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 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

  3. 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

  4. 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

  5. 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...

  6. 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...

  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. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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.

  10. 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...

  11. 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...

  12. Nuclear Safety advisory committee (NSAC)

    International Nuclear Information System (INIS)

    1999-01-01

    The NNSA convened the 16th NSAC meeting in 1999. The Committee listened to the report by the NNSA relating to the fault of core barrel at the QNPP. And also the NNSA convened the 17th NSAC meeting in Beijing. The Committee listened to the report by the NNSA relating to the review and assessment on the application of CP at the JTNPP and discussed on the granting of CP and the related license conditions at the JTNPP. The Sub-Committee of NSAC of the NNSA on siting convened and enlarged meeting for a consulting with the domestic experts on the issue of seismic response spectrum in design at the JTNPP

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  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 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...

  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. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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.

  4. 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

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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

  10. 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...

  11. 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.

  12. 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)

  13. 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

  14. 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.

  15. 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

  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. 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

  18. 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

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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

  5. 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...

  6. 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...

  7. 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...

  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. 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...

  10. 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

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. Review of safety assessment methods. A report of the performance assessment advisory group of the radioactive waste management committee OECD Nuclear Energy Agency

    International Nuclear Information System (INIS)

    1991-01-01

    The disposal of radioactive waste is a major issue in the nuclear debate. This report provides a concise and accessible overview of the methods available for evaluating the long-term safety of radioactive waste disposal systems, particularly those to be built in deep geological formations

  10. 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

  11. 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).

  12. 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).

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  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 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...

  19. 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

  20. 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.

  1. 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...

  2. 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)

  3. 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...

  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 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...

  6. 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...

  7. 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...

  8. AGI Safety Literature Review

    OpenAIRE

    Everitt, Tom; Lea, Gary; Hutter, Marcus

    2018-01-01

    The development of Artificial General Intelligence (AGI) promises to be a major event. Along with its many potential benefits, it also raises serious safety concerns (Bostrom, 2014). The intention of this paper is to provide an easily accessible and up-to-date collection of references for the emerging field of AGI safety. A significant number of safety problems for AGI have been identified. We list these, and survey recent research on solving them. We also cover works on how best to think of ...

  9. 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

  10. 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...

  11. 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

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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

  17. 76 FR 67020 - Railroad Safety Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2011-10-28

    ... Device Distraction, Critical Incident, Track Safety Standards, Dark Territory, Passenger Safety, and... requisite range of views and expertise necessary to discharge its responsibilities. See the RSAC Web site...

  18. Queensland Energy Advisory Council 1984 annual review

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    The Council consists of senior officials of Government Departments involved with various aspects of assessment, production, distribution and utilisation of energy resources. Noted in the annual review are functions of QEAC; activities; overview of Queensland's energy position; non renewable resources; coal; electricity; crude oil; natural gas; PGL; oil shale; uranium; renewable resources; solar energy; wind energy and biomass.

  19. Reviews on Food Safety

    International Nuclear Information System (INIS)

    Wilkins, E.

    2004-01-01

    Food safety is an increasing concern. The desire for rapid, specific methods for the detection of viable potential pathogens has grown into a necessity. Microbial contamination of meat, fresh fruits, and vegetables has become a mounting concern during the last decade due to emphasis on their importance in a healthy diet and the recognition of new food borne pathogens such as Campylobacter jejuni, Escherichia coli 0157:H7, and Listeria monocytogenes. This paper presents an overview of different commercial techniques for identification of bacteria such as: III-nitride on Silicon Chips for detection of live bacteria, Optical Biosensors, Piezoelectric-based acoustic wave devices, Electrochemical Biosensors, Immunogenic Techniques, Polymerase chain reaction

  20. Reviews on Food Safety

    Energy Technology Data Exchange (ETDEWEB)

    Wilkins, E [Department of Chemical and Nuclear Engineering. University orNew Mexico. 209 Farris Engineering Center. Albuquerque. NM 117131 (Ukraine)

    2004-07-01

    Food safety is an increasing concern. The desire for rapid, specific methods for the detection of viable potential pathogens has grown into a necessity. Microbial contamination of meat, fresh fruits, and vegetables has become a mounting concern during the last decade due to emphasis on their importance in a healthy diet and the recognition of new food borne pathogens such as Campylobacter jejuni, Escherichia coli 0157:H7, and Listeria monocytogenes. This paper presents an overview of different commercial techniques for identification of bacteria such as: III-nitride on Silicon Chips for detection of live bacteria, Optical Biosensors, Piezoelectric-based acoustic wave devices, Electrochemical Biosensors, Immunogenic Techniques, Polymerase chain reaction.

  1. 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...

  2. 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

  3. 77 FR 73734 - Railroad Safety Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-12-11

    ... by the Engineering and System Safety Task Forces. This agenda is subject to change, including the... National Transportation Safety Board, and the Federal Transit Administration. The diversity of the...

  4. 78 FR 26423 - Railroad Safety Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2013-05-06

    ... Engineering and System Safety Task Forces. This agenda is subject to change, including the possible addition... National Transportation Safety Board, and the Federal Transit Administration. The diversity of the...

  5. 77 FR 52393 - Railroad Safety Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-08-29

    ... provided by the Engineering and System Safety Task Forces, and a presentation on headwear will be provided... Safety Board, and the Federal Transit Administration. The diversity of the Committee ensures the...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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

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

    International Nuclear Information System (INIS)

    1982-02-01

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

  12. 77 FR 63849 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2012-10-17

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2012-0855] National Offshore Safety... November 7 and 8, 2012, in Houston, TX to discuss various issues related to safety of operations and other... public comments. ADDRESSES: The meetings will be held at the Marriott South Hobby Airport Hotel, 9100...

  13. 77 FR 17084 - National Boating Safety Advisory Council

    Science.gov (United States)

    2012-03-23

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2010-0164] National Boating Safety..., Virginia, to discuss issues relating to recreational boating safety. The meetings will be open to the... Arlington, 4610 N. Fairfax Drive, Arlington, VA 22203. The hotel's Web site is: http://www.hiarlington.com...

  14. 78 FR 18614 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2013-03-27

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2013-0182] National Offshore Safety... April 17 and 18, 2013, in New Orleans, LA, to discuss various issues related to safety of operations and... comments. ADDRESSES: The meetings will be held at the Wyndham Garden New Orleans Baronne Plaza Hotel, 201...

  15. 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...

  16. 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

  17. 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

  18. 77 FR 19054 - Railroad Safety Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-03-29

    ... Safety Standards, Critical Incident, Dark Territory, Fatigue Management, Risk Reduction, Electronic.... See the RSAC Web site for details on prior RSAC activities and pending tasks at: http://rsac.fra.dot...

  19. 78 FR 19277 - Navigation Safety Advisory Council; Meeting

    Science.gov (United States)

    2013-03-29

    ... regarding multiple risk assessments for U.S. ports and waterways. If you have been adversely affected by the... measures; marine information; diving safety; and aids to navigation systems. This notice corrects the...

  20. 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...

  1. 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

  2. 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)

  3. 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)

  4. 78 FR 19506 - National Boating Safety Advisory Council

    Science.gov (United States)

    2013-04-01

    ... teleconference and online webinar to discuss issues related to improving safety of recreational boating through... 19, 2013. ADDRESSES: The Subcommittee will meet via teleconference and online webinar. To participate... possible. Dated: Mar 26, 2013. David S. Fish, Captain, U.S. Coast Guard, Acting Director of Inspections and...

  5. 78 FR 36790 - Commercial Fishing Safety Advisory Committee; Vacancies

    Science.gov (United States)

    2013-06-19

    ... position); (c) a representative of education or training professionals related to fishing vessel safety or...) manufacturers of equipment for vessels to which Chapter 45 of Title 46, U.S.C. applies; (3) education or... Homeland Security (DHS) does not discriminate in employment on the basis of race, color, religion, sex...

  6. 77 FR 17491 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2012-03-26

    ... stemming from the Deepwater Horizon casualty event (2:30 p.m. to 5 p.m.). Day 2 The NOSAC will meet on... Safety and Environmental Enforcement (BSEE) concerning the status of their Deepwater Horizon... the event key. The meeting will be recorded by a court reporter. A transcript of the meeting and any...

  7. 76 FR 65205 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2011-10-20

    ... discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to...), 915 2nd Ave, Seattle, Washington 98174. For information on facilities or services for individuals with...., Monday through Friday, except Federal Holidays. The telephone number is 202-366-9329. Instructions: All...

  8. 78 FR 34115 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2013-06-06

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2013-0461] National Offshore Safety... Organization--Maritime Labour Convention of 2006, a task statement presented at the 17-18 April, 2013 NOSAC... SE., Washington, DC 20590-0001. We encourage use of electronic submissions because security screening...

  9. 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...

  10. 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

  11. 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

  12. 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)

  13. Nuclear Safety Research Review Committee

    International Nuclear Information System (INIS)

    Todreas, N.E.

    1990-01-01

    The Nuclear Safety Research Review Committee has had a fundamental difficulty because of the atmosphere that has existed since it was created. It came into existence at a time of decreasing budgets. For any Committee the easiest thing is to tell the Director what additional to do. That does not really help him a lot in this atmosphere of reduced budgets which he reviewed for you on Monday. Concurrently the research arm of Nuclear Regulatory Commission has recognized that the scope of its activity needed to be increased rather than decreased. In the last two-and-a-half-year period, human factors work was reinstated, radiation and health effects investigations were reinvigorated, research in the waste area was given significant acceleration. Further, accident management came into being, and the NRC finally got back into the TMI-2 area. So with all of those activities being added to the program at the same time that the research budget was going down, the situation has become very strained. What that leads to regarding Committee membership is a need for technically competent generalists who will be able to sit as the Division Directors come in, as the contractors come in, and sort the wheat from the chaff. The Committee needs people who are interested in and have a broad perspective on what regulatory needs are and specifically how safety research activities can contribute to them. The author summarizes the history of the Committee, the current status, and plans for the future

  14. 75 FR 27353 - Navigation Safety Advisory Council; Meeting

    Science.gov (United States)

    2010-05-14

    ... meet at the Courtyard by Marriott Washington Capitol Hill/Navy Yard Hotel, Admiral I and II Conference... online docket, USCG-2010-0387, at http://www.regulations.gov . FOR FURTHER INFORMATION CONTACT: Mr. Mike... Installations (OREI) NVIC 02-07 review. (3) Designation of ``narrow channels'' for Inland Navigation Rule 9...

  15. 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)

  16. 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)

  17. 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.

  18. 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

  19. 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...

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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)

  5. 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)

  6. 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.

  7. 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.

  8. 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)

  9. 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)

  10. 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.

  11. 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...

  12. 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)

  13. 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.

  14. 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...

  15. 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)

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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...

  1. 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

  2. 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.

  3. 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

  4. Potential exposure in nuclear safety. INSAG-9. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    1995-01-01

    The report defines potential exposure in terms of probability of its occurrence and possible consequences. Individual risk is expressed as the probability of the exposure and the conditional probability of death resulting from the exposure. Societal risk is more than the sum of individual risks. This report explores the relationship between individual risk and societal risk and the relevant criteria. For accidents causing serious damage to a nuclear power plant or having off-site consequences, individual risk is not sufficiently limiting because of the many aspects of societal impact. The approach to dealing with potential exposures in nuclear safety results in risks that are consistent with or more stringent than the ICRP's recommendations in its recent publications. 10 refs

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. REVIEW OF SAFETY AND TOLERANCE OF OMALIZUMAB

    Directory of Open Access Journals (Sweden)

    A.V. Emel'yanov

    2008-01-01

    Full Text Available The review of safety of monoclonal anti-ige-antibodies (xolair — a new medication for the treatment of severe allergic bronchial asthma is presented. Local and system adverse events, originating after injection of medicament in clinical studies and following administration in patients are discussed.Key words: children, bronchial asthma, monoclonal anti Ige antibodies.

  11. 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)

  12. 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)

  13. 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

  14. 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.

  15. 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...

  16. [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.

  17. Nuclear Safety Review for the Year 2006

    International Nuclear Information System (INIS)

    2007-07-01

    the various stakeholders effectively and efficiently. Related to this is the need for operators, users and regulatory bodies to communicate with the public effectively and in an open and transparent manner. The global nature of safety is reflected in the relevant international instruments, including conventions and codes of conduct, currently in place. All the international conventions related to safety welcomed additional contracting parties in 2006. During the year, the second review meeting took place for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The newly established Integrated Regulatory Review Service (IRRS) is contributing to the enhancement of Member States' legislative and regulatory infrastructure and the harmonization of regulatory approaches in nuclear, radiation, radioactive waste and transport safety. It is also one of the most effective feedback tools on the application of Agency standards that will be used for the further improvement of existing standards and guidance. In addition, the approach evaluates not only the policies and strategies, but also how efficient and effective they are regarding protection against all types of exposure. Therefore it is also a tool for information sharing and mutual learning on good policies and practices that can be used to reach harmonization step by step. Overall, the safety performance of the nuclear industry is good. However, there continue to be recurring events and there is a need to maintain vigilance. There is also a need for lessons learned to be transferred across the various sectors of the nuclear industry. Strong safety management and safety culture are vitally important for the continuation of this good performance. Leaders must ensure that personnel are properly trained and that adequate resources are available. The nuclear power industry around the world remains a safe and sound one with no worker or member of the public receiving a

  18. Nuclear Safety Review for the Year 2007

    International Nuclear Information System (INIS)

    2008-07-01

    In 2007, the 50th anniversary year of the Agency, the safety performance of the nuclear industry, on the whole, remained high, although incidents and accidents with no significant impact on public health and safety continue to make news headlines and challenge operators and regulators. It is therefore essential to maintain vigilance, continuously improve safety culture and enhance the international sharing and utilization of operating and other safety experience, including that resulting from natural events. The establishment and sustainability of infrastructures for all aspects of nuclear, radiation, transport and waste safety will remain a high priority. Member States embarking on nuclear power programmes will need to be active participants in the global nuclear safety regime. Harmonized safety standards, the peer review mechanism among contracting parties of the safety conventions, and sharing safety knowledge and best practices through networking are key elements for the continuous strengthening of the global nuclear safety regime. Technical and scientific support organizations (TSOs), whether part of the regulatory body or a separate organization, are gaining increased importance by providing the technical and scientific basis for safety related decisions and activities. There is a need for enhanced interaction and cooperation between TSOs. Academic and industrial expert communities also play a vital role in improving safety cooperation and capacity building. Countries embarking on nuclear power programmes, as well as countries expanding existing programmes, have to meet the challenge of building a technically qualified workforce. A vigorous knowledge transfer programme is key to capacity building - particularly in view of the ageing of experienced professionals in the nuclear field. National and regional safety networks, and ultimately a global safety network will greatly help these efforts. Changes in world markets and technology are having an impact on both

  19. 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)

  20. Nuclear safety review requirements for launch approval

    International Nuclear Information System (INIS)

    Sholtis, J.A. Jr.; Winchester, R.O.

    1992-01-01

    Use of nuclear power systems in space requires approval which is preceded by extensive safety analysis and review. This careful study allows an informed risk-benefit decision at the highest level of our government. This paper describes the process as it has historically been applied to U.S. isotopic power systems. The Ulysses mission, launched in October 1990, is used to illustrate the process. Expected variations to deal with reactor-power systems are explained

  1. 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)

  2. 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...

  3. Nuclear Safety Review for the Year 2008

    International Nuclear Information System (INIS)

    2009-07-01

    Nuclear technologies are increasingly seen as important solutions for meeting a number of challenges. Enabling the peaceful use of nuclear technology to support global energy demands and other human needs must be accompanied by deliberate, internationally-coordinated actions to minimize the potential for nuclear accidents and terrorism. While in recent years, the safety performance of the nuclear industry has been good, it is important to avoid any complacency. The Agency continues to support and promote the global nuclear safety and security regime as a framework for worldwide achievement of high levels of safety and security in nuclear activities. In 2008, three general themes can be observed from the global trends, issues and challenges in nuclear safety: the continuous improvements in strengthening safety worldwide through international cooperation; an expected increase of new entrant nuclear power programmes and the expansion of existing programmes; and safety and security synergy. Regarding continuous improvements to strengthen safety worldwide, the focus was on operating experience feedback and knowledge networking; and self-assessment and peer review. In the areas of new entrant nuclear programmes and expansion of existing nuclear programmes, activities centred on national safety infrastructures; human resources and capacity building; regulatory independence; nuclear incident and emergency preparedness and response; spent fuel and radioactive waste management; and multinational aspects of nuclear activities. In the area of safety and security synergy, in 2008 there was increasing awareness that processes need to be in place to ensure that safety activities do not compromise security and vice versa. As outlined in Safety Fundamentals No. SF-1, the prime responsibility for safety must rest with the person or organization responsible for facilities and activities that give rise to radiation risks. An effective legal and governmental framework for safety

  4. 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...

