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Sample records for safety review panel

  1. Panel Resource Management (PRM) Implementation and Effects within Safety Review Panel Settings and Dynamics

    Science.gov (United States)

    Taylor, Robert W.; Nash, Sally K.

    2007-01-01

    While technical training and advanced degree's assure proficiency at specific tasks within engineering disciplines, they fail to address the potential for communication breakdown and decision making errors familiar to multicultural environments where language barriers, intimidating personalities and interdisciplinary misconceptions exist. In an effort to minimize these pitfalls to effective panel review, NASA's lead safety engineers to the ISS Safety Review Panel (SRP), and Payload Safety Review Panel (PSRP) initiated training with their engineers, in conjunction with the panel chairs, and began a Panel Resource Management (PRM) program. The intent of this program focuses on the ability to reduce the barriers inhibiting effective participation from all panel attendees by bolstering participants confidence levels through increased communication skills, situational awareness, debriefing, and a better technical understanding of requirements and systems.

  2. 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

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

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  4. 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

  5. Main findings, conclusions and recommendations of the Ignalina Safety Panel

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1999-01-01

    Ignalina Safety Panel was created to define, monitor and supervise the scope and production of the Ignalina Safety Analysis Report (SAR) and its Review (RSR); to review results of in-depth safety assessment addressing important contradictory statements; to give Lithuanian Government recommendations in view of further licensing process. In this paper General and Specific Recommendations provided by the Panel are presented

  6. Differing professional opinions: 1987 special review panel

    International Nuclear Information System (INIS)

    1988-01-01

    In November 1987, the five-member Differing Professional Opinions Special Review Panel established by the Executive Director for Operations of the US Nuclear Regulatory Commission to review agency policies and procedures for handling differing professional opinions (DPOs) presented its findings and recommendations in NUREG-1290. The issuance of that report completed the first task of the panel's charter. In accordance with Manual chapter 4125, Section L, and the charter of the Special Review Panel, the panel's second task was to ''...review...the DPOs submitted subsequent to the previous Panel's review, in order to identify any employee whose DPO made a significant contribution to the Agency or to the public safety but who has not yet been recognized for such contribution.'' This Addendum provides the findings of that review

  7. Insights from the panel review process

    International Nuclear Information System (INIS)

    Searborn, B.

    1998-01-01

    The environmental review process for nuclear waste management and disposal was unusual in that the Panel was asked to examine a concept rather than a specific project at a specific site. The Panel was charged with commenting on the safety and acceptability of the AECL concept, examining criteria for determining the safety and acceptability of any concept for managing nuclear fuel waste, and examining future steps which should be taken. In short, it was asked to provide policy advice to governments. The Panel concluded that safety is a key part, but only one part, of acceptability, and that safety must be viewed from both a technical and a social perspective. It judged that safety of the AECL concept had been adequately demonstrated from a technical perspective, but not from a social perspective. It also concluded that the AECL concept does not have the required level of public acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. The paper examines in some detail the various aspects of the public concerns surrounding the nuclear cycle in general, and the safety of the proposals put forward by AECL for nuclear fuel waste management in particular. It notes the differences between those who look at safety from a technical perspective, and those who look at safety from a social perspective. And it lists the concerns related to acceptability in addition to the key factor of safety. After outlining the Panel's recommendations to governments on future steps to be taken, the paper discusses the extent to which the recommendations respond to the public's concerns. It stresses the importance of Aboriginal participation; of the creation of a new agency to deal with the full range of activities, technical and social, related to long-term management; of the public and decision-makers having more than one viable option to choose from; and of the essentiality of an inter-active process of public participation at all stages of decision-making. Finally

  8. 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

  9. 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...

  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. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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

  20. 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...

  1. 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...

  2. 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...

  3. Conduct and results of the Interagency Nuclear Safety Review Panel's evaluation of the Ulysses space mission

    International Nuclear Information System (INIS)

    Sholtis, J.A. Jr.; Gray, L.B.; Huff, D.A.; Klug, N.P.; Winchester, R.O.

