart, D.

    1996-01-01

    Work on the French-German common safety approach for future nuclear power plants continued in 1994 to allow for more detailed discussion of some major issues, taking into account the options provided by the industry for the EPR (European Pressurized water Reactor) project, as described in the document entitled 'Conceptual Safety Features Review File'. Seven meetings of a GPR/RSK advisory experts subgroup, six GPR/RSK plenary sessions and six meetings of the safety authorities (DFD) dealt with the following topics: design of the systems and use of probabilistic approaches, application of a 'break preclusion' approach to the main primary pipings, protection against external hazards (aircraft crashes, explosions, earthquakes), provisions with respect to accidents involving core melt and to containment design, radiological consequences of reference accidents and accidents involving core melt at low pressure. The important aspects of the joint policy are recalled in the presentation. The whole set of GPR/RSK recommendations were agreed by the French and German safety authorities during the DFD meetings of 1994 and early 1995. The utilities decided to begin the basic design phase in February, 1995. Work is now continuing to develop the common French-German approach for future nuclear power plants, in the same way as before. In 1995, this mainly covers the design of the containment and of the systems, but also new issues such as the protection against secondary side overpressurization, radiological protection of workers and radioactive wastes. (J.S.). 3 figs., 1 tab

  3. IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

  4. Safety inspections to TRIGA reactors

    International Nuclear Information System (INIS)

    Byszewski, W.

    1988-01-01

    The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

  5. 76 FR 7815 - Renewable Energy and Energy Efficiency Advisory Committee

    Science.gov (United States)

    2011-02-11

    ... DEPARTMENT OF COMMERCE International Trade Administration Renewable Energy and Energy Efficiency... of an open meeting. SUMMARY: The Renewable Energy and Energy Efficiency Advisory Committee (RE&EEAC... programs support the competitiveness of U.S. renewable energy and energy efficiency companies, to review...

  6. 75 FR 13294 - National Boating Safety Advisory Council

    Science.gov (United States)

    2010-03-19

    ... the strategic planning process and any new issues or factors that could impact, or contribute to, the...) Recreational Boating Safety Strategic Planning Subcommittee meeting. Saturday, April 17, 2010: (12) Recreational Boating Safety Strategic Planning Subcommittee meeting (Cont.). (13) Prevention through People...

  7. 75 FR 63255 - Air Traffic Procedures Advisory Committee Meeting

    Science.gov (United States)

    2010-10-14

    ...The FAA is issuing this notice to advise the public that a meeting of the Federal Aviation Administration Air Traffic Procedures Advisory Committee (ATPAC) will be held to review present air traffic control procedures and practices for standardization, revision, clarification, and upgrading of terminology and procedures.

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

    International Nuclear Information System (INIS)

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

    1990-08-01

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

  9. International Expert Review of Sr-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Sagar, Budhi (Center for Nuclear Waste Regulatory Analyses, Southwest Research Inst., San Antonio, TX (US)); Egan, Michael (Quintessa Limited, Henley-on-Thames (GB)); Roehlig, Klaus-Juergen (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (DE)); Chapman, Neil (Independent Consultant (XX)); Wilmot, Roger (Galson Sciences Limited, Oakham (GB))

    2008-03-15

    In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The purposes of the SR-Can project were stated in the main project report to be: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's research and development (R and D) programme, to further site investigations and to future safety assessments. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. To help inform their review of SKB's proposed approach to development of the longterm safety case, the authorities appointed three international expert review teams to carry out a review of SKB's SR-Can safety assessment report. Comments from one of these teams - the Safety Assessment Methodology (SAM) review team - are presented in this document. The SAM review team's scope of work included an examination of SKB's documentation of the assessment ('Long-term safety for KBS-3 Repositories at Forsmark and Laxemar - a first evaluation' and several supporting reports) and hearings with SKB staff and contractors, held in March 2007. As directed by SKI and SSI, the SAM review team focused on methodological aspects and sought to determine whether SKB's proposed safety assessment methodology is likely to be suitable for use in the future SR-Site and to assess its consistency with the Swedish regulatory framework. No specific evaluation of long-term safety or site acceptability was undertaken by any of the review teams. SKI and SSI's Terms of Reference for the SAM

  10. 77 FR 25706 - Notice of Advisory Committee Closed Meeting; U.S. Strategic Command Strategic Advisory Group

    Science.gov (United States)

    2012-05-01

    ... DEPARTMENT OF DEFENSE Notice of Advisory Committee Closed Meeting; U.S. Strategic Command Strategic Advisory Group AGENCY: Department of Defense. ACTION: Notice of Advisory Committee closed meeting.... [[Page 25707