  5. 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

  6. 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.

  7. 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

  8. 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.

  9. Safety of human papillomavirus vaccines: a review.

    Science.gov (United States)

    Stillo, Michela; Carrillo Santisteve, Paloma; Lopalco, Pier Luigi

    2015-05-01

    Between 2006 and 2009, two different human papillomavirus virus (HPV) vaccines were licensed for use: a quadrivalent (qHPVv) and a bivalent (bHPVv) vaccine. Since 2008, HPV vaccination programmes have been implemented in the majority of the industrialized countries. Since 2013, HPV vaccination has been part of the national programs of 66 countries including almost all countries in North America and Western Europe. Despite all the efforts made by individual countries, coverage rates are lower than expected. Vaccine safety represents one of the main concerns associated with the lack of acceptance of HPV vaccination both in the European Union/European Economic Area and elsewhere. Safety data published on bivalent and quadrivalent HPV vaccines, both in pre-licensure and post-licensure phase, are reviewed. Based on the latest scientific evidence, both HPV vaccines seem to be safe. Nevertheless, public concern and rumors about adverse events (AE) represent an important barrier to overcome in order to increase vaccine coverage. Passive surveillance of AEs is an important tool for detecting safety signals, but it should be complemented by activities aimed at assessing the real cause of all suspect AEs. Improved vaccine safety surveillance is the first step for effective communication based on scientific evidence.

  10. 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)

  11. Nuclear Safety Review for the Year 2005

    International Nuclear Information System (INIS)

    2006-01-01

    In 2005, the Agency and its Director General were awarded the Nobel Peace Prize. The Nobel Committee statement recognizes the Agency's 'efforts to prevent nuclear energy from being used for military purposes and to ensure that nuclear energy for peaceful purposes is used in the safest possible way.' The global nature of safety is reflected in the relevant international legal instruments, both binding conventions and the non-binding codes of conduct currently in place. During the year, the third review meeting of the Contracting Parties to the Convention on Nuclear Safety as well as the third meeting of the representatives of the competent authorities under the Convention on Early Notification of a Nuclear Accident and Convention on Assistance in the Case of a Nuclear Accident or a Radiological Emergency took place. Improvements have been made in national legislation and regulatory infrastructure in many Member States in 2005. However, inadequate safety management and regulatory supervision of nuclear installations and use of ionizing radiation is a continuing issue in many Member States. A continuing challenge is to collect, analyse and disseminate safety experience and knowledge. Nuclear power plant (NPP) operational safety performance remained high throughout the world in 2005. Radiation doses to workers and members of the public due to NPP operation are well below regulatory limits. Personal injury accidents and incidents are among the lowest in industry. There were no accidents that resulted in the release of radiation that could adversely impact the environment. NPPs in many parts of the world have successfully coped with severe natural disaster conditions such as earthquakes, tsunamis, widespread river flooding and hurricanes. However, operational safety performance has been on a plateau for several years and concern has been expressed in many forums regarding the need to guard against complacency in the industry. Research reactors also maintained a good

  12. Nuclear Safety Review for the Year 2010

    International Nuclear Information System (INIS)

    2011-07-01

    The Agency, as a leading organization for promoting international cooperation among its Member States, is in a unique position to observe global trends, issues and challenges in nuclear safety and security through a wide variety of activities related to the establishment of safety standards and security guidelines and their application. The contents of this Nuclear Safety Review reflect the emerging nuclear safety trends, issues and challenges for 2010, as well as recapitulate the Agency's activities intended to further strengthen the global nuclear safety and security framework in all areas of nuclear, radiation, waste and transport safety. The accident at the Fukushima Daiichi Nuclear Power Plant, caused by the extraordinary disasters of the earthquake and tsunamis that struck Japan on 11 March 2011, continues to be assessed. As this report focuses on developments in 2010, the accident and its implications are not addressed here, but will be addressed in future reports of the Agency. The international nuclear community maintained a high level of safety performance in 2010. Nuclear power plant safety performance remained high, and indicated an improved trend in the number of emergency shutdowns as well in the level of energy available during these shutdowns. In addition, more States explored or expanded their interests in nuclear power programmes, and more faced the challenge of establishing the required regulatory infrastructure, regulatory supervision and safety management over nuclear installations and the use of ionizing radiation. Issues surrounding radiation protection and radioecology continued as trends in 2010. For example, increased public awareness of exposure to and environmental impacts of naturally occurring radioactive material (NORM) as well as nuclear legacy sites has led to increased public concern. In addition, human resources in radiation protection and radioecology have been lost as a result of retirement and of the migration of experts to

  13. Nuclear Safety Review for the Year 2009

    International Nuclear Information System (INIS)

    2010-07-01

    . A growing number of Member States are considering or have expressed interest in developing nuclear power programmes for the first time. Several countries have also embarked on ambitious plans for expanding their current programmes. The Agency's latest projections for the future of nuclear power by 2030 are higher than they were last year. Emerging international cooperative efforts in support of new and expanding nuclear power programmes have focused on many key issues. Such issues include gaps in national safety infrastructures, safety and security synergy and integration, and safety responsibilities and capacities for the various participants in a nuclear power programme, which include operators, regulators, government, suppliers, technical support organizations and relevant international organizations. Continued focus on cooperation for new and expanding nuclear power programmes is underscored by the fact that in some cases plans for nuclear programme development are moving faster than the establishment of the necessary safety infrastructure and capacity. Therefore, it is important that those countries of new and expanding nuclear power programmes actively participate in the global nuclear safety and security regime. As a result of the increasingly multinational nature of today's nuclear business and activities and associated technical and economic benefits, suppliers, operators, regulators and experts communities are making significant efforts towards the standardization and harmonization of equipment, components, methods and processes. As an example, the adoption by the European Union of a nuclear towards a harmonized approach to sustainable nuclear safety infrastructure worldwide. Similarly, international cooperation through conventions and codes of conduct, including associated peer review mechanisms, also provide for harmonized approaches to safety. Establishing and maintaining a regulatory body which is effectively independent in its decision making

  14. 75 FR 13785 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH); Request for Nominations

    Science.gov (United States)

    2010-03-23

    ... industries of the United States which include longshoring, marine terminals, and shipyard employment. The... providing safe and healthful employment in the maritime industries. The Secretary consults with MACOSH on... advisory committees. Nominees from all races, gender, age and disabilities are encouraged to apply...

  15. 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...

  16. 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

  17. Passenger safety, health, and comfort: a review.

    Science.gov (United States)

    Rayman, R B

    1997-05-01

    Since the birth of aviation medicine approximately 80 yrs ago, practitioners and scientists have given their attention primarily to flight deck crew, cabin crew, and ground support personnel. However, in more recent years we have broadened our horizons to include the safety, health, and comfort of passengers flying commercial aircraft. This will be even more compelling as more passengers take to the air in larger aircraft and flying longer hours to more distant destinations. Further, we can expect to see more older passengers because people in many countries are living longer, healthier lives. The author first discusses the stresses imposed by ordinary commercial flight upon travelers such as airport tumult, barometric pressure changes, immobility, jet lag, noise/ vibration, and radiation. Medical considerations are next addressed describing inflight illness and medical care capability aboard U.S. air carriers. Passenger safety, cabin air quality, and the preventive medicine aspects of air travel are next reviewed in the context of passenger safety, health, and comfort. Recommendations are addressed to regulator agencies, airlines aircraft manufacturers, and the aerospace medicine community.

  18. Nuclear Safety Review for the Year 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-15

    The contents of this Nuclear Safety Review reflect the emerging nuclear safety trends, issues and challenges for 2010, as well as recapitulate the Agency's activities intended to further strengthen the global nuclear safety and security framework in all areas of nuclear, radiation, waste and transport safety. Nuclear power plant safety performance remained high, and indicated an improved trend in the number of emergency shutdowns as well in the level of energy available during these shutdowns. In addition, more States explored or expanded their interests in nuclear power programmes, and more faced the challenge of establishing the required regulatory infrastructure, regulatory supervision and safety management over nuclear installations and the use of ionizing radiation. Issues surrounding radiation protection and radioecology continued as trends in 2010. For example, increased public awareness of exposure to and environmental impacts of naturally occurring radioactive material (NORM) as well as nuclear legacy sites has led to increased public concern. In addition, human resources in radiation protection and radioecology have been lost as a result of retirement and of the migration of experts to other fields. It is clear that safety continues to be a work in progress. The global nuclear power industry continued to require substantial efforts by designers, manufacturers, operators, regulators and other stakeholders to satisfy diverse quality and safety requirements and licensing processes, along with the recognized need in industry and among regulators to standardize and harmonize these requirements and processes. In some cases, plans for nuclear power programme development moved faster than the establishment of the necessary regulatory and safety infrastructure and capacity. To assist Member States in this effort, the Regulatory Cooperation Forum (RCF) was formed in June 2010. The RCF is a regulator-to-regulator forum that optimizes regulatory support from Member

  19. 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

  20. 78 FR 33891 - Safety Advisory: Compressed Gas Cylinders That Have Not Been Tested Properly

    Science.gov (United States)

    2013-06-05

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Properly AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Safety... otherwise safely discharged. Cylinders that are filled with a material other than an atmospheric gas should...

  1. 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)

  2. 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)

  3. 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)

  4. 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

  5. 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

  6. 75 FR 34520 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-06-17

    ... Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting AGENCY: Office of the Secretary of... Secretary of Transportation, announces a meeting of the FAAC Aviation Safety Subcommittee, which will be... of the global economy. The Aviation Safety Subcommittee will develop a list of priority safety issues...

  7. 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...

  8. 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

  9. 77 FR 66639 - Advisory Committee on Construction Safety and Health (ACCSH)

    Science.gov (United States)

    2012-11-06

    ... Contract Work Hours and Safety Standards Act (Construction Safety Act) (40 U.S.C. 3701 et seq.) and the.../Women in Construction: 2:15 to 4:15 p.m. The following ACCSH Work Groups will meet November 28, 2012... Occupational Safety and Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety...

  10. 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...

  11. 76 FR 4128 - Establishment of the Ocean Energy Safety Advisory Committee

    Science.gov (United States)

    2011-01-24

    ... relating to offshore energy safety, including, but not limited to drilling and workplace safety, well... Federal Officer (DFO). BOEMRE will provide administrative and logistical support to the Committee. The..., including, but not limited to drilling and workplace safety, well intervention and containment, and oil...

  12. 75 FR 28619 - Meeting of the Advisory Committee on Blood Safety and Availability

    Science.gov (United States)

    2010-05-21

    ... public health parameters around safety and availability of the blood supply and blood products, (2) broad public health, ethical and legal issues related to transfusion and transplantation safety, and (3) the implications for safety and the availability of various economic factors affecting product cost and supply...

  13. 76 FR 26300 - Meeting of the Advisory Committee on Blood Safety and Availability

    Science.gov (United States)

    2011-05-06

    ... around safety and availability of the blood supply and blood products, (2) broad public health, ethical... safety and availability of various economic factors affecting product cost and supply. In keeping with... reactions on the practices, safety, quality, efficacy, epidemiology and ethics of donations and...

  14. 76 FR 41304 - Advisory Committee on Construction Safety and Health (ACCSH)

    Science.gov (United States)

    2011-07-13

    ... arising in the administration of the safety and health provisions under the Contract Work Hours and Safety....; Multilingual Issues, Diversity, Women in Construction-- 3:45 to 5 p.m. For additional information on ACCSH Work... and Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety Standards...

  15. NRU licence extension via integrated safety review

    Energy Technology Data Exchange (ETDEWEB)

    Mantifel, N. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    The National Research Reactor, NRU at AECL Chalk River Laboratories achieved first criticality in November 1957. The completion of an Integrated Safety Review (ISR) in 2011, and subsequent Global Assessment Report (GAR), and Integrated Implementation Plan (IIP) has given confidence in the safe and reliable operation of NRU, therefore extending the licensing case to safely and reliably operate NRU until 2021 and beyond (64+ years of operation). The key vehicle to achieve this confidence is the IIP, that resulted from the ISR. NRU's IIP is a 10 year plan that addresses the gaps identified in the ISR between modern codes and standards in a prioritized approach. AECL is currently in year 3 of the IIP execution, is on or ahead of schedule to complete the identified improvements. The IIP in conjunction with a License Condition Handbook has replaced the licensing protocol with the Canadian Nuclear Safety Commission, (CNSC). Execution of the IIP to plan supports the continued safe operation of NRU. The ISR was carried out with the recognition that the NRU reactor is a research and isotope producing reactor approaching license renewal and not a power reactor undergoing refurbishment and life extension. Therefore, the IIP is being executed while NRU continues to deliver on its three missions: production of medical isotopes, support for fuels and materials research, and serving as a high flux neutron source in support of research relying on neutron scattering. The IIP is grouped into 5 Global Issue Groups, (GIGs) to support focused execution. The activities and tasks within the five GIGs are being executed via a matrix organization through the use of the Chalk River Laboratories Corrective Action Program to ensure the assignment of actions, completion and evidence to support closure is documented and retained. This paper discusses the approach taken by AECL to license and ensure safe, reliable operation of NRU until 2021 and beyond. (author)

  16. 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.

  17. Defence in depth in nuclear safety. INSAG-10. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    1996-01-01

    The present report deals with the concept of defence in depth in nuclear and radiation safety, discussing its objectives, strategy, implementation and future development. The report is intended for use by governmental authorities and by the nuclear industry and its supporting organizations. It is intended to stimulate discussion and to promote practical action at all levels to enhance safety. 6 refs, 1 tab

  18. The role of the Australian Adverse Drug Reactions Advisory Committee (ADRAC) in monitoring drug safety

    International Nuclear Information System (INIS)

    Boyd, Ian W.

    2002-01-01

    The Australian adverse drug reaction reporting system is acknowledged as one of the best in the world. Despite its small population of less than 20 million people, Australia's current ADR reporting rate of over 12000 reports per year places it in the top few nations in terms of reports per capita. The ADRAC program has been in operation for over 30 years. Australia was a founding member of the WHO International Drug Monitoring Programme which commenced in 1968 and currently there are about 153000 reports in the ADRAC database. Reports from health professionals have uncovered a number of significant safety problems over the years. Of particular importance are flucloxacillin-induced hepatitis, amoxycillin/clavulanate-induced hepatitis, and the association of cystitis with tiaprofenic acid. The number and quality of the reports has allowed an understanding of the characteristics of the reactions and, using ADRAC reporters as a major source of cases, case-control studies have been completed which have identified risk factors. ADRAC's review of Australian reports has highlighted many important associations that have been disseminated through the Australian Adverse Drug Reactions Bulletin

  19. Critical review of safety performance metrics

    NARCIS (Netherlands)

    Karanikas, Nektarios

    2016-01-01

    Various tools for safety performance measurement have been introduced in order to fulfil the need for safety monitoring in organisations, which is tightly related to their overall performance and achievement of their business goals. Such tools include accident rates, benchmarking, safety culture and

  20. 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

  1. 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

  2. Review of Medical Advisory Services by the Korean Society of Pathologists from 2003 to 2014

    Directory of Open Access Journals (Sweden)

    Min Hye Jang

    2016-01-01

    Full Text Available Background: Since 2003, the Korean Society of Pathologists (KSP has been officially providing medical advisory services (MAS. We reviewed the cases submitted to the KSP between 2003 and 2014. Methods: In total, 1,950 cases were submitted, most by private health insurance companies. The main purposes of the consultations were to clarify the initial diagnoses and to assign a proper disease classification code. We comprehensively reviewed 1,803 consultation cases with detailed information. Results: In spite of some fluctuations, the number of submitted cases has been significantly increasing over the 12 study years. The colon and rectum (40.3%, urinary bladder (14.2%, and stomach (6.9% were the three most common tissues of origin. The most common diagnoses for each of the three tissues of origin were neuroendocrine tumor (50.7%, non-invasive papillary urothelial carcinoma (70.7%, and adenocarcinoma (36.2%. Regardless of the tissue of origin, neuroendocrine tumor of the digestive system was the most common diagnosis (419 of 1,803. Conclusions: In the current study, we found that pathologic consultations associated with private health insurance accounted for a large proportion of the MAS. Coding of the biologic behavior of diseases was the main issue of the consultations. In spite of the effort of the KSP to set proper guidelines for coding and classification of tumors, this review revealed that problems still exist and will continue to be an important issue.

  3. IRSN safety research carried out for reviewing safety cases

    International Nuclear Information System (INIS)

    Serres, Ch.

    2010-01-01

    Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

  4. 76 FR 73687 - Advisory Committee on Construction Safety and Health (ACCSH)

    Science.gov (United States)

    2011-11-29

    ... arising in the administration of the safety and health provisions under the Contract Work Hours and Safety... 10:10 a.m. to 12:10 p.m. Multilingual Issues, Diversity, Women in Construction 1 to 3 p.m. ACCSH Work... Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety Standards Act...