    1991-01-01

    The recent 6 October 1990 launch and deployment of the nuclear-powered Ulysses spacecraft from the Space Shuttle Discovery culminated an extensive safety review and evaluation effort by the Interagency Nuclear Safety Review Panel (INSRP). After more than a year of detailed independent review, study, and analysis, the INSRP prepared a Safety Evaluation Report (SER) on the Ulysses mission, in accordance with Presidential Directive-National Security Council memorandum 25. The SER, which included a review of the Ulysses Final Safety Analysis Report (FSAR) and an independent characterization of the mission risks, was used by the National Aeronautics and Space Administration (NASA) in its decision to request launch approval as well as by the Executive Office of the President in arriving at a launch decision based on risk-benefit considerations. This paper provides an overview of the Ulysses mission and the conduct as well as the results of the INSRP evaluation. While the mission risk determined by the INSRP in the SER was higher than that characterized by the Ulysses project in the FSAR, both reports indicated that the radiological risks were relatively small. In the final analysis, the SER proved to be supportive of a positive launch decision. The INSRP evaluation process has demonstrated its effectiveness numerous times since the 1960s. In every case, it has provided the essential ingredients and perspective to permit an informed launch decision at the highest level of our Government

  4. Differing professional views or opinions: 1994 Special Review Panel

    International Nuclear Information System (INIS)

    1996-09-01

    In July 1994, the Executive Director for Operations of the US Nuclear Regulatory Commission (NRC) appointed a Special Review Panel to assess the Differing Professional View or Opinion (DPV/DPO) process, including its effectiveness, how well it is understood by employees, and the organizational climate for having such views aired and properly decided. An additional area within this review was to address the effectiveness of the DPO procedures as they pertain to public access and confidentiality. Further, the Panel was charged with the review of the submittals completed since the last review to identify employees who made significant contributions to the agency or to the public health and safety but had not been adequately recognized for this contribution. The report presents the Special Review Panel's evaluation of the NRC's current process for dealing with Differing Professional Views or Opinions. Provided in this report are the results of an employee opinion survey on the process; highlights and suggestions from interviews with individuals who had submitted a Differing Professional View or Opinion, as well as with agency managers directly involved with the Differing Professional Views or Opinions process; and the Special Review Panel's recommendations for improving the DPV/DPO process

  5. 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...

  6. The Atomic Safety and Licensing Board Panel

    International Nuclear Information System (INIS)

    1998-01-01

    Through the Atomic Energy Act, Congress made is possible for the public to get a full and fair hearing on civilian nuclear matters. Individuals who are directly affected by any licensing action involving a facility producing or utilizing nuclear materials may participate in a formal hearing, on the record, before independent judges on the Atomic Safety and Licensing Board Panel (ASLBP or Panel). Frequently, in deciding whether a license, permit, amendment, or extension should be granted to a particular applicant, the Panel members must be more than mere umpires. If appropriate, they are authorized to go beyond the issues the parties place before them in order to identify, explore, and resolve significant questions involving threats to the public health and safety that come to a board's attention during the proceedings. This brochure explains the purpose of the panel. Also addressed are: type of hearing handled; method of public participation; formality of hearings; high-level waste; other panel responsibilities and litigation technology

  7. Establishing research priorities for patient safety in emergency medicine: a multidisciplinary consensus panel.

    Science.gov (United States)

    Plint, Amy C; Stang, Antonia S; Calder, Lisa A

    2015-01-01

    Patient safety in the context of emergency medicine is a relatively new field of study. To date, no broad research agenda for patient safety in emergency medicine has been established. The objective of this study was to establish patient safety-related research priorities for emergency medicine. These priorities would provide a foundation for high-quality research, important direction to both researchers and health-care funders, and an essential step in improving health-care safety and patient outcomes in the high-risk emergency department (ED) setting. A four-phase consensus procedure with a multidisciplinary expert panel was organized to identify, assess, and agree on research priorities for patient safety in emergency medicine. The 19-member panel consisted of clinicians, administrators, and researchers from adult and pediatric emergency medicine, patient safety, pharmacy, and mental health; as well as representatives from patient safety organizations. In phase 1, we developed an initial list of potential research priorities by electronically surveying a purposeful and convenience sample of patient safety experts, ED clinicians, administrators, and researchers from across North America using contact lists from multiple organizations. We used simple content analysis to remove duplication and categorize the research priorities identified by survey respondents. Our expert panel reached consensus on a final list of research priorities through an in-person meeting (phase 3) and two rounds of a modified Delphi process (phases 2 and 4). After phases 1 and 2, 66 unique research priorities were identified for expert panel review. At the end of phase 4, consensus was reached for 15 research priorities. These priorities represent four themes: (1) methods to identify patient safety issues (five priorities), (2) understanding human and environmental factors related to patient safety (four priorities), (3) the patient perspective (one priority), and (4) interventions for