  11. SSI and SKI's Review of SKB's Updated Final Safety Report for SFR 1. Review Report

    International Nuclear Information System (INIS)

    2003-10-01

    The Repository for Radioactive Operational Waste (SFR 1) is now the object of a new review by the Swedish Radiation Protection Authority (SSI) and the Swedish Nuclear Power Inspectorate (SKI). One of the stipulations for operating SFR 1 was that a new assessment of the long-term performance and environmental consequences of the repository should be conducted once every 10 years by the licensee, the Swedish Nuclear Fuel and Waste Management Co (SKB). During the time that SFR 1 has been in operation, experience has been gained of operating the facility and new knowledge of long-term performance of SFR 1 has been obtained. New regulations for nuclear facilities have been promulgated since SFR 1 was taken into operation (1988). A review committee comprising employees from SKI and SSI has conducted the review of SSR 2001. This review report has resulted in the committee's evaluation of the safety of SFR 1 and is the basis of the regulatory authorities' decision concerning any amendments to the stipulations for the operation of SFR 1. However, the review has found deficiencies in the follow up of the development of design basis norms since the facility was constructed as well as deficiencies in learning from operating experience. However, the overall evaluation is that the facility is being operated in an acceptable manner from the standpoint of safety. With respect to the long-term performance of the repository, it is a deficiency that SSR 2001 does not describe how compliance with the stipulated radiation protection requirements on optimisation and use of the best available technology (BAT) is achieved during operation. In the opinion of the review committee, issues relating to occupational radiation protection are being handled satisfactorily and the operational releases of radioactive substances are very small. Safety and Radiation Protection after Closure SKB's long-term repository performance assessment contains essential updates and improvements compared with the

  12. A Review of Research on Driving Styles and Road Safety.

    Science.gov (United States)

    Sagberg, Fridulv; Selpi; Piccinini, Giulio Francesco Bianchi; Engström, Johan

    2015-11-01

    The aim of this study was to outline a conceptual framework for understanding driving style and, on this basis, review the state-of-the-art research on driving styles in relation to road safety. Previous research has indicated a relationship between the driving styles adopted by drivers and their crash involvement. However, a comprehensive literature review of driving style research is lacking. A systematic literature search was conducted, including empirical, theoretical, and methodological research, on driving styles related to road safety. A conceptual framework was proposed whereby driving styles are viewed in terms of driving habits established as a result of individual dispositions as well as social norms and cultural values. Moreover, a general scheme for categorizing and operationalizing driving styles was suggested. On this basis, existing literature on driving styles and indicators was reviewed. Links between driving styles and road safety were identified and individual and sociocultural factors influencing driving style were reviewed. Existing studies have addressed a wide variety of driving styles, and there is an acute need for a unifying conceptual framework in order to synthesize these results and make useful generalizations. There is a considerable potential for increasing road safety by means of behavior modification. Naturalistic driving observations represent particularly promising approaches to future research on driving styles. Knowledge about driving styles can be applied in programs for modifying driver behavior and in the context of usage-based insurance. It may also be used as a means for driver identification and for the development of driver assistance systems. © 2015, Human Factors and Ergonomics Society.

  13. 77 FR 38768 - Smart Grid Advisory Committee

    Science.gov (United States)

    2012-06-29

    ...The Smart Grid Advisory Committee (SGAC or Committee) will hold a meeting via teleconference on Friday, July 27, 2012 from 11 a.m. to 2 p.m. Eastern Time (ET). The primary purposes of this meeting are to review updates on the Smart Grid Interoperability Panel transition plan, review the status of the research subcommittee and the August Smart Grid Workshop in Boulder, Colorado, and plan for a fall meeting. Interested members of the public will be able to participate in the meeting from remote locations by calling into a central phone number.

  14. INSAG's ongoing work on nuclear, radiation and waste safety

    International Nuclear Information System (INIS)

    Baer, A.J.