  5. 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

  6. 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.

  7. 75 FR 44998 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-07-30

    ... evolving transportation needs, challenges, and opportunities of the global economy. The Aviation Safety... activities associated with the list of priority safety issues developed during the first meeting. The subcommittee will also develop a work plan for future meetings. DATES: The meeting will be held on August 24...

  8. 76 FR 15982 - Nominations to the Advisory Committee on Blood Safety and Availability

    Science.gov (United States)

    2011-03-22

    ... Committee is the responsibility of the OASH. The qualified individuals will be nominated to the Secretary of... Mr. James Berger, Associate Public Health Advisor for Blood, Organ and Tissue Safety; Office of... Public Health Advisor for Blood, Organ and Tissue Safety. Contact information for Mr. Berger is provided...

  9. 77 FR 17119 - Pipeline Safety: Cast Iron Pipe (Supplementary Advisory Bulletin)

    Science.gov (United States)

    2012-03-23

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... national attention and highlight the need for continued safety improvements to aging gas pipeline systems... 26, 1992) covering the continued use of cast iron pipe in natural gas distribution pipeline systems...

  10. 78 FR 28848 - Meeting of the Advisory Committee on Blood and Tissue Safety and Availability

    Science.gov (United States)

    2013-05-16

    ... health, ethical and legal issues related to the safety of blood, blood products, and tissues; (4) the impact of various economic factors (e.g., product cost and supply) on safety and availability of blood... coordinated system to manage tissue supplies and distributions during a disaster does not exist. Past...

  11. 75 FR 14471 - Advisory Committee on Construction Safety and Health (ACCSH)

    Science.gov (United States)

    2010-03-25

    ... and Health (ACCSH) and ACCSH Work Group meetings. SUMMARY: ACCSH will meet April 14 and 16, 2010, in... Safety and Health in the formulation of standards affecting the construction industry and on policy matters arising in the administration of the safety and health provisions of the Contract Work Hours and...

  12. US nuclear safety. Review and experience

    International Nuclear Information System (INIS)

    Hanauer, S.H.

    1977-01-01

    The paper deals with the evolution of reactor safety principles, design bases, regulatory requirements, and experience in the United States. Safety concerns have evolved over the years, from reactivity transients and shut-down systems, to blowdowns and containment, to severe design basis accidents and mitigating systems, to the performance of actual materials, systems and humans. The primary safety concerns of one epoch have been superseded in considerable measure by those of later times. Successive plateaus of technical understanding are achieved by solutions being found to earlier problems. Design studies, research, operating experience and regulatory imperatives all contribute to the increased understanding and thus to the safety improvements adopted and accepted. The improvement of safety with time, and the ability of existing reactors to operate safely in the face of new concerns, has confirmed the correctness and usefulness of the defence-in-depth approach and safety margins used in safety design in the United States of America. A regulatory programme such as the one in the United States justifies its great cost by its important contributions to safety. Yet only the designers, constructors and operators of nuclear power plants can actually achieve public safety. The regulatory programme audits, assesses and spot-checks the actual work. Since neither materials nor human beings are flawless, mistakes will be made; that is why defence-in-depth and safety margins are provided. The regulatory programme should enhance safety by decreasing the frequency of uncorrected mistakes. Maintenance of public safety also requires technical and managerial competence and attention in the organizations responsible for nuclear plants as well as regulatory organizations. (author)

  13. 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...

  14. 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

  15. Sulfur Dioxide (SO2) Primary NAAQS Review: Integrated Review Plan - Advisory with CASAC

    Science.gov (United States)

    The SO2 Integrated Review Plan is the first document generated as part of the National Ambient Air Quality Standards (NAAQS) review process. The Plan presents background information, the schedule for the review, the process to be used in conducting the review, and the key policy-...

  16. 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

  17. 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)

  18. 76 FR 62496 - Motor Carrier Safety Advisory Committee Series of Public Subcommittee Meetings

    Science.gov (United States)

    2011-10-07

    ... Carrier Safety Admin., No. 10-2340 (7th Cir. 2011).] The Agency will not appeal the court's decision and... effective public participation before the comment period deadline, FMCSA encourages use of the Web site...

  19. 78 FR 24237 - Advisory Committee on Construction Safety and Health (ACCSH)

    Science.gov (United States)

    2013-04-24

    ... arsenic, that may affect construction employees; --Permit digital storage of x-rays (not just film); [cir... Construction, Health and Safety Checklist; Discussion of the 2-hour introduction to the OSHA 10-hour and 30...

  20. 78 FR 66006 - Meeting of the Advisory Committee on Blood and Tissue Safety and Availability

    Science.gov (United States)

    2013-11-04

    ... decision making from donor to recipient. The Committee will also hear from the World Health Organization's... include: (1) Definition of public health parameters around safety and availability of blood and blood...

  1. 77 FR 24257 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2012-04-23

    ... publication. Contact: Steve Clay, (202) 493-6259. Task 06-03--Medical Standards for Safety-Critical Personnel... 97-2--(Completed) Evaluating the extent to which environmental, sanitary, and other working...

  2. 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...

  3. Detailed Safety Review of Anthrax Vaccine Adsorbed

    National Research Council Canada - National Science Library

    2001-01-01

    To date, 18 human studies have assessed the safety of anthrax vaccination. These studies, some stretching back almost 50 years, reported adverse events after vaccination in varying degrees of detail...

  4. Patient safety in otolaryngology: a descriptive review.

    Science.gov (United States)

    Danino, Julian; Muzaffar, Jameel; Metcalfe, Chris; Coulson, Chris

    2017-03-01

    Human evaluation and judgement may include errors that can have disastrous results. Within medicine and healthcare there has been slow progress towards major changes in safety. Healthcare lags behind other specialised industries, such as aviation and nuclear power, where there have been significant improvements in overall safety, especially in reducing risk of errors. Following several high profile cases in the USA during the 1990s, a report titled "To Err Is Human: Building a Safer Health System" was published. The report extrapolated that in the USA approximately 50,000 to 100,000 patients may die each year as a result of medical errors. Traditionally otolaryngology has always been regarded as a "safe specialty". A study in the USA in 2004 inferred that there may be 2600 cases of major morbidity and 165 deaths within the specialty. MEDLINE via PubMed interface was searched for English language articles published between 2000 and 2012. Each combined two or three of the keywords noted earlier. Limitations are related to several generic topics within patient safety in otolaryngology. Other areas covered have been current relevant topics due to recent interest or new advances in technology. There has been a heightened awareness within the healthcare community of patient safety; it has become a major priority. Focus has shifted from apportioning blame to prevention of the errors and implementation of patient safety mechanisms in healthcare delivery. Type of Errors can be divided into errors due to action and errors due to knowledge or planning. In healthcare there are several factors that may influence adverse events and patient safety. Although technology may improve patient safety, it also introduces new sources of error. The ability to work with people allows for the increase in safety netting. Team working has been shown to have a beneficial effect on patient safety. Any field of work involving human decision-making will always have a risk of error. Within

  5. 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

  6. 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

  7. 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.

  8. Nuclear Safety Review for the Year 2004

    International Nuclear Information System (INIS)

    2005-08-01

    In the nuclear area, challenges continue to emerge from the globalization of issues related to safety, technology, business, information, communication and security. Scientific advances and operational experience in nuclear, radiation, waste and transport technology are providing new opportunities to continuously improve safety and security by utilizing synergies between safety and security. The prime responsibility for nuclear, radiation, waste and transport safety rests with users and national governments. The Agency continues to support a Global Nuclear Safety Regime based on strong national safety infrastructures and widespread subscription to international legal instruments to maintain high levels of safety worldwide. Central to the Agency's role are the establishment of international safety standards and the provision for applying these standards, as well as the promotion of sharing information through managing the knowledge base. Nuclear power plant operational safety performance remains high throughout the world. Challenges facing the nuclear power industry include avoiding complacency, maintaining the necessary infrastructure, nuclear power plant ageing and long-term operation, as well as new reactor designs and construction. The research reactor community has a long history of safe operation. However nearly two-thirds of the world's operating research reactors are now over 30 years old and face safety and security challenges. In 2004, the Board of Governors approved the Code of Conduct on the Safety of Research Reactors to help address these challenges. In 2004, there was international consensus on radionuclide activity concentrations in materials below which regulatory controls need not apply. Key occupational radiation protection performance indicators continued to improve in 2004. Challenges include new medical practices where workers can receive high exposures, industrial radiography and worker exposure to naturally occurring radioactive material. New

  9. 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.

  10. 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.

  11. Independence in regulatory decision making - INSAG-17. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    2003-01-01

    This report is intended to promote a common understanding among legislators and other political decision makers, nuclear safety regulators and licensees of the concept of independence in regulatory decision making and how to achieve it. Other interest groups, such as non-governmental organizations and members of the public interested in the regulation of nuclear safety, may also find the report useful. The principles concerning the independence of regulatory organizations are developed and discussed in publications in the IAEA's Safety Standards Series. Although the principles relating to protecting the independence of the regulatory body provide the necessary basis for independence in regulatory decision making, there are additional factors and features that require attention to ensure independence in the decision making by the regulatory body. This INSAG report highlights and discusses a number of such factors and features

  12. 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

  13. 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

  14. 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

  15. 75 FR 76070 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2010-12-07

    ... the Passenger Equipment Safety Standards. The Working Group met on September 16, 2010; currently there... ``after arrival mandatory directives,'' among other issues. The Working Group continues to work on after... protecting persons who work on, under, or between rolling equipment and persons applying, removing, or...

  16. 76 FR 72997 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2011-11-28

    ... two additional Task Groups to work in the areas of track worthiness and brakes. The Track worthiness... Group includes experts and key stakeholders such as international operators of high-speed equipment, car... regulatory language to the Passenger Safety Working Group at the September 16, 2010, meeting. More work...

  17. Radioactive waste management services. Safety and technical advisory services available from the IAEA

    International Nuclear Information System (INIS)

    2000-09-01

    This brochure provides updated information about the services and assistance the International Atomic Energy Agency (IAEA) is able to render, upon request by Member States, in the area of radioactive waste management. The ultimate objective is to ensure that all wastes are managed safely and in a way which protects both individual and the environment, now and in the future. The IAEA is the sole global international organization with the statutory authority to establish safety standards for the protection of health against exposure to ionizing radiation. These include safety standards for radioactive waste management. A comprehensive set of such standards is being established, and continuously updated, under the Agency's aegis, which lay out the requirements for the safe management of all types of radioactive waste. The Agency has a further statutory obligation ro provide for the application of these standards at the request of States. The safety of radioactive waste management is not attainable through safety standards alone but requires special technology. An additional function of the IAEA is thus to foster the transfer of technology among States, including the specific technology needed to ensure safe radioactive waste management

  18. 78 FR 12062 - Nominations to the Advisory Committee on Blood and Tissue Safety and Availability

    Science.gov (United States)

    2013-02-21

    ... Committee is the responsibility of the OASH. The qualified individuals will be nominated to the Secretary of... Mr. James Berger, Senior Advisor for Blood Policy; Division of Blood and Tissue Safety and...: (240) 453-8803. FOR FURTHER INFORMATION CONTACT: Mr. James Berger, Senior Advisor for Blood Policy...

  19. 76 FR 76732 - Nominations to the Advisory Committee on Blood Safety and Availability

    Science.gov (United States)

    2011-12-08

    ... individuals will be nominated to the Secretary of HHS for consideration of appointment as members of the ACBSA..., Associate Public Health Advisor for Blood, Organ and Tissue Safety Policy, Department of Health and Human.... Nominations In accordance with the charter, persons nominated for appointment as members of the ACBSA should...

  20. 78 FR 13747 - Railroad Safety: Advisory Notice Related to Railroad Accidents in Vicinity of Underground Pipelines

    Science.gov (United States)

    2013-02-28

    ... underground natural gas transmission pipeline operated by Nicor Gas. The pipeline well exceeded Federal... had the gas pipeline been installed at the railroad crossing with only the minimum level of ground... resumption of service.'' On July 31, 2012, the Pipeline and Hazardous Materials Safety Administration (PHMSA...

  1. 75 FR 76465 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2010-12-08

    ... significant number of Council members have made business and travel plans in accordance with this schedule... implementation of solutions and best practices for public safety communications and cybersecurity. Recognizing... Public Notice announcing the meeting is available at http://www.fcc.gov/Daily_Releases/Daily_Business...

  2. 75 FR 5172 - Solicitation of Nominations for Members of the Transit Rail Advisory Committee for Safety

    Science.gov (United States)

    2010-02-01

    ... reform in this area, convening affected parties now will only help strengthen FTA's decision-making..., major accidents in Chicago, Washington, DC, San Francisco, and Boston have captured the attention of the... affected by rail transit safety requirements. These key constituencies will include, but are not limited to...

  3. 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.

  4. 78 FR 64503 - Subcommittee for Dose Reconstruction Reviews (SDRR), Advisory Board on Radiation and Worker...

    Science.gov (United States)

    2013-10-29

    ... in the official record of the meeting. The public is also welcome to listen to the meeting by joining... implement and effectively manage the new compensation program. Key functions of the Advisory Board include...

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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.)

  11. 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

  12. 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)

  13. 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

  14. 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

  15. 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

  16. Shielding modefication and safety review on Mutsu

    International Nuclear Information System (INIS)

    Osanai, Masao

    1978-01-01

    The Japan Atomic Energy Commission requests strongly to repair the shielding and make general safety inspection on Mutsu after an accident of radiation leakage from the reactor. The content and procedure of this repair of shielding and general safety inspection are outlined. The neutron leakage location in the reactor proper, technical shielding investigation, conceptual design of relating shielding repair, the mock up test of the shielding on the neutron streaming, the final conceptual design of repair, the relating research and development experiment and the detailed basic design of repair are explained, comparing the original design and the modified one. The modified design depends on the experimental results of neutron streaming test between the reactor vessel and the primary shield. As for the general safety inspection, the functional test of control rod driving mechanism and other main components, the flaw detection for heat transfer tubes of the steam generator and primary cooling pipings are carried out in hardwares, and the integrity analysis of fuel assemblies, stress corrosion cracking of fuel claddings and primary cooling pipings, the natural circulation analysis of primary cooling system, and integrity check of the heat transfer tubes of steam generator are carried out in softwares. The burst test and the strength test after high temperature oxidation for fuel claddings made of stainless steel were carried out. (Nakai, Y.)

  17. 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.

  18. 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)

  19. 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

  20. 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

  1. Safety reviews of the Brazilian multipurpose reactor

    International Nuclear Information System (INIS)

    Soares, Humberto Vitor

    2014-01-01

    This work presents a model developed for thermal hydraulic (TH) simulation of the Multipurpose Brazilian Reactor (RMB), whose Brazilian proposal for design, construction and operation was established in 2007. This reactor has as main proposed the production of radioisotopes for use in exams of nuclear medicine, material tests and utilization of neutrons beams. Besides of the TH modeling and safety analysis of the reactor, the application of a methodology to perform coupled calculation thermal-hydraulic/neutron kinetic (TH/NK) is also presented. Initially, the RMB was modeled in the safety analysis RELAP5 code. This code performs the thermal hydraulic calculation using point kinetics. Subsequently, the model was adapted and verified to the RELAP5-3D© code. This code performs the process of internal coupling through the option of nodal neutron kinetics calculation using the NESTLE code which solves the neutron diffusion equation. To generate the neutronic group constants, which are macroscopic cross sections that serve as input data for the neutronic codes, it was used the WIMSD-5B cell calculation code. The neutron analysis code PARCS was also used to model the 3D RMB core in order to compare the results of radial and axial average power distribution with the results generated by RELAP5-3D© code and with the available results of the CITATION neutron kinetic code. The safety analyses demonstrated safe behavior of the reactor through situations of possible transients. The 3D coupled calculations to the steady state operation also showed expected behavior, as well as the RMB neutronic analyzes performed with the codes NESTLE and PARCS.(author)

  2. 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.)

  3. WNP-2 outage safety review methodology

    International Nuclear Information System (INIS)

    Chiang, Albert; Fu, James

    2004-01-01

    A practical and versatile method was developed in the flow chart and checklist forms to show the defense-in-depth for various key safety functions of a nuclear power plant during shutdown. Using four different colors (green, yellow, orange, and red) for indication of levels of defense-in-depth is visually impressive, easy to understand, and was adopted by the outage management personnel as a convenient reference tool for maintenance activity planning before the outage, and schedule changes during the outage. This paper describes the method and its application at Washington Public Power Supply System's Nuclear Project 2 (WNP-2). (author)

  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. 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.

  6. 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

  7. 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

  8. Review of the German Reactor Safety Study

    International Nuclear Information System (INIS)

    Bayer, A.

    1980-01-01

    The accident risks in German nuclear power plants are reviewed. Parameters influencing the extent and consequences of an accident are differentiated. Risks of normal operation, war, and sabotage have not been considered. Measures taken by the operating shaft in the course of an accident are taken into account. The knowledge thus gained can be applied in the planning of emergency measures. (DG) [de

  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. 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)

  11. Review of design criteria and safety analysis of safety class electric building for fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y.

    1998-02-01

    Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. HANARO fuel test loop was designed for CANDU and PWR fuel testing. Safety related system of Fuel Test Loop such as emergency cooling water system, component cooling water system, safety ventilation system, high energy line break mitigation system and remote control room was required 1E class electric supply to meet the safety operation in accordance with related code. Therefore, FTL electric building was designed to construction and install the related equipment based on seismic category I. The objective of this study is to review the design criteria and analysis the safety function of safety class electric building for fuel test loop, and this results will become guidance for the irradiation testing in future. (author). 10 refs., 6 tabs., 30 figs.

  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. 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

  14. Book review: Safety of Biologics Therapy

    Directory of Open Access Journals (Sweden)

    Robak T

    2017-01-01

    Full Text Available Tadeusz Robak Department of Hematology, Medical University of Lodz and Copernicus Memorial Hospital, Lodz, PolandSafety of Biologics Therapy: Monoclonal Antibodies, Cytokines, Fusion Proteins, Hormones, Enzymes, Coagulation Proteins, Vaccines, Botulinum Toxins (Cham, Switzerland: Springer International Publishing; 2016 by Brian A Baldo from the Molecular Immunology Unit, Kolling Institute of Medical Research, Royal North Shore Hospital of Sydney, and the Department of Medicine, University of Sydney, Australia, is a book that belongs on the shelf of everyone in the field of biologic therapies research and clinical practice. In writing this book, the author’s intention was to produce an up-to-date text book on approved biologic therapies, as far as that is possible in this time of rapidly evolving developments in biotherapeutic research and the introduction of new and novel agents for clinical use.The monograph comprises 610 pages in 13 chapters, each including a summary and further reading suggestions. All chapters include a discussion of basic and clinical material. Well-designed, comprehensive tables and color figures are present throughout the book. The book itself examines the biologic products that have regulatory approval in the USA and/or European Union and that show every indication of remaining important therapies. It covers in great detail all the latest work on peptide hormones and enzymes, monoclonal antibodies, fusion proteins, and cytokine therapies. Beyond that, it also presents the latest information on blood coagulation proteins, vaccines, botulinum neurotoxins, and biosimilars. 

  15. 75 FR 71694 - Science Advisory Board Staff Office; Notification of Two Public Quality Review Teleconferences of...

    Science.gov (United States)

    2010-11-24

    ... teleconference, to give EPA as much time as possible to process your request. Dated: November 16, 2010. Anthony... Board can be found on the SAB Web site at http://www.epa.gov/sab . SUPPLEMENTARY INFORMATION: Pursuant... advisory activity can be found on the SAB Web site at: http://yosemite.epa.gov/sab/sabproduct.nsf/fedrgstr...

  16. 76 FR 38182 - Subcommittee for Dose Reconstruction Reviews (SDRR), Advisory Board on Radiation and Worker...

    Science.gov (United States)

    2011-06-29

    ... Pass Code 9933701. Background: The Advisory Board was established under the Energy Employees... whether there is a class of employees at any Department of Energy facility who were exposed to radiation... Subcommittee meeting includes: Selection of individual radiation dose reconstruction cases to be considered for...

  17. Safety review for seismic qualification on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Fang Qingxian

    1995-01-01

    The standards and requirements for seismic qualification of nuclear power plant's component have been fully addressed, including the scope of seismic qualification, the approach and the method of common seismic qualification, the procedure of the seismic tests, and the criteria for the seismic qualification review. The problems discovered in the safety review and the solution for these problems and some other issues are also discussed

  18. A Systematic Review of the Safety of Lisdexamfetamine Dimesylate

    OpenAIRE

    Coghill, David R.; Caballero, Beatriz; Sorooshian, Shaw; Civil, Richard

    2014-01-01

    Background Here we review the safety and tolerability profile of lisdexamfetamine dimesylate (LDX), the first long-acting prodrug stimulant for the treatment of attention-deficit/hyperactivity disorder (ADHD). Methods A PubMed search was conducted for English-language articles published up to 16 September 2013 using the following search terms: (lisdexamfetamine OR lisdexamphetamine OR SPD489 OR Vyvanse OR Venvanse OR NRP104 NOT review [publication type]). Results In short-term, parallel-group...

  19. Managing change in the nuclear industry: The effects on safety. INSAG-18. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    The nuclear industry is going through a period of unprecedented change. The changes arise from the political and business environment in which the industry must operate, and from within the industry itself as it strives to become more competitive. These pressures have already led to significant changes in how nuclear enterprises are organized. The changes can be expected to continue. It is absolutely essential that throughout the period of time that organizational changes are taking place, and after the changes have occurred, very high standards of safety are maintained by all the elements that make up the industry. Changes can be made effectively and safely, and gains in efficiency and competitiveness, as well as safety, can be realized if changes are introduced carefully and managed well. Experience has shown that this is not a simple matter to achieve. Nuclear installations are complex, and it is inherently demanding to foresee all the implications that a change may have on safety. However, experience has shown very clearly that many changes have a strong potential to affect both the safety that has been built into a design and in the safety culture of an organization. Hence failure to manage change well can significantly affect the likelihood of an accident, the degree to which the assets of the company are put at risk and the company's reputation. This INSAG report is directed at members of boards of directors and senior executives who are responsible for the overall safety of an installation, who make decisions for change and who implement these decisions. It is also written for senior regulators who, on behalf of the public, ensure that boards of directors and executives meet their responsibilities for safety. This report discusses how and why change can challenge the maintenance of a high level of safety, and what can be done to control that challenge and hence reap all the benefits of change. It draws an analogy between the well established principles

  20. Managing change in the nuclear industry: The effects on safety. INSAG-18. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    2003-01-01

    The nuclear industry is going through a period of unprecedented change. The changes arise from the political and business environment in which the industry must operate, and from within the industry itself as it strives to become more competitive. These pressures have already led to significant changes in how nuclear enterprises are organized. The changes can be expected to continue. It is absolutely essential that throughout the period of time that organizational changes are taking place, and after the changes have occurred, very high standards of safety are maintained by all the elements that make up the industry. Changes can be made effectively and safely, and gains in efficiency and competitiveness, as well as safety, can be realized if changes are introduced carefully and managed well. Experience has shown that this is not a simple matter to achieve. Nuclear installations are complex, and it is inherently demanding to foresee all the implications that a change may have on safety. However, experience has shown very clearly that many changes have a strong potential to affect both the safety that has been built into a design and in the safety culture of an organization. Hence failure to manage change well can significantly affect the likelihood of an accident, the degree to which the assets of the company are put at risk and the company's reputation. This INSAG report is directed at members of boards of directors and senior executives who are responsible for the overall safety of an installation, who make decisions for change and who implement these decisions. It is also written for senior regulators who, on behalf of the public, ensure that boards of directors and executives meet their responsibilities for safety. This report discusses how and why change can challenge the maintenance of a high level of safety, and what can be done to control that challenge and hence reap all the benefits of change. It draws an analogy between the well established principles for

  1. 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

  2. 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

  3. 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)

  4. 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)

  5. 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

    ..., and Marie C.McCormick, Editors Immunization Safety Review Committee Board on Health Promotion and Disease Prevention INSTITUTE OF MEDICINE NATIONAL ACADEMY PRESS Washington, D.C. Copyrightoriginal retained, the be not from cannot book, paper original however, for version formatting, authoritative the typesetting-specific created from the as publ...

  6. 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.

  7. 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.

  8. 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.

  9. Review of Safety and Security of Radioactive Sources in Africa

    International Nuclear Information System (INIS)

    Kiti, Shadrack Anthony; Choi, Kwang Sik

    2011-01-01

    Radioactive materials are used worldwide for peaceful applications in medicine, industry, agriculture, environmental science, education and research and military applications. Most of these radioactive sources used are imported therefore trans-boundary movement is a significant factor in consideration of safety and security measures during movement of these sources. It is estimated that 20 million packages of radioactive materials are transported annually worldwide and this number of shipments is expected to increase due to the renaissance of nuclear power generation. The African continent has shown considerable leadership in its advocacy for the safety and security of radioactive sources. The First Africa Workshop on the Establishment of a Legal Framework governing Radiation Protection, the Safety of Radiation Sources and the Safe Management of Radioactive Waste held in Ethiopia in 2001 called upon the IAEA to form a forum for African countries to consider the Code of Conduct on the Safety and Security of Radioactive Sources and give it a legally binding effect so that the peaceful use of nuclear technology is not compromised. Despite these laudable efforts, Africa still faces considerable challenges in the implementation of safety and security of radioactive sources because of weak regulatory control and lack of infrastructure to properly control, manage and secure radiation sources 1 . The purpose of this paper was therefore, to analyze, review, address and share knowledge and experience with regard to safety and security measures of radioactive materials in Africa. This project will benefit IAEA's African member states in creating nuclear safety and security networking in the region

  10. [Patient safety in home care - A review of international recommendations].

    Science.gov (United States)

    Czakert, Judith; Lehmann, Yvonne; Ewers, Michael

    2018-06-08

    In recent years there has been a growing trend towards nursing care at home in general as well as towards intensive home care being provided by specialized home care services in Germany. However, resulting challenges for patient safety have rarely been considered. Against this background we aimed to explore whether international recommendations for patient safety in home care in general and in intensive home care in particular already exist and how they can stimulate further practice development in Germany. A review of online English documents containing recommendations for patient safety in intensive home care was conducted. Available documents were analyzed and compared in terms of their form and content. Overall, a small number of relevant documents could be identified. None of these documents exclusively refer to the intensive home care sector. Despite their differences, however, the analysis of four selected documents showed similarities, e. g., regarding specific topics of patient safety (communication, involvement of patients and their relatives, risk assessment, medication management, qualification). Furthermore, strengths and weaknesses of the documents became apparent: e. g., an explicit understanding of patient safety, a literature-based introduction to safety topics or an adaptation of the recommendations to the specific features of home care were occasionally lacking. This document analysis provides interesting input to the formal and content-related development of specific recommendations and to practice development in Germany to improve patient safety in home care. Copyright © 2018. Published by Elsevier GmbH.

  11. Review of current status of LWR safety research in Japan

    International Nuclear Information System (INIS)

    Yamada, Tasaburo; Mishima, Yoshitsugu; Ando, Yoshio; Miyazono, Shohachiro; Takashima, Yoichi.

    1977-01-01

    The Japan Atomic Energy Commission has exerted efforts on the research of the safety of nuclear plants in Japan, and ''Nuclear plant safety research committees'' was established in August 1974, which is composed of the government and the people. The philosophy of safety research, research and development plan, the forwarding procedure of the plan, international cooperation, for example LOFT program, and the effective feed back of the experimental results concerning nuclear safety are reviewed in this paper at first. As for the safety of nuclear reactors the basic philosophy that radio active fission products are contained in fuel or reactors with multiple barriers, (defence in depth) and almost no fission product is released outside reactor plants even at the time of hypothetical accident, is kept, and the research and development history and the future plan are described in this paper with the related technical problems. The structural safety is also explained, for example, on the philosophy ''leak before break'', pipe rupture, pipe restraint and stress analysis. The release of radioactive gas and liquid is decreased as the philosophy ''ALAP''. And probability safety evaluation method, LOCA, reactivity, accident and aseismatic design in nuclear plants in Japan are described. (Nakai, Y.)

  12. The value of peer reviews to nuclear plant safety

    International Nuclear Information System (INIS)

    Subalusky, W.T. Jr.

    1994-01-01

    On a global basis, the nuclear utility industry has clearly demonstrated the value of peer reviews for improving nuclear safety and overall plant performance. Peer reviews are conducted by small teams of technical experts who review various aspects of plant operation, recognize strengths and recommend improvements, thereby stimulating a positive response to the recommendations. U.S. nuclear utilities initiated the operator-to-operator peer review process first through the Institute of Nuclear Power Operations (INPO). Now, voluntary peer reviews are an important activity of the World Association of Nuclear Operators (WANO). Formed just five years ago. WANO has made significant progress in its key activities of the operator-to-operator exchanges, operating experience exchange, monitoring of plant performance indicators and sharing of good practices worldwide. A fifth activity, peer review on a strictly voluntary basis, is pertinent to this paper

  13. IAEA Review for Gap Analysis of Safety Analysis Capability

    International Nuclear Information System (INIS)

    Basic, Ivica; Kim, Manwoong; Huges, Peter; Lim, B-K; D'Auria, Francesco; Louis, Vidard Michael

    2014-01-01

    improvement of nuclear safety in the participating host organization and host member countries. To achieve this goal, the EM is to establish a process of discussion and comparison of gap findings, which will lead to sharing of information, experience, strengths and weaknesses among the participants, and foster regional cooperation to improve the weaknesses and improve safety generally. The pilot mission was conducted from 28 October to 1 November for one week at the National Nuclear Agency (BATAN) in Indonesia by the mission team formulated with 6 international experts who have considerable knowledge and experience in the field of safety analysis such as the deterministic safety analysis (DSA) and probabilistic safety analysis (PSA). Some comments and recommendations were given to BATAN management to support the establishment and maintenance of safety analysis capability and human resource, organizational and training aspects. Those aspects are important as a measure of the progress being made and an indicator of areas in SATG within the framework of the Extra-budgetary Programme on the Safety of Nuclear Installations in Southeast Asia, the Pacific, and Far East Countries (the EBP-Asia) or other cooperation programme, such as the IAEA Technical Cooperation programme. Provided in 2013 the Review of Gap Analysis for BATAN (Indonesian Nuclear Safety Regulatory Body) could be good reference for all other newcomer countries which started or plans nuclear power plant installation. (authors)

  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. 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

  16. 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

  17. Grasping at Straws: Comments on the Alberta Pipeline Safety Review

    Directory of Open Access Journals (Sweden)

    Jennifer Winter

    2013-09-01

    Full Text Available The release last month of the Alberta Pipeline Safety Review was meant to be a symbol of the province’s renewed commitment to environmental responsibility as it aims for new export markets. The report’s authors, Group 10 Engineering, submitted 17 recommendations covering public safety and pipeline incidents, pipeline integrity management and pipeline safety near bodies of water — and many of them run the gamut from the obvious to the unhelpful to the contradictory. That the energy regulator ought to be staffed to do its job should go without saying; in fact, staffing levels were never identified as an issue. The recommendation that record retention and transfer requirements be defined for mergers and acquisitions, sales and takeovers is moot. There is no reason a purchasing party would not want all relevant documents, and no real way to enforce transparency if the seller opts to withhold information. Harmonizing regulations between provinces could reduce companies’ cost of doing business, but could also prove challenging if different jurisdictions use performance-based regulations — which is what the Review recommended Alberta consider. This very brief paper pries apart the Review’s flaws and recommends that the province go back to the drawing board. Safety is a serious issue; a genuine statistical review linking pipeline characteristics to failures and risk-mitigation activities would be a better alternative by far.