    1999-01-01

    The International Nuclear Safety Advisory Group (INSAG) is an advisory group to the Director General of the IAEA. It identifies current nuclear safety issues, draws conclusions from its analyses and gives advice on those issues. INSAG is currently working on four documents: a complete revision of INSAG-3, the classical paper on safety principles for nuclear plants, published in 1988; 'Safety Management', the effective system for the management of operational strategy; 'Safe Management of the Life Cycle of Nuclear Power Plants'; and the fourth document in preparation entitled 'The Safe Management of Sources of Radiation: Principles and Strategies'. The fourth document is aimed primarily at political decision makers who have no knowledge of radiation safety or of nuclear matters generally but are called upon to make important decisions in this field. INSAG has attempted to present them with a 'unified doctrine' of the management of all radiation sources, even though, for historical reasons radiation protection and nuclear safety have evolved largely independently of each other. The major conclusion to be drawn from the paper is that a systematic application of protection and safety principles, and of appropriate strategies, goes a long way towards ensuring the safe management of technologies involving radiation. Furthermore, the management of sources of radiation could benefit from the experience accumulated in other industries facing comparable challenges

  15. Immunization Safety Review: Thimerosal - Containing Vaccines and Neurodevelopmental Disorders

    National Research Council Canada - National Science Library

    Stratton, Kathleen; Gable, Alicia; McCormick, Marie C

    2001-01-01

    In this report, the Immunization Safety Review committee examines the hypothesis of whether or not the use of vaccines containing the preservative thimerosal can cause neurodevelopmental disorders (NDDs...

  16. Review of SKB's Safety Assessment SR-Can: Contributions in Support of SKI's and SSI's Review by External Consultants

    International Nuclear Information System (INIS)

    2008-03-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety report, SR-Site, on the repository's long-term safety and radiological consequences. As a preparation for SR-Site, SKB published the preliminary safety assessment SR-Can in November 2006. The purposes were to document a first evaluation of long-term safety for the two candidate sites at Forsmark and Laxemar and to provide feedback to SKB's future programme of work. An important objective of the authorities' review of SR-Can is to provide guidance to SKB on the complete safety reporting for the license application. The authorities have engaged external experts for independent modelling, analysis and review, with the aim to provide a range of expert opinions related to the sufficiency and appropriateness of various aspects of SR-Can. The conclusions and judgments in this report are those of the authors and may not necessarily coincide with those of SKI and SSI. The authorities own review will be published separately (SKI Report 2008:23, SSI Report 2008:04 E). This report compiles contributions from several specific research projects. The separate reviews cover topics regarding the engineered barrier system, the quality assurance, the climate evolution and its effects, and the ecosystems and environmental impacts. All contributions are in English apart from the review concerning ecosystems and environmental impacts, which is presented in Swedish

  17. A probabilistic safety assessment PEER review: Case study on the use of probabilistic safety assessment for safety decisions

    International Nuclear Information System (INIS)

    1989-10-01

    The purpose of this case study is to illustrate, using an actual example, the organizing and carrying out of an independent peer review of a draft full-scope (level 3) probabilistic safety assessment. The specific findings of the peer review are of less importance than the approach taken, the interaction between sponsor and study team, and the technical and administrative issues that can arise during a peer review. This case study will examine the following issues: how the scope of the peer review was established, based on how it was to be used by the review sponsoring body; how the level of effort was determined, and what this determination meant for the technical quality of the review; how the team of peer reviewers was selected; how the review itself was carried out; what findings were made; what was done with these findings by both the review sponsoring body and the PSA analysis team. 9 refs, 2 figs, 1 tab

  18. 78 FR 41991 - Pipeline Safety: Potential for Damage to Pipeline Facilities Caused by Flooding

    Science.gov (United States)

    2013-07-12

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice; Issuance of Advisory... Gas and Hazardous Liquid Pipeline Systems. Subject: Potential for Damage to Pipeline Facilities Caused...

  19. 75 FR 22678 - Pipeline Safety: Implementation of Electronic Filing for Recently Revised Incident/Accident...

    Science.gov (United States)

    2010-04-29

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Liquid Systems AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice; Issuance of Advisory Bulletin. SUMMARY: This notice advises owners and operators of gas pipeline...

  20. IAEA Completes Nuclear Security Advisory Mission in France

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts today completed a nuclear security advisory mission in France. The mission was carried out at the request of the French Government. The scope of the two-week International Physical Protection Advisory Service (IPPAS) follow-up mission included France’s responses to the recommendations of the initial mission in 2011, the regulatory framework for the security of nuclear material and facilities as well as computer security. The IPPAS team also reviewed the country’s implementation of the 2005 Amendment to the Convention on the Physical Protection of Nuclear Material (CPPNM). As part of the review, the team visited the Georges Besse II uranium enrichment plant at the Tricastin nuclear site in Pierrelatte, south-eastern France. The team observed that the nuclear security regime in France is robust and well-established, and incorporates the fundamental principles of the amended CPPNM. The team provided recommendations and suggestions to support France in enhancing and sustaining nuclear security. Good practices were identified that can serve as examples to other IAEA Member States to help strengthen their nuclear security activities.