  18. Maintaining knowledge, training and infrastructure for research and development in nuclear safety - INSAG-16. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    2003-01-01

    . Education in nuclear science and technology needs to be stabilized in order to maintain sufficient human resources in sciences and engineering relating to nuclear safety. Part of the research infrastructure should be maintained at universities. There is a concern that deterioration of the research infrastructure may lead over time to a deterioration in safety which the public will not tolerate. National and international bodies have a key role to play in ensuring that the skills and capabilities required by the nuclear industry and its regulators are available and that the infrastructure required for this is provided for. Maintaining the safety of nuclear facilities, a pool of expertise and the level of safety research is a common concern of IAEA Member States and therefore, to the extent practicable, research facilities and research data should be shared in joint research programmes by IAEA Member States. The OECD Nuclear Energy Agency (OECD/NEA) is actively engaged in this effort. It has recently published two important reports dealing with research capabilities and facilities and with major research programmes at risk. Following up on the conclusions of these reports, the OECD/NEA continues to review safety research needs and organizes and sponsors internationally funded projects which contribute to maintaining key research facilities and teams. However, it is important that such efforts encompass all countries having nuclear power programmes. The IAEA and OECD/NEA could explore this possibility further. More frequent interactions among research managers in Member States should be considered to ensure that full advantage is being taken of the joint expertise and equipment available around the world. Results of national research programmes should be made public and broadly shared. This will increase public confidence and help to ensure that regulatory processes reflect the state of knowledge

  19. Maintaining knowledge, training and infrastructure for research and development in nuclear safety. INSAG-16. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    . Education in nuclear science and technology needs to be stabilized in order to maintain sufficient human resources in sciences and engineering relating to nuclear safety. Part of the research infrastructure should be maintained at universities. There is a concern that deterioration of the research infrastructure may lead over time to a deterioration in safety which the public will not tolerate. National and international bodies have a key role to play in ensuring that the skills and capabilities required by the nuclear industry and its regulators are available and that the infrastructure required for this is provided for. Maintaining the safety of nuclear facilities, a pool of expertise and the level of safety research is a common concern of IAEA Member States and therefore, to the extent practicable, research facilities and research data should be shared in joint research programmes by IAEA Member States. The OECD Nuclear Energy Agency (OECD/NEA) is actively engaged in this effort. It has recently published two important reports dealing with research capabilities and facilities and with major research programmes at risk. Following up on the conclusions of these reports, the OECD/NEA continues to review safety research needs and organizes and sponsors internationally funded projects which contribute to maintaining key research facilities and teams. However, it is important that such efforts encompass all countries having nuclear power programmes. The IAEA and OECD/NEA could explore this possibility further. More frequent interactions among research managers in Member States should be considered to ensure that full advantage is being taken of the joint expertise and equipment available around the world. Results of national research programmes should be made public and broadly shared. This will increase public confidence and help to ensure that regulatory processes reflect the state of knowledge

  20. Review of national accelerator driven system programmes for partitioning and transmutation. Proceedings of an advisory group meeting

    International Nuclear Information System (INIS)

    2003-08-01

    One of the current important issues of nuclear power is the long lived radioactive waste toxicity problem. The sharpness of this problem could be considerably reduced if, during energy production, there was the possibility to incinerate at least the most toxic radioactive isotopes (long lived fission products and minor actinides). The combination of external intensive neutron sources with facilities containing nuclear fuel, so-called hybrid systems, are under investigation in several countries. The surplus of neutrons in such systems may be used to convert most of the long lived radioactive nuclides into isotopes having a shorter lifetime. Currently, an increasing number of groups are entering this field of research. There is clearly a need for co-originated their efforts, and also for the exchange of information from nationally or internationally co-ordinated activities. Consideration of the advantages of hybrid systems, and the wide field of interdisciplinary areas of research involved, show the need for an international co-operation in this novel R and D area. The International Atomic Energy Agency has maintained an active interest in advanced nuclear technology related to accelerator driven systems (ADS), and related activities have been carried out within the framework of its programme on emerging nuclear energy systems. After thorough analyses of the outcomes of several international forums and recommendations of the IAEA Technical Committee Meeting on Feasibility and Motivation for Hybrid Concepts for Nuclear Energy Generation and Transmutation (Madrid, Spain, 1997), the IAEA conducted an Advisory Group Meeting on Review of National Accelerator Driven System Programmes in Taejon, Republic of Korea, from 1 to 4 November 1999. The scope of the meeting included review of the current R and D programmes in the Member States and the assessment of the progress in the development of hybrid concepts. The programme of the AGM included the following topics

  1. Review of Radiation Safety in Medical X-Ray Diagnosis

    International Nuclear Information System (INIS)

    Koteng, O.A.

    2015-01-01

    Medical X-Ray machines have been used for more than a century for non-invasive diagnosis of patients for the benefit of mankind. The safety of operators and patients during such practice has improved with time, but, still cases of detrimental effects to Radiation Workers in Kenya including cancer related deaths have been reported in the recent past. An ongoing study is reviewing the safety status of the worker and patients during medical and dental exposures. The study was initiated following complaint of recurrent headaches by a radiographer working in a busy Kenyan hospital. (author)

  2. 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

  3. 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

  4. 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...

  5. 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)

  6. 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)

  7. 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).

  8. ENHANCING FOOD SAFETY AND STABILITY THROUGH IRRADIATION: A REVIEW

    Directory of Open Access Journals (Sweden)

    Manzoor Ahmad Shah

    2014-04-01

    Full Text Available Food irradiation is one of the non thermal food processing methods. It is the process of exposing food materials to the controlled amounts of ionizing radiations such as gamma rays, X-rays and accelerated electrons, to improve microbiological safety and stability. Irradiation disrupts the biological processes that lead to decay of food quality. It is an effective tool to reduce food-borne pathogens, spoilage microorganisms and parasites; to extend shelf-life and for insect disinfection. The safety and consumption of irradiated foods have been extensively studied at national levels and in international cooperations and have concluded that foods irradiated under appropriate technologies are both safe and nutritionally adequate. Specific applications of food irradiation have been approved by national legislations of more than 55 countries worldwide. This review aims to discuss the applications of irradiation in food processing with the emphasis on food safety and stability.

  9. Patient Safety Learning Systems: A Systematic Review and Qualitative Synthesis.

    Science.gov (United States)

    2017-01-01

    A patient safety learning system (sometimes called a critical incident reporting system) refers to structured reporting, collation, and analysis of critical incidents. To inform a provincial working group's recommendations for an Ontario Patient Safety Event Learning System, a systematic review was undertaken to determine design features that would optimize its adoption into the health care system and would inform implementation strategies. The objective of this review was to address two research questions: (a) what are the barriers to and facilitators of successful adoption of a patient safety learning system reported by health professionals and (b) what design components maximize successful adoption and implementation? To answer the first question, we used a published systematic review. To answer the second question, we used scoping study methodology. Common barriers reported in the literature by health care professionals included fear of blame, legal penalties, the perception that incident reporting does not improve patient safety, lack of organizational support, inadequate feedback, lack of knowledge about incident reporting systems, and lack of understanding about what constitutes an error. Common facilitators included a non-accusatory environment, the perception that incident reporting improves safety, clarification of the route of reporting and of how the system uses reports, enhanced feedback, role models (such as managers) using and promoting reporting, legislated protection of those who report, ability to report anonymously, education and training opportunities, and clear guidelines on what to report. Components of a patient safety learning system that increased successful adoption and implementation were emphasis on a blame-free culture that encourages reporting and learning, clear guidelines on how and what to report, making sure the system is user-friendly, organizational development support for data analysis to generate meaningful learning outcomes

  10. 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

  11. Russian MINATOM nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    1999-03-01

    The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

  12. 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

  13. 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.

  14. Management implementation plan for a safety analysis and review system

    International Nuclear Information System (INIS)

    Hulburt, D.A.; Berkey, B.D.

    1981-04-01

    The US Department of Energy has issued an Order, DOE 5481.1, which establishes uniform requirements for the preparation and review of Safety Analysis for DOE Operations. The Management Implementation Plan specified herein establishes the administrative procedures and technical requirements for implementing DOE 5481.1 to Operations under the cognizance of the Pittsburgh Energy Technology Center. This Implementation Plan is applicable to all present and future Operations under the cognizance of PETC. The Plan identifies those Operations for which DOE 5481.1 is applicable and those Operations for which no further analysis is required because the initial determination and review has concluded that DOE 5481.1 does not apply

  15. 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

  16. 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

  17. Renewable electricity generation: supporting documentation for the Renewables Advisory Board submission to the 2006 UK energy review

    International Nuclear Information System (INIS)

    2006-01-01

    The Renewables Advisory Board (RAB) is an independent, non-departmental public body, sponsored by the DTI, which brings together representatives of the renewable sector and the unions. Electricity generation from renewable energy sources offers a range of advantages to the UK electricity-generating sector. This document, prepared as supporting documentation for the RAB submission to the 2006 Energy Review, examines the role of renewable energy in improving security of supply, lowering financial risk for energy portfolios, and reducing electricity cost volatility and fuel costs for the UK. Key topics addressed in this report include: resource security; security of supply; price security; and operational security. Also covered are variability patterns, financial costs and benefits of renewable generation. Maintaining the option and flexibility of future renewables development has a real option value, with overseas evidence showing that this can be significant

  18. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2000 COMPOSITION OF THE JOINT TRAINING BOARD (JTB) - 2000/2001

    CERN Multimedia

    HR Division

    2000-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows:Senior Staff Advancement Committee (SSAC)D. Treille / EP (Convener)C. Benvenuti / ESTD. O. Williams /ITTechnical Engineers & Administrative Careers Committee (TEACC) C. Hauviller / EPL. Leistam / ESTS. Jarp / IT [Chairman]F. Pedersen / PSR. Lauckner / SLC. Roche / ETTLong-term contract Boards (LTCBs) (Categories 2 &5a)Tiziano Camporesi / EP [Convener]Florence Ranjard / EP\t[Alternate]Jacques Gruber / PSPeter Sievers / LHCThomas Pettersson / ESTMichel Mayoud / ESTSue Foffano / ASThierry Lagrange / SPLWerner Zapf / HR (Secretary) LTCB 2(Categories 3, 4, 5b & 5c)Véronique Paris / SL [Convener]Fabien Pérriolat / PS\t [Alternate]Mats Wilhelmsson / STVéronique Fassnacht / TISLucie Linssen / EPMichel Mayoud / ESTPatrick Geeraert / FIJohn Cuthbert / HRSeamus Hegarty / HR (Secretary) Composition of the Joint Training Board (JT...

  19. 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.

  20. 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

  1. SKI - ASAR - O3. As operated Safety Analysis Report. Recurring safety review 1996 Oskarshamn 3

    International Nuclear Information System (INIS)

    1997-12-01

    According to Swedish law, the reactor owner is responsible for performing a safety review and writing a ''ASAR''-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the ''SKI-ASAR'' report). Each Swedish reactor should pass through three full ASAR reviews during its life-time, similar to the licensing inspection before start-up of the reactor. The first series ASAR was delivered by OKG to SKI in December 1996, and forms the basis for the SKI analysis in the present report

  2. SKI - ASAR - F3. As operated Safety Analysis Report. Recurring safety review 1996 Forsmark 3

    International Nuclear Information System (INIS)

    1997-12-01

    According to Swedish law, the reactor owner is responsible for performing a safety review and writing a ''ASAR''-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the ''SKI-ASAR'' report). Each Swedish reactor should pass through three full ASAR reviews during its life-time, similar to the licensing inspection before start-up of the reactor. The first series ASAR was delivered by FKA to SKI in December 1996, and forms the basis for the SKI analysis in the present report

  3. SKI - ASAR - R1. As operated Safety Analysis Report. Recurring safety review 1995 Ringhals 1

    International Nuclear Information System (INIS)

    2000-01-01

    According to Swedish law, the reactor owner is responsible for performing a safety review and writing a so called ASAR-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the so called SKI-ASAR-report). Each Swedish reactor should pass through three full ASAR reviews during its lifetime, similar to the licensing inspection before start-up of the reactor. The second series ASAR was delivered by the Ringhals utility to SKI in September 1995, and forms the basis for the SKI analysis in the present report

  4. 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...

  5. 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...

  6. 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...

  7. 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...

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

    International Nuclear Information System (INIS)

    2001-07-01

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

  9. Current Status of Periodic Safety Review of HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Minjin; Ahn, Guk-Hoon; Lee, Choong Sung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    A PSR for a research reactor became a legal requirement as the Nuclear Safety Act was amended and came into effect in 2014. This paper describes the current status and methodology of the first Periodic Safety Review (PSR) of HANARO that is being performed. The legal requirements, work plan, and process of implementing a PSR are described. Because this is the first PSR for a research reactor, it is our understating that the operating organization and regulatory body should communicate well with each other to complete the PSR in a timely manner. The first PSR of HANARO is under way. In order to achieve a successful result, activities of the operation organization such as scheduling, maintaining consistency in input data for review, and reviewing the PSR reports that will require intensive resources should be well planned. This means the operating organization needs to incorporate appropriate measures to ensure the transfer of knowledge and expertise arising from the PSR via a contractor to the operation organization. It is desirable for the Regulatory Body to be involved in all stage of the PSR to prevent any waste of resources and minimize the potential for a reworking of the PSR and the need for an additional assessment and review as recommended by foreign experts.

  10. An international review of patient safety measures in radiotherapy practice

    International Nuclear Information System (INIS)

    Shafiq, Jesmin; Barton, Michael; Noble, Douglas; Lemer, Claire; Donaldson, Liam J.

    2009-01-01

    Errors from radiotherapy machine or software malfunction usually are well documented as they affect hundreds of patients, whereas random errors affecting individual patients are more difficult to be discovered and prevented. Although major clinical radiotherapy incidents have been reported, many more have remained unrecognised or have not been reported. The literature in this field is limited as it is mostly published as a result of investigation of major errors. We present a review of radiotherapy incidents internationally with the aim of identifying the domains where most errors occur through extensive review and synthesis of published reports, unpublished 'Grey literature' and departmental incident data. Our review of radiotherapy-related events in the last three decades (1976-2007) identified more than seven thousand (N = 7741) incidents and near misses. Three thousand one hundred and twenty-five incidents reported patient harm of variable intensity ranging from underdose increasing the risk of recurrence, to overdose causing toxicity, and even death for 1% (N = 38); 4616 events were near misses with no recognisable patient harm. Based on our review, a radiotherapy risk profile has been published by the WHO World Alliance for Patient Safety that highlights the role of communication, training and strict adherence to guidelines/protocols in improving the safety of radiotherapy process.

  11. 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

  12. 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...

  13. [A systematic review of the effectiveness of workplace safety interventions].

    Science.gov (United States)

    Baldasseroni, A; Olimpi, Nadia; Bonaccorsi, G

    2009-01-01

    The authors carried out a systematic review of the effectiveness of workplace safety interventions, as a part of a wider project funded by CCM, Centre for Disease Control. Several electronic bibliographic databases were checked, using a standardized string selection. The string contained the following four items: the intervention; job features; type of injury; efficacy/effectiveness. Of the various databases consulted, Web of Science was the most efficient. Overall 5531 articles were selected. After reading the title and abstract, 4695 were excluded and eventually 35 systematic reviews were selected, which synthesized 769 original articles. The main topics of the selected systematic reviews were: certain sectors (building industry, agriculture, health care); personal protective equipment; work organization and prevention management at plant level; evaluation of prevention policies by national and regional authorities. A clear need for multiple bibliographical data-base search emerged at the end of this study.

  14. 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)

  15. The safety of bone allografts used in dentistry: a review.

    Science.gov (United States)

    Holtzclaw, Dan; Toscano, Nicholas; Eisenlohr, Lisa; Callan, Don

    2008-09-01

    Recent media reports concerning "stolen body parts" have shaken the public's trust in the safety of and the use of ethical practices involving human allografts. The authors provide a comprehensive review of the safety aspects of human bone allografts. The authors reviewed U.S. government regulations, industry standards, independent industry association guidelines, company guidelines and scientific articles related to the use of human bone allografts in the practice of dentistry published in the English language. The use of human bone allografts in the practice of dentistry involves the steps of procurement, processing, use and tracking. Rigorous donor screening and aseptic proprietary processing programs have rendered the use of human bone allografts safe and effective as a treatment option. When purchasing human bone allografts for the practice of dentistry, one should choose products accredited by the American Association of Tissue Banks for meeting uniformly high safety and quality control measures. Knowledge of human bone allograft procurement, processing, use and tracking procedures may allow dental clinicians to better educate their patients and address concerns about this valuable treatment option.

  16. Review of SFR Design Safety using Preliminary Regulatory PSA Model

    International Nuclear Information System (INIS)

    Na, Hyun Ju; Lee, Yong Suk; Shin, Andong; Suh, Nam Duk

    2013-01-01

    The major objective of this research is to develop a risk model for regulatory verification of the SFR design, and thereby, make sure that the SFR design is adequate from a risk perspective. In this paper, the development result of preliminary regulatory PSA model of SFR is discussed. In this paper, development and quantification result of preliminary regulatory PSA model of SFR is discussed. It was confirmed that the importance PDRC and ADRC dampers is significant as stated in the result of KAERI PSA model. However, the importance can be changed significantly depending on assumption of CCCG and CCF factor of PDRC and ADRC dampers. SFR (sodium-cooled fast reactor) which is Gen-IV nuclear energy system, is designed to accord with the concept of stability, sustainability and proliferation resistance. KALIMER-600, which is under development in Korea, includes passive safety systems (e. g. passive reactor shutdown, passive residual heat removal, and etc.) as well as active safety systems. Risk analysis from a regulatory perspective is needed to support the regulatory body in its safety and licensing review for SFR (KALIMER-600). Safety issues should be identified in the early design phase in order to prevent the unexpected cost increase and delay of the SFR licensing schedule that may be caused otherwise

  17. 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

  18. 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

  19. Review of the DOE Packaging and Transportation Safety Program

    International Nuclear Information System (INIS)

    Snyder, B.J.; Cece, J.M.

    1992-12-01

    This report documents the results of a year-long self-assessment of DOE-EH transportation and packaging safety activities. The self-assessment was initiated in September 1991 and concluded in August 1992. The self-assessment identified several significant issues, some of which have been resolved by EH. Also, improvements in the EH program were made during the course of the self-assessment. The report reflects the status of the EH transportation and packaging safety activities at the conclusion of the self-assessment. This report consists of several sections which discuss background, objectives and description of the review. Another section includes summary discussion and key conclusions. Appendix A, Issues, Observations and Recommendations, lists fifteen issues, including appropriate observations and recommendations. A Corrective Action Plan, which documents EH managements resolve to implement the agreed-upon recommendations, is included. The Corrective Action Plan reflects the status of completed and planned actions as of the date of the report

  20. Modern diaper performance: construction, materials, and safety review.

    Science.gov (United States)

    Dey, Swatee; Kenneally, Dianna; Odio, Mauricio; Hatzopoulos, Ioannis

    2016-07-01

    A review of the literature on diapers and diaper rash reveals that many clinicians are unfamiliar with modern diaper construction and materials as well as diaper safety testing methods. Typical modern diapers do not contain ingredients of concern such as latex and disperse dyes, but use ingredients such as spandex and pigments with a favorable safety profile. Today's disposable diaper is a high performance product whose carefully designed layers and liners provide optimal urine and feces absorption and an ever more clothing-like and comfortable fit. This is possible due to a variety of specialized polymer materials that provide optimal absorption of urine and feces, thereby minimizing skin exposure. © 2016 The International Society of Dermatology.

  1. How Swedish communities organised themselves in reviewing a safety case

    International Nuclear Information System (INIS)

    Soderblom, Anna-Lena

    2014-01-01

    Full text of publication follows: In 2009 the Swedish nuclear waste management company, SKB, choose Forsmark in the municipality of Oesthammar as the best place for a repository for spent nuclear fuel. In 2011, as a natural follow-up, SKB presented applications to two Swedish authorities, the Land and Environmental Court and the Swedish Radiation Safety Authority. The municipality of Oesthammar has together with the municipality of Oskarshamn been an active part in the process since 1994, with different local organisations financed by the Swedish nuclear fund. Three leading themes form the basis for our participation - voluntarism, complete openness of plans and results and participation with the possibility to influence. Site investigations for a repository started in 2002 and were finished when SKB selected Oesthammar municipality in the middle of 2009. To follow and scrutinise both site investigations as well as the applications, the organisation within the municipality has changed over time. As the site selection process got underway, the municipality extended its organisation to three committees (EIA, long-term safety and consultation). The committees have respective objectives: reviewing the health and environmental impact, reviewing the long-term safety and communication about the work that is going on within and around the municipality. These are primarily political committees to which a unit of civil servants is attached. The main goal for the organisation is to build up knowledge skills and prepare both the existing as well as the future municipality council for the decision of whether or not the municipality of Oesthammar will accept a final repository for spent nuclear fuel in our municipality. The absolutely most important issue for the municipality is long term-safety and as the process has progressed the municipality has made several statements to the authorities. (authors)

  2. Shielding modification and safety review on the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Osanai, Masao

    1978-01-01

    The Japan Atomic Energy Commission (JAEC) called on the Japan Nuclear Ship Development Agency (JNSDA) for shielding modification and safety review on the nuclear ship ''Mutsu'', and JNSDA has conducted the research and development (R and D) to meet the request of JAEC for the above two items. Concerning the shield modification, the following matters are described: the study on the cause of radiation leakage which was concluded to the fast neutron streaming, the conceptual design for this modification, the mock up experiment for shielding utilizing JRR-4, the basic design following on the conceptual design, including the detailed drawings of the modified construction and the shielding analysis using RADHEAT-V3 code, and the relating experiments such as the heat transfer test of the primary shielding structure and the test of strength in stranding. As for the safety review, the survey of the troubles and the technical problems having been experienced in the light water reactor plants of land use, for example, fuel integrity, stress corrosion cracking and the leakage of steam generator tubes, the revision of the design so as to adapt to current safety standards and regulations, for example, in-service inspection, the setting of additional leak detectors in the primary cooling system, the modification of emergeney filters, etc., and the review of the design and construction corresponding to recent R and D works, such as re-evaluation of the core design, cooling capability of natural circulation, thermal stress analysis of main pipings, and the evaluation of ECCS performance are presented . (Nakai, Y.)

  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. Safety analysis and review system: a Department of Energy safety assurance tool

    International Nuclear Information System (INIS)

    Rosenthal, H.B.

    1981-01-01

    The concept of the Safety Analysis and Review System is not new. It has been used within the Department and its predecessor agencies, Atomic Energy Commission (AEC) and Energy Research and Development Administration (ERDA), for over 20 years. To minimize the risks from nuclear reactor and power plants, the AEC developed a process to support management authorization of each operation through identification and analysis of potential hazards and the measures taken to control them. As the agency evolved from AEC through ERDA to the Department of Energy, its responsibilities were broadened to cover a diversity of technologies, including those associated with the development of fossil, solar, and geothermal energy. Because the safety analysis process had proved effective in a technology of high potential hazard, the Department investigated the applicability of the process to the other technologies. This paper describes the system and discusses how it is implemented within the Department

  5. Brief review: sleep health and safety for transportation workers

    Directory of Open Access Journals (Sweden)

    Quan SF

    2015-03-01

    Full Text Available Accidents related to sleepiness related fatigue are an important concern in transportation related industries. This brief review outlines the public safety concerns with sleepiness related fatigue in the railroad, aviation and motor vehicle transportation fields. In addition, the common causes of sleepiness related fatigue, and impact on operators and their families are highlighted. It is suggested that in addition to greater recognition and changes in duty hour regulations, there should be a greater emphasis on the education of operators on the importance of sleep and circadian factors in causing fatigue, as well as strategies to mitigate their impact.

  6. Response to Absorber-Focus Coil Preliminary Safety Review Panel

    International Nuclear Information System (INIS)

    Barr, Giles; Baynham, Elwyn; Black, Edgar; Bradshaw, Tom; Cummings, Mary Anne; Green, Michael A.; Ishimoto, Shigeru; Ivanyushenkov, Yury; Lau, Wing; Zisman, Michael S.

    2004-01-01

    In this document we provide responses to the various issues raised in the report of the Preliminary Safety Review Panel (see http://mice.iit.edu/mnp/MICE0069.pdf). In some cases we have made design changes in response to the Panels suggestions. In other cases, we have chosen not to do so. In a few cases, we indicate our plans, although the tasks have not yet been completed. For simplicity, the responses are organized along the same lines as those of the Panel Report

  7. Review of irradiation experiments for water reactor safety research

    International Nuclear Information System (INIS)

    Tobioka, Toshiaki

    1977-02-01

    A review is made of irradiation experiments for water reactor safety research under way in both commercial power plants and test reactors. Such experiments are grouped in two; first, LWR fuel performance under normal and abnormal operating conditions, and second, irradiation effects on fracture toughness in LWR vessels. In the former are fuel densification, swelling, and the influence of power ramp and cycling on fuel rod, and also fuel rod behavior under accident conditions in in-reactor experiment. In the latter are the effects of neutron exposure level on the ferritic steel of pressure vessels, etc.. (auth.)

  8. 76 FR 80368 - Notification of a Public Meeting of the Science Advisory Board Libby Amphibole Asbestos Review Panel

    Science.gov (United States)

    2011-12-23

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9610-8] Notification of a Public Meeting of the Science...: Notice. SUMMARY: The Environmental Protection Agency (EPA or Agency) Science Advisory Board (SAB) [email protected] . General information concerning the EPA Science Advisory Board can be found at the EPA SAB...

  9. Team of experts concludes review of safety issues at Temelin

    International Nuclear Information System (INIS)

    2001-01-01

    Full text: At the request of the Czech Government, the International Atomic Energy Agency (IAEA) assembled a team of national experts from Bulgaria, France, Germany, Spain, and the United Kingdom, with an observer from Austria, to review safety issues at the Temelin power plant that were identified in 1996 as relevant to reactors of the generic Temelin design (WWER-1000/320 type). Following a detailed on-site review from 18 to 23 November 2001, the experts concluded that most identified issues had been addressed and resolved. Work is continuing on the few remaining issues. These issues, however, are not judged by them to be significant and would not from the experts' standpoint preclude the safe operation of the Temelin nuclear power plant. The final report of the team of experts will be available to the Czech Government in one month's time. (author)

  10. 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

  11. Experience in the review of utility control room design review and safety parameter display system programs

    International Nuclear Information System (INIS)

    Moore, V.A.

    1985-01-01

    The Detailed Control Room Design Review (DCRDR) and the Safety Parameter Display System (SPDS) had their origins in the studies and investigations conducted as the result of the TMI-2 accident. The President's Commission (Kemeny Commission) critized NRC for not examining the man-machine interface, over-emphasizing equipment, ignoring human beings, and tolerating outdated technology in control rooms. The Commission's Special Inquiry Group (Rogovin Report) recommended greater application of human factors engineering including better instrumentation displays and improved control room design. The NRC Lessons Learned Task Force concluded that licensees should review and improve control rooms using NRC Human engineering guidelines, and install safety parameter display systems (then called the safety staff vector). The TMI Action Plan Item I.D.1 and I.D.2 were based on these recommendations

  12. Fission, critical mass and safety-a historical review

    International Nuclear Information System (INIS)

    Meggitt, Geoff

    2006-01-01

    Since the discovery of fission, the notion of a chain reaction in a critical mass releasing massive amounts of energy has haunted physicists. The possibility of a bomb or a reactor prompted much of the early work on determining a critical mass, but the need to avoid an accidental critical excursion during processing or transport of fissile material drove much that took place subsequently. Because of the variety of possible situations that might arise, it took some time to develop adequate theoretical tools for criticality safety and the early assessments were based on direct experiment. Some extension of these experiments to closely similar situations proved possible, but it was not until the 1960s that theoretical methods (and computers to run them) developed enough for them to become reliable assessment tools. Validating such theoretical methods remained a concern, but by the end of the century they formed the backbone of criticality safety assessment. This paper traces the evolution of these methods, principally in the UK and USA, and summarises some related work concerned with the nature of criticality accidents and their radiological consequences. It also indicates how the results have been communicated and used in ensuring nuclear safety. (review)

  13. Integrated Approaches to Occupational Health and Safety: A Systematic Review.

    Science.gov (United States)

    Cooklin, A; Joss, N; Husser, E; Oldenburg, B

    2017-09-01

    The study objective was to conduct a systematic review of the effectiveness of integrated workplace interventions that combine health promotion with occupational health and safety. Electronic databases (n = 8), including PsychInfo and MEDLINE, were systematically searched. Studies included were those that reported on workplace interventions that met the consensus definition of an "integrated approach," published in English, in the scientific literature since 1990. Data extracted were occupation, worksite, country, sample size, intervention targets, follow-up period, and results reported. Quality was assessed according to American College of Occupational and Environmental Medicine Practice Guidelines. Heterogeneity precluded formal meta-analyses. Results were classified according to the outcome(s) assessed into five categories (health promotion, injury prevention, occupational health and safety management, psychosocial, and return-on-investment). Narrative synthesis of outcomes was performed. A total of 31 eligible studies were identified; 23 (74%) were (quasi-)experimental trials. Effective interventions were most of those aimed at improving employee physical or mental health. Less consistent results were reported from integrated interventions targeting occupational health and safety management, injury prevention, or organizational cost savings. Integrated approaches have been posed as comprehensive solutions to complex issues. Empirical evidence, while still emerging, provides some support for this. Continuing investment in, and evaluation of, integrated approaches are worthwhile.

  14. Regulatory review of probabilistic safety assessment (PSA) level 1

    International Nuclear Information System (INIS)

    2000-02-01

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

  15. 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

  16. 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

  17. A review on safety and efficacy of products containing Longifolia

    Directory of Open Access Journals (Sweden)

    Abdul Hafeez Ahmad Hamdi

    2016-01-01

    Full Text Available Eurycoma longifolia (commonly called tongkat ali is a flowering plant in the family Simaroubaceae, native to Indonesia, Malaysia, and, to a lesser extent, Thailand, Vietnam and also Laos. The roots extract of E. longifolia, is a well-known traditional herbal medicine in Asia used for many purposes such as sexual dysfunction, aging, malaria, cancer, diabetes, anxiety, aches, constipation, exercise recovery, fever, increased energy, increased strength, leukemia, osteoporosis, stress, syphilis and glandular swelling. The roots are also used as an aphrodisiac, antibiotic, appetite stimulant and health supplement. It is very important to conserve this valuable medicinal plant for the health benefit of future generations. The purpose of this review article is to evaluate and summarize the existing literatures regarding the efficacy and safety of products which contain E. longifolia as its main ingredient. In summary, based on the literature evaluated in this review article, products which contain tongkat ali showed a clinical benefit on improving erectile dysfunction as well as a good safety profile. We recommend consumers to check the level of the bioactive compound “eurycomanone” as their guide before choosing any E. longifolia product.

  18. Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

    International Nuclear Information System (INIS)

    1996-12-01

    The meeting provided an overview of the key issues on passive safety. Technical problems which may affect future deployment, and the operating experience of passive systems and components, as well as, definitions of passive safety terms, were discussed. Advantages and disadvantages of passive systems were also highlighted. The philosophy behind different passive safety systems was presented and the range of possibility between fully passive and fully active systems was discussed. Refs, figs, tabs

  19. Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The meeting provided an overview of the key issues on passive safety. Technical problems which may affect future deployment, and the operating experience of passive systems and components, as well as, definitions of passive safety terms, were discussed. Advantages and disadvantages of passive systems were also highlighted. The philosophy behind different passive safety systems was presented and the range of possibility between fully passive and fully active systems was discussed. Refs, figs, tabs.

  20. Phenomenological Studies on Sodium for CSP Applications: A Safety Review

    Energy Technology Data Exchange (ETDEWEB)

    Armijo, Kenneth Miguel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Concentrating Solar Technologies Dept.; Andraka, Charles E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Concentrating Solar Technologies Dept.

    2016-09-01

    Sodium as a heat transfer fluid (HTF) can achieve temperatures above 700°C to improve power cycle performance for reducing large infrastructure costs of high-temperature systems. Current concentrating solar power (CSP) sensible HTF’s (e.g. air, salts) have poor thermal conductivity, and thus low heat transfer capabilities, requiring a large receiver. The high thermal conductivity of sodium has demonstrated high heat transfer rates on dish and towers systems, which allow a reduction in receiver area by a factor of two to four, reducing re-radiation and convection losses and cost by a similar factor. Sodium produces saturated vapor at pressures suitable for transport starting at 600°C and reaches one atmosphere at 870°C, providing a wide range of suitable latent operating conditions that match proposed high temperature, isothermal input power cycles. This advantage could increase the receiver and system efficiency while lowering the cost of CSP tower systems. Although there are a number of desirable thermal performance advantages associated with sodium, its propensity to rapidly oxidize presents safety challenges. This investigation presents a literature review that captures historical operations/handling lessons for advanced sodium systems, and the current state-of-knowledge related to sodium combustion behavior. Technical and operational solutions addressing sodium safety and applications in CSP will be discussed, including unique safety hazards and advantages using latent sodium. Operation and maintenance experience from the nuclear industry with sensible and latent systems will also be discussed in the context of safety challenges and risk mitigation solutions.

  1. Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

  2. 77 FR 3546 - Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting Medical Review Board: Joint...

    Science.gov (United States)

    2012-01-24

    ... Thursday, February 9, 2012, from 8:30 a.m. to 12 p.m., E.T. The meetings will be held at the Hilton... floor. The Hilton Alexandria Old Town is located across the street from the King Street Metro station...

  3. 78 FR 75924 - Request for Nominations of Candidates To Serve on the Mine Safety and Health Research Advisory...

    Science.gov (United States)

    2013-12-13

    ..., occupational safety and health engineering, chemistry, safety and health education, ergonomics, epidemiology... 15236, telephone (412) 386-5301. The Director, Management Analysis and Services Office, has been... Office, Centers for Disease Control and Prevention. [FR Doc. 2013-29747 Filed 12-12-13; 8:45 am] BILLING...

  4. 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.

  5. Maintaining knowledge, training and infrastructure for research and development in nuclear safety. A note by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    International Nuclear Safety Advisory Group

    2001-01-01

    The purpose of this INSAG Note is to emphasize the importance of maintaining capabilities for nuclear research and education, especially with regard to safety aspects, so that nuclear safety may be maintained in IAEA Member States, and to alert Member States to the potential for significant harm if the infrastructure for research, development and education is not maintained

  6. 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

  7. Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Ed.). Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-06-15

    This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material (2012 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Standards Series No. TS-G-1.1 Rev. 1, which was issued in 2008.

  8. 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

  9. Review of key Belotero Balance safety and efficacy trials.

    Science.gov (United States)

    Lorenc, Z Paul; Fagien, Steven; Flynn, Timothy C; Waldorf, Heidi A

    2013-10-01

    Belotero Balance is a novel highly cross-linked hyaluronic acid that uses cohesive polydensified matrix technology to achieve cohesive gel; improved adaptation by the dermis; and a soft, smooth fill. Several studies have now compared Belotero Balance to bovine collagen and other hyaluronic acids. Two pivotal studies demonstrated the noninferiority and superiority of Belotero Balance to bovine collagen. In the first study, more than half of the patients maintained optimal correction at 6 months on the Belotero-treated side of the face. The second of those two studies followed patients to week 96 and demonstrated that the effects of Belotero Balance in this long-term, open-label study persisted in the majority of subjects without repeated treatment for at least one interval of 48 weeks. The filler was well tolerated, with only one of 34 total adverse events (injection-site bruising) considered to be related to the study device. A third study compared the safety and efficacy of other hyaluronic acids (i.e., Juvéderm and Restylane) with Belotero Balance. In this study, the safety profiles of all three hyaluronic acids were generally favorable, with site-specific adverse events mild to moderate and comparable across each hyaluronic acid. Aesthetic results were also similar, although Belotero Balance resulted in greater evenness than Restylane at 4 weeks by one indicator used in the study. Finally, a 5-year retrospective safety review of 317 patients treated with Belotero Balance over a 5-year period revealed no severe adverse events in any patients, including the absence of persistent nodules or granulomas.

  10. Reviewing real-time performance of nuclear reactor safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Preckshot, G.G. [Lawrence Livermore National Lab., CA (United States)

    1993-08-01

    The purpose of this paper is to recommend regulatory guidance for reviewers examining real-time performance of computer-based safety systems used in nuclear power plants. Three areas of guidance are covered in this report. The first area covers how to determine if, when, and what prototypes should be required of developers to make a convincing demonstration that specific problems have been solved or that performance goals have been met. The second area has recommendations for timing analyses that will prove that the real-time system will meet its safety-imposed deadlines. The third area has description of means for assessing expected or actual real-time performance before, during, and after development is completed. To ensure that the delivered real-time software product meets performance goals, the paper recommends certain types of code-execution and communications scheduling. Technical background is provided in the appendix on methods of timing analysis, scheduling real-time computations, prototyping, real-time software development approaches, modeling and measurement, and real-time operating systems.

  11. Reviewing real-time performance of nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Preckshot, G.G.

    1993-08-01

    The purpose of this paper is to recommend regulatory guidance for reviewers examining real-time performance of computer-based safety systems used in nuclear power plants. Three areas of guidance are covered in this report. The first area covers how to determine if, when, and what prototypes should be required of developers to make a convincing demonstration that specific problems have been solved or that performance goals have been met. The second area has recommendations for timing analyses that will prove that the real-time system will meet its safety-imposed deadlines. The third area has description of means for assessing expected or actual real-time performance before, during, and after development is completed. To ensure that the delivered real-time software product meets performance goals, the paper recommends certain types of code-execution and communications scheduling. Technical background is provided in the appendix on methods of timing analysis, scheduling real-time computations, prototyping, real-time software development approaches, modeling and measurement, and real-time operating systems

  12. Employing ionizing radiation to enhance food safety. A review

    International Nuclear Information System (INIS)

    Grolichova, M.; Dvorak, P.; Musilova, H.

    2004-01-01

    Food irradiation is employed to ensure food safety or food sterility, extend its shelf-life and reduce the losses due to sprouting, ripening or pests. In the Czech Republic mainly spices, mixed spices and dried vegetables are exposed to ionizing radiation. The leading suppliers of irradiated foodstuffs in Europe are Belgium, France and the Netherlands. In the USA, food irradiation is more common and there are also attempts to enforce irradiation not only for food safety, but also for technological purposes. Even though irradiation is a prospective technology, its application causes physico-chemical changes that may affect nutritional adequacy and sensory characteristics of irradiated food. In this paper, the chemical changes of basic food components (proteins, saccharides, fats) are reviewed. Some chemical changes lead to the formation of radiolytic products whose risks are still subject of scientific research. It is expected that the main use of gamma irradiation will be the treatment of diets for patients suffering from different disorders of the immune system, allergic patients or for the army and space flights. Irradiation may be a critical control point in the production of some types of foodstuffs

  13. Safety of treatment options for spondyloarthritis: a narrative review.

    Science.gov (United States)

    D'Angelo, Salvatore; Carriero, Antonio; Gilio, Michele; Ursini, Francesco; Leccese, Pietro; Palazzi, Carlo

    2018-05-01

    Spondyloarthritis (SpA) are chronic inflammatory diseases with overlapping pathogenic mechanisms and clinical features. Treatment armamentarium against SpA includes non-steroidal anti-inflammatory drugs, glucocorticoids, conventional disease-modifying antirheumatic drugs (DMARDs, including sulfasalazine, methotrexate, leflunomide, cyclosporine), targeted synthetic DMARDs (apremilast) and biological DMARDs (TNF inhibitors, anti-IL 12/23 and anti-IL-17 agents). Areas covered: A narrative review of published literature on safety profile of available SpA treatment options was performed. Readers will be provided with a comprehensive overview on frequent and rare adverse events associated with each drug listed in current SpA treatment recommendations. Expert opinion: The overall safety profile of such molecules is good and serious adverse events are rare but need to be promptly recognized and treated. However, the monitoring of adverse events is a major challenge for clinicians because it is not adequately addressed by current treatment recommendations. A tailored treatment is crucial and rheumatologists must accurately select patients in order to identify those more susceptible to develop adverse events.

  14. Westinghouse independent safety review of Savannah River production reactors

    Energy Technology Data Exchange (ETDEWEB)

    Leggett, W.D.; McShane, W.J. (Westinghouse Hanford Co., Richland, WA (USA)); Liparulo, N.J.; McAdoo, J.D.; Strawbridge, L.E. (Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear and Advanced Technology Div.); Toto, G. (Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Services Div.); Fauske, H.K. (Fauske and Associates, Inc., Burr Ridge, IL (USA)); Call, D.W. (Westinghouse Savannah R

    1989-04-01

    Westinghouse Electric Corporation has performed a safety assessment of the Savannah River production reactors (K,L, and P) as requested by the US Department of Energy. This assessment was performed between November 1, 1988, and April 1, 1989, under the transition contract for the Westinghouse Savannah River Company's preparations to succeed E.I. du Pont de Nemours Company as the US Department of Energy contractor for the Savannah River Project. The reviewers were drawn from several Westinghouse nuclear energy organizations, embody a combination of commercial and government reactor experience, and have backgrounds covering the range of technologies relevant to assessing nuclear safety. The report presents the rationale from which the overall judgment was drawn and the basis for the committee's opinion on the phased restart strategy proposed by E.I. du Pont de Nemours Company, Westinghouse, and the US Department of Energy-Savannah River. The committee concluded that it could recommend restart of one reactor at partial power upon completion of a list of recommended upgrades both to systems and their supporting analyses and after demonstration that the organization had assimilated the massive changes it will have undergone.

  15. Westinghouse independent safety review of Savannah River production reactors

    International Nuclear Information System (INIS)

    Leggett, W.D.; McShane, W.J.; Liparulo, N.J.; McAdoo, J.D.; Strawbridge, L.E.; Call, D.W.

    1989-01-01

    Westinghouse Electric Corporation has performed a safety assessment of the Savannah River production reactors (K, L, and P) as requested by the US Department of Energy. This assessment was performed between November 1, 1988, and April 1, 1989, under the transition contract for the Westinghouse Savannah River Company's preparations to succeed E.I. du Pont de Nemours ampersand Company as the US Department of Energy contractor for the Savannah River Project. The reviewers were drawn from several Westinghouse nuclear energy organizations, embody a combination of commercial and government reactor experience, and have backgrounds covering the range of technologies relevant to assessing nuclear safety. The report presents the rationale from which the overall judgment was drawn and the basis for the committee's opinion on the phased restart strategy proposed by E.I. du Pont de Nemours ampersand Company, Westinghouse, and the US Department of Energy-Savannah River. The committee concluded that it could recommend restart of one reactor at partial power upon completion of a list of recommended upgrades both to systems and their supporting analyses and after demonstration that the organization had assimilated the massive changes it will have undergone. 37 refs., 1 fig., 3 tabs

  16. 76 FR 23644 - Solicitation of Nominations for Members of the Transit Rail Advisory Committee for Safety (TRACS)

    Science.gov (United States)

    2011-04-27

    ... communication of information from knowledgeable and independent perspectives regarding transit rail safety... evaluated mainly on academic experience but also the following factors: Leadership and organizational skills... committee member's name and organizational affiliation, a cover letter describing the nominee's...

  17. Statin Therapy: Review of Safety and Potential Side Effects.

    Science.gov (United States)

    Ramkumar, Satish; Raghunath, Ajay; Raghunath, Sudhakshini

    2016-11-01

    Hydroxymethyl glutaryl coenzyme A reductase inhibitors, commonly called statins, are some of the most commonly prescribed medications worldwide. Evidence suggests that statin therapy has significant mortality and morbidity benefit for both primary and secondary prevention from cardiovascular disease. Nonetheless, concern has been expressed regarding the adverse effects of long term statin use. The purpose of this article was to review the current medical literature regarding the safety of statins. Major trials and review articles on the safety of statins were identified in a search of the MEDLINE database from 1980 to 2016, which was limited to English articles. Myalgia is the most common side effect of statin use, with documented rates from 1-10%. Rhabdomyolysis is the most serious adverse effect from statin use, though it occurs quite rarely (less than 0.1%). The most common risk factors for statin-related myopathy include hypothyroidism, polypharmacy and alcohol abuse. Derangement in liver function tests is common, affecting up to 1% of patients; however, the clinical significance of this is unknown. Some statin drugs are potentially diabetogenic and the risk appears to increase in those patients on higher doses. Pitavastatin has not been associated with increased risk of diabetes. Statins have not been proven to increase the risk of malignancy, dementia, mood disorders or acute interstitial nephritis. However, statins do have multiple drug interactions, primarily those which interact with the cytochrome p450 enzyme group. Overall, statin drugs appear to be safe for use in the vast majority of patients. However, patients with multiple medical co-morbidities are at increased risk of adverse effects from long-term statin use.

  18. 76 FR 11845 - Notice of Intent To Review Structure of the Aviation Rulemaking Advisory Committee

    Science.gov (United States)

    2011-03-03

    ... Management Facility at 202-493-2251. Hand Delivery: Bring comments to the Docket Management Facility in Room... technical subject areas (presently, air carrier operations, maintenance, occupant safety, general aviation...: Renee Butner, Office of Rulemaking, ARM-24, Federal Aviation Administration, 800 Independence Ave., SW...

  19. Scientific and technical advisory committee review of the nutrient inputs to the watershed model

    Science.gov (United States)

    The following is a report by a STAC Review Team concerning the methods and documentation used by the Chesapeake Bay Partnership for evaluation of nutrient inputs to Phase 6 of the Chesapeake Bay Watershed Model. The “STAC Review of the Nutrient Inputs to the Watershed Model” (previously referred to...

  20. 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

  1. A systematic review of occupational safety and health business cases.

    Science.gov (United States)

    Verbeek, Jos; Pulliainen, Marjo; Kankaanpää, Eila

    2009-12-01

    Business cases are commonly developed as means to rationalize investment. We systematically reviewed 26 reported cases on occupational safety and health (OSH) interventions to assess if health and productivity arguments make a good business case. To be included in the review, studies had to analyze the costs and benefits, including productivity, of an OSH intervention at the enterprise level. We searched Medline and Embase for studies and used Google search in addition. Two reviewers independently selected studies and extracted data. The intervention profitability was calculated in euros (euro in 2008) as the first year's benefits minus the total intervention costs per worker. The payback period was calculated as the intervention costs divided by the first year's benefits. We found three ex-ante and 23 ex-post cases. In 20 cases, the study design was a before-after comparison without a control group. Generally a 100% reduction of injuries or sickness absence was assumed. In two cases, productivity and quality increases were very large. The main benefit was avoided sick leave. Depreciation or discounting was applied only in a minority of cases. The intervention profitability was negative in seven studies, up to euro 500 per employee in 12 studies and more than euro 500 per employee in seven studies. The payback period was less than half a year for 19 studies. Only a few studies included sensitivity analyses. Few ex-ante business cases for management decisions on OSH are reported. Guidelines for reporting and evaluation are needed. Business cases need more sound assumptions on the effectiveness of interventions and should incorporate greater uncertainty into their design. Ex-post evaluation should be based preferably on study designs that control for trends at a time different from that of the intervention.

  2. 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

  3. 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)

  4. 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

  5. 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

  6. Green light for the methodology file. Periodical safety review 2016 has begun

    International Nuclear Information System (INIS)

    2014-01-01

    Every ten years, the organisational framework and the facilities of the Belgian Nuclear Research Center SCK-CEN are subject to an encompassing safety evaluation. Together with initiatives arising from the stress tests, a large number of safety studies and actions are scheduled until 2018. The article discusses the ongoing safety review.

  7. 78 FR 41853 - Safety Advisory Guidance: Heating Rail Tank Cars To Prepare Hazardous Material for Unloading or...

    Science.gov (United States)

    2013-07-12

    ... rail tank car due to chemical self-reaction and expansion of the toluene diisocyanate matter wastes. On...: Cheryl West Freeman, Division of Engineering and Research, Pipeline and Hazardous Materials Safety... catastrophically ruptured at a transfer station at the BASF Corporation chemical facility in Freeport, Texas. The...

  8. A review of the safety aspects of radio frequency ablation

    Directory of Open Access Journals (Sweden)

    Abhishek Bhaskaran

    2015-09-01

    Full Text Available In light of recent reports showing high incidence of silent cerebral infarcts and organized atrial arrhythmias following radiofrequency (RF atrial fibrillation (AF ablation, a review of its safety aspects is timely. Serious complications do occur during supraventricular tachycardia (SVT ablations and knowledge of their incidence is important when deciding whether to proceed with ablation. Evidence is emerging for the probable role of prophylactic ischemic scar ablation to prevent VT. This might increase the number of procedures performed. Here we look at the various complications of RF ablation and also the methods to minimize them. Electronic database was searched for relevant articles from 1990 to 2015. With better awareness and technological advancements in RF ablation the incidence of complications has improved considerably. In AF ablation it has decreased from 6% to less than 4% comprising of vascular complications, cardiac tamponade, stroke, phrenic nerve injury, pulmonary vein stenosis, atrio-esophageal fistula (AEF and death. Safety of SVT ablation has also improved with less than 1% incidence of AV node injury in AVNRT ablation. In VT ablation the incidence of major complications was 5–11%, up to 3.4%, up to 1.8% and 4.1–8.8% in patients with structural heart disease, without structural heart disease, prophylactic ablations and epicardial ablations respectively. Vascular and pericardial complications dominated endocardial and epicardial VT ablations respectively. Up to 3% mortality and similar rates of tamponade were reported in endocardial VT ablation. Recent reports about the high incidence of asymptomatic cerebral embolism during AF ablation are concerning, warranting more research into its etiology and prevention.

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

    International Nuclear Information System (INIS)

    1996-10-01

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

  10. An approach for Periodic Safety Review (PSR) of units 5 and 6 of Kozloduy NPP

    International Nuclear Information System (INIS)

    Kichev, Emil

    2014-01-01

    Periodic Safety Reviews (PSR) is complementary to the routine and special safety reviews and does not replaced them. It determines the level of compliance with current safety requirements and covers all safety aspects of NPP operation and all equipment (SSCs) on site. Three levels of importance are defined for the documents in PSR (towards higher conservatism): Bulgarian documents; IAEA documents; Documents of manufactures and suppliers of the equipment (SSCs). The scope and activities consists of four stages and includes 14 safety factors (SF). Cooperation with external companies and organizations in areas with proved experience is used.

  11. 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

  12. 76 FR 17649 - Science Advisory Board Staff Office; Request for Nominations; SAB Mercury Review Panel

    Science.gov (United States)

    2011-03-30

    ... nominations of women and men of all racial and ethnic groups. The EPA SAB Staff Office will acknowledge... factors); (b) availability and willingness to serve; (c) absence of financial conflicts of interest; (d... Staff Office's evaluation of an absence of financial conflicts of interest will include a review of the...

  13. 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

  14. Safety of High Speed Magnetic Levitation Transportation Systems: Preliminary Safety Review of the Transrapid Maglev System

    Science.gov (United States)

    1990-11-01

    The safety of various magnetically levitated trains under development for possible : implementation in the United States is of direct concern to the Federal Railroad : Administration. This report, one in a series of planned reports on maglev safety, ...

  15. Lithium safety and tolerability in mood disorders: a critical review

    Directory of Open Access Journals (Sweden)

    Ivan Aprahamian

    2014-04-01

    Full Text Available Background : Lithium is a first-line treatment for bipolar disorder in all phases, also indicated as add-on drug for unipolar depression and suicide prevention. This study encompasses a broad critical review on the safety and tolerability of lithium for mood disorders. Methods : A computerized search for English written human studies was made in MEDLINE, using the keywords “lithium” and “mood disorders”, starting from July 1993 through July 2013 (n = 416. This initial search aimed to select clinical trials, prospective data, and controlled design studies of lithium treatment for mood disorders reporting adverse effects (n = 36. The final selection yielded 91 studies. Results : The most common general side effects in patients on lithium treatment were thirst, frequent urination, dry mouth, weight gain, fatigue and cognitive complaints. Lithium users showed a high prevalence of hypothyroidism, hyperparathyroidism, and decrease in urinary concentration ability. Reduction of glomerular filtration rate in patients using lithium was also observed, but in a lesser extent. The evidence of teratogenicity associated with lithium use is not well established. Anti-inflammatory non-steroidal drugs, thiazide diuretics, angiotensin-converting enzyme inhibitors, and alprazolam may increase serum lithium and the consequent risk for intoxication. Discussion : Short-term lithium treatment is associated with mild side effects. Medium and long-term lithium treatment, however, might have effects on target organs which may be prevented by periodical monitoring. Overall, lithium is still a safe option for the treatment of mood disorders.

  16. Commercial Crew Program and the Safety Technical Review Board

    Science.gov (United States)

    Mullen, Macy

    2016-01-01

    The Commercial Crew Program (CCP) is unique to any other program office at NASA. After the agency suffered devastating budget cuts and the Shuttle Program retired, the U.S. gave up its human spaceflight capabilities. Since 2011 the U.S. has been dependent on Russia to transport American astronauts and cargo to the International Space Station (ISS) and back. NASA adapted and formed CCP, which gives private, domestic, aerospace companies unprecedented reign over America's next ride to space. The program began back in 2010 with 5 companies and is now in the final phase of certification with 2 commercial partners. The Commercial Crew Program is made up of 7 divisions, each working rigorously with the commercial providers to complete the certification phase. One of these 7 divisions is Systems Engineering and Integration (SE&I) which is partly comprised of the Safety Technical Review Board (STRB). The STRB is primarily concerned with mitigating improbable, but catastrophic hazards. It does this by identifying, managing, and tracking these hazards in reports. With the STRB being in SE&I, it significantly contributes to the overall certification of the partners' vehicles. After the partners receive agency certification approval, they will have the capability to provide the U.S. with a reliable, safe, and cost-effective means of human spaceflight and cargo transport to the ISS and back.

  17. Review of health safety aspects of nanotechnologies in food production.

    Science.gov (United States)

    Bouwmeester, Hans; Dekkers, Susan; Noordam, Maryvon Y; Hagens, Werner I; Bulder, Astrid S; de Heer, Cees; ten Voorde, Sandra E C G; Wijnhoven, Susan W P; Marvin, Hans J P; Sips, Adriënne J A M

    2009-02-01

    Due to new, previously unknown, properties attributed to engineered nanoparticles many new products are introduced in the agro-food area. Nanotechnologies cover many aspects, such as disease treatment, food security, new materials for pathogen detection, packaging materials and delivery systems. As with most new and evolving technologies, potential benefits are emphasized, while little is known on safety of the application of nanotechnologies in the agro-food sector. This review gives an overview of scientific issues that need to be addressed with priority in order to improve the risk assessment for nanoparticles in food. The following research topics are considered to contribute pivotally to risk assessment of nanotechnologies and nanoparticles in food products. Set a definition for NPs to facilitate regulatory discussions, prioritization of research and exchange of study results. Develop analytical tools for the characterization of nanoparticles in complex biological matrices like food. Establish relevant dose metrics for nanoparticles used for both interpretation of scientific studies as well as regulatory frameworks. Search for deviant behavior (kinetics) and novel effects (toxicity) of nanoparticles and assess the validity of currently used test systems following oral exposure. Estimate the consumer exposure to nanoparticles.

  18. Review of the Safety Design Approaches in Sodium Fast Reactors

    International Nuclear Information System (INIS)

    Suk, Soo Dong; Lee, Yong Bum

    2009-12-01

    The principle of the Defense in depth is essential in securing the safety of nuclear power plants, that is, to prevent cores-damaging severs accidents and to minimize the radiological consequences of the accidents 'as low as possible' (ALARA). One of the major design features of sodium fast reactors (SFRs) is that it has a large amount of sodium in the reactor vessel, providing a large heat capacity, such that it is feasible to contain the consequences of sever core damaging accidents in the vessel and primary system boundary. Containment of a severe accident in the primary system boundary, that is called in-vessel retention(IVR), is not a licensing requirement but set up as a design goal in most of the SFR design in the context of risk minimization. The objective of this report is to broadly review and compare the approaches and efforts made in the some of the major SFR designs of the US, Europe and Japan to prevent severe accidents and mitigate their consequences should they occur. Specifically, the subjects described in this report include design criteria or requirements, accident categorization and acceptance criteria, design features to prevent and contain severs accidents

  19. Factors influencing the microbial safety of fresh produce: a review.

    Science.gov (United States)

    Olaimat, Amin N; Holley, Richard A

    2012-10-01

    Increased consumption, larger scale production and more efficient distribution of fresh produce over the past two decades have contributed to an increase in the number of illness outbreaks caused by this commodity. Pathogen contamination of fresh produce may originate before or after harvest, but once contaminated produce is difficult to sanitize. The prospect that some pathogens invade the vascular system of plants and establish "sub-clinical" infection needs to be better understood to enable estimation of its influence upon risk of human illness. Conventional surface sanitation methods can reduce the microbial load, but cannot eliminate pathogens if present. Chlorine dioxide, electrolyzed water, UV light, cold atmospheric plasma, hydrogen peroxide, organic acids and acidified sodium chlorite show promise, but irradiation at 1 kGy in high oxygen atmospheres may prove to be the most effective means to assure elimination of both surface and internal contamination of produce by pathogens. Pathogens of greatest current concern are Salmonella (tomatoes, seed sprouts and spices) and Escherichia coli O157:H7 on leafy greens (spinach and lettuce). This review considers new information on illness outbreaks caused by produce, identifies factors which influence their frequency and size and examines intervention effectiveness. Research needed to increase our understanding of the factors influencing microbial safety of fresh produce is addressed. Copyright © 2012 Elsevier Ltd. All rights reserved.

  20. The Safety of Ingested Caffeine: A Comprehensive Review

    Directory of Open Access Journals (Sweden)

    Jennifer L. Temple

    2017-05-01

    Full Text Available Caffeine is the most widely consumed psychoactive drug in the world. Natural sources of caffeine include coffee, tea, and chocolate. Synthetic caffeine is also added to products to promote arousal, alertness, energy, and elevated mood. Over the past decade, the introduction of new caffeine-containing food products, as well as changes in consumption patterns of the more traditional sources of caffeine, has increased scrutiny by health authorities and regulatory bodies about the overall consumption of caffeine and its potential cumulative effects on behavior and physiology. Of particular concern is the rate of caffeine intake among populations potentially vulnerable to the negative effects of caffeine consumption: pregnant and lactating women, children and adolescents, young adults, and people with underlying heart or other health conditions, such as mental illness. Here, we review the research into the safety and safe doses of ingested caffeine in healthy and in vulnerable populations. We report that, for healthy adults, caffeine consumption is relatively safe, but that for some vulnerable populations, caffeine consumption could be harmful, including impairments in cardiovascular function, sleep, and substance use. We also identified several gaps in the literature on which we based recommendations for the future of caffeine research.

  1. 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

  2. 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

  3. 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

  4. 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...

  5. 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...

  6. A review of the safety of cold pasteurization through irradiation

    International Nuclear Information System (INIS)

    Crawford, L.M.; Ruff, E.H.

    1996-01-01

    Perhaps no food process has been researched and reviewed more than food irradiation. The scientific basis and mechanisms of food irradiation are as thoroughly understood by the scientific community and regulatory agencies as traditional food processes. While irradiation provides many benefits, it cannot replace proper food handling as the single most critical food safety measure. Irradiation does not prevent contamination but it controls it.A broad spectrum of national and international studies conclude that food irradiation can accomplish the following:* inhibit sprouting in crops like potatoes, onions and garlic;* destroy insects and parasites in cereal grains, dried beans, dried and fresh fruits, meat and seafood;* delay the ripening and spoilage of fresh fruits and vegetables;* extend the shelf-life of perishable products like beef, poultry and seafood;* eliminate disease-causing microorganisms in food; bacterial and fungal spores and viruses are not affected by the most commonly used dose levels; and* sterilize at doses above 10 kGy herbs, spices and other ingredients like dried vegetables, in addition to foods prescribed for immuno-compromised hospital patients and for astronauts during space flight.Scientific research has also determined that food irradiation does not make food 'radioactive' and at low to medium doses, has little negative effect on vitamins and other nutrients humans obtain from their food supply. In cases where the level of certain vitamins are reduced, similar losses are experienced with other processing treatments such as thermal heat and canning. However, irradiation cannot destroy toxins.Scientists have also studied the creation of radiolytic products, including 'free radicals', by food irradiation. There is broad agreement among world renowned researchers, health organizations and agencies that radiolytic products formed during irradiation pose no danger to humans. This conclusion is based upon hundreds of toxicological studies, some

  7. Review of Policy Documents for Nuclear Safety and Regulation

    International Nuclear Information System (INIS)

    Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki

    2006-01-01

    The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies

  8. Review of Policy Documents for Nuclear Safety and Regulation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2006-07-01

    The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies.

  9. SRTC criticality safety technical review: Nuclear criticality safety evaluation 94-02, uranium solidification facility pencil tank module spacing

    International Nuclear Information System (INIS)

    Rathbun, R.

    1994-01-01

    Review of NMP-NCS-94-0087, ''Nuclear Criticality Safety Evaluation 94-02: Uranium Solidification Facility Pencil Tank Module Spacing (U), April 18, 1994,'' was requested of the SRTC Applied Physics Group. The NCSE is a criticality assessment to show that the USF process module spacing, as given in Non-Conformance Report SHM-0045, remains safe for operation. The NCSE under review concludes that the module spacing as given in Non-Conformance Report SHM-0045 remains in a critically safe configuration for all normal and single credible abnormal conditions. After a thorough review of the NCSE, this reviewer agrees with that conclusion

  10. Safety impacts of bicycle infrastructure: A critical review.

    Science.gov (United States)

    DiGioia, Jonathan; Watkins, Kari Edison; Xu, Yanzhi; Rodgers, Michael; Guensler, Randall

    2017-06-01

    This paper takes a critical look at the present state of bicycle infrastructure treatment safety research, highlighting data needs. Safety literature relating to 22 bicycle treatments is examined, including findings, study methodologies, and data sources used in the studies. Some preliminary conclusions related to research efficacy are drawn from the available data and findings in the research. While the current body of bicycle safety literature points toward some defensible conclusions regarding the safety and effectiveness of certain bicycle treatments, such as bike lanes and removal of on-street parking, the vast majority treatments are still in need of rigorous research. Fundamental questions arise regarding appropriate exposure measures, crash measures, and crash data sources. This research will aid transportation departments with regard to decisions about bicycle infrastructure and guide future research efforts toward understanding safety impacts of bicycle infrastructure. Copyright © 2017 Elsevier Ltd and National Safety Council. All rights reserved.

  11. Nuclear Safety: Technical progress review, January-March 1988

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-01-01

    This 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.

  12. 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

  13. FMCSA safety program effectiveness measurement : compliance review effectiveness model results for carriers with compliance reviews in FY 2008

    Science.gov (United States)

    2012-09-30

    In FY 2008, Federal and State enforcement personnel conducted 14,906 compliance reviews (CRs) on individual motor carriers. It is intended that through education, heightened safety regulation awareness, and the enforcement effects of the CR, carriers...

  14. FMCSA safety program effectiveness measurement : compliance review effectiveness model results for carriers with compliance reviews in fiscal year 2009.

    Science.gov (United States)

    2014-04-01

    In FY 2009, Federal and State enforcement personnel conducted more than 15,000 compliance reviews (CRs) on individual motor carriers. It is intended that through education, heightened safety regulation awareness, and the enforcement effects of the CR...

  15. 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'

  16. 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...

  17. 77 FR 41881 - Safety Advisory 2012-03; Buckling-Prone Conditions in Continuous Welded Rail Track

    Science.gov (United States)

    2012-07-16

    ... awareness of the potential consequences of an unexpected track buckle, particularly considering the... track is located on or near railroad bridges. It also recommends that track owners and railroads review.... CWR can produce peculiar maintenance issues for the railroad industry due to the constant temperature...

  18. Uterine sarcoma Part I—Uterine leiomyosarcoma: The Topic Advisory Group systematic review

    Directory of Open Access Journals (Sweden)

    Kuo-Chang Wen

    2016-08-01

    Full Text Available Uterine sarcomas account for 3–7% of all uterine cancers. Because of their rarity, unknown etiology, and highly divergent genetic aberration, there is a lack of consensus on risk factors for occurrence and predictive poor outcomes as well as optimal therapeutic choices. Tumor types according to the World Health Organization classification include leiomyosarcoma, endometrial stroma sarcoma, and undifferentiated sarcoma. Staging is done using the 2014 Federation International Gynecology and Obstetrics and 2010 American Joint Committee on Cancer tumor, lymph node, and metastases systems. Tumor grade can be classified based on the French Federation of Cancer Centers Sarcoma Group system or the Broder’s system that incorporates tumor differentiation, mitotic count, and tumor necrosis. This review is a series of articles discussing uterine sarcoma, and this is Part I, which focuses on one of the subtypes of uterine sarcomas—uterine leiomyosarcoma. The clinical characteristics, diagnosis, outcome, and recent advances are summarized in this article.

  19. A critical review on toxicological safety of 2-alkylcyclobutanones

    International Nuclear Information System (INIS)

    Song, Beom-Seok; Choi, Soo-Jeong; Jin, Young-Bae; Park, Jong-Heum; Kim, Jae-Kyung; Byun, Eui-Baek; Kim, Jae-Hun; Lee, Ju-Woon; Kim, Gang-Sung; Marchioni, Eric

    2014-01-01

    2-Alkylcyclobutanones (2-ACBs) are known as unique radiolytic products generated from the major fatty acids and triglycerides in food through only irradiation. Since 1990, studies on the toxicological safety of 2-ACBs have been conducted extensively with synthetic compounds. Mutagenicity tests of 2-ACBs on the microorganisms reviewed in this study clearly indicate that no evidence was observed, while several in vitro studies demonstrated the cytotoxicity of 2-ACBs through cell death. Moreover, the genotoxicity of 2-ACBs was suggested as DNA strand breaks were observed. However, these findings should be interpreted with caution because genotoxicity may result from cytotoxicity, which causes DNA damage or from cell membrane destruction and indirect oxidative DNA damage. Therefore, elucidation of the mechanism of genotoxic effects is needed. With regards to the suggestion of Raul et al. (2002) who showed the promoting effect of colon cancer by the administration of 2-ACBs, further studies are needed to correct some experimental design errors. Moreover, an in-vivo experiment that evaluated the metabolism of 2-ACBs has revealed that 2-dDCB was metabolized into cyclic alcohol and excreted through fecal discharge. In conclusion, it is considered that the ingestion of 2-ACBs through irradiated foods is unlikely to affect the human health. However, more specific studies are required to identify the fate of 2-ACBs in body and the LD 50 values. The determination of chronic toxicity by long-term exposure to low concentrations of 2-ACBs has to be evaluated more clearly to determine if these compounds are safe to human. - Highlights: • Mutagenicity 2-ACBs on the microorganisms was not observed. • Several in vitro studies demonstrated the cytotoxicity of 2-ACBs. • Genotoxicity of 2-ACBs was suggested, but elucidation of the mechanism is needed. • 2-dDCB was metabolized into cyclic alcohol and excreted in feces. • Further studies for toxicity of 2-ACBs following

  20. Radiation safety, protection and recommendations in dentistry - a review

    International Nuclear Information System (INIS)

    Castelino, Renita

    2013-01-01

    Radiation is the transmission of energy through space and matter. Diagnostic radiology uses ionizing radiations which have sufficient energy to ionize atoms or molecules in biological and other systems. X-rays used in diagnostic radiology are a potent mutagenic agent, capable of inducing both gene mutations and chromosomal aberrations. X-rays are extensively used in medical and dental practice for the purpose of diagnosis and treatment. X-rays provide useful information and aid in diagnosis but at the same time they also have the potential to cause harmful effects. In dentistry X-rays are used mainly for diagnosis. Radiation in doses required for dentistry may not present any major risks, however these small doses are not necessarily risk free. Hence, no exposure to X-rays can be considered completely free of risk, so the use of radiation by dentists is accompanied by a responsibility to ensure appropriate protection. Several radiation safety measures have been recommended and advocated to reduce harmful effects. Dental professionals are the only practitioners who perform radiographical examination of their patients themselves. Although the exposure used in dentistry is low every effort should be made to reduce radiation in order to prevent the accumulated dose to the dentist in their lifetime. The dose reduction can be achieved in three main steps. They are decision making, optimising radiologic procedures and patient protection. The potential for undesirable effects must be balanced against the benefits obtained from radiographs. Therefore, the aim of the paper is to review important parameters that must be taken into consideration in the clinical set up to reduce radiation exposure to patients and dental personnel. (author)