  8. Atomic Safety and Licensing Board Panel annual report

    International Nuclear Information System (INIS)

    1991-09-01

    In Fiscal Year 1990, The Atomic Safety and Licensing Board Panel (Panel) handled 40 proceedings involving the construction, operation, and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights, and analyzes how the judges and licensing boards of the Panel addressed the wide-ranging issues raised in these proceedings during the year

  9. Involving patients in patient safety programmes: A scoping review and consensus procedure by the LINNEAUS collaboration on patient safety in primary care.

    Science.gov (United States)

    Trier, Hans; Valderas, Jose M; Wensing, Michel; Martin, Helle Max; Egebart, Jonas

    2015-09-01

    Patient involvement has only recently received attention as a potentially useful approach to patient safety in primary care. To summarize work conducted on a scoping review of interventions focussing on patient involvement for patient safety; to develop consensus-based recommendations in this area. Scoping review of the literature 2006-2011 about methods and effects of involving patients in patient safety in primary care identified evidence for previous experiences of patient involvement in patient safety. This information was fed back to an expert panel for the development of recommendations for healthcare professionals and policy makers. The scoping review identified only weak evidence in support of the effectiveness of patient involvement. Identified barriers included a number of patient factors but also the healthcare workers' attitudes, abilities and lack of training. The expert panel recommended the integration of patient safety in the educational curricula for healthcare professionals, and expected a commitment from professionals to act as first movers by inviting and encouraging the patients to take an active role. The panel proposed a checklist to be used by primary care clinicians at the point of care for promoting patient involvement. There is only weak evidence on the effectiveness of patient involvement in patient safety. The recommendations of the panel can inform future policy and practice on patient involvement in safety in primary care.

  10. 75 FR 82376 - North American Free Trade Agreement, Article 1904 NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2010-12-30

    ... Mexico and the People's Republic of China. This determination was published in the Federal Register (75... Panel Review. SUMMARY: On December 22, 2010, the Government of Mexico filed a First Request for Panel... Government of Mexico established Rules of Procedure for Article 1904 Binational Panel Reviews (``Rules...

  11. 7 CFR 205.509 - Peer review panel.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Peer review panel. 205.509 Section 205.509 Agriculture... PROVISIONS NATIONAL ORGANIC PROGRAM Accreditation of Certifying Agents § 205.509 Peer review panel. The Administrator shall establish a peer review panel pursuant to the Federal Advisory Committee Act (FACA) (5 U.S.C...

  12. Advanced conversion technology review panel report

    International Nuclear Information System (INIS)

    Frazier, T.A.

    1998-01-01

    The Department of Energy (DOE), the National Aeronautics and Space Administration (NASA) and the Jet Propulsion Laboratory (JPL) established a DOE lead management team and an Advanced Conversion Technology Review Panel. The panel was tasked with providing the management team with an assessment and ranking of the three advanced conversion technologies. The three advanced conversion technologies were alkali metal thermal to electric converter (AMTEC), Stirling engine converter (SEC), and thermophotovoltaic (TPV). To rate and rank these three technologies, five criteria were developed: (1) Performance, (2) Development and Cost/Production and Cost/Schedule Risk, (3) Spacecraft Interface and Operations, (4) Ability to Scale Conversion, and (5) Safety. Discussed are the relative importance of each of these criteria and the rankings of the three advanced conversion technologies. It was the conclusion of the panel that the technology decision should be based on the risk that DOE and NASA are willing to accept. SEC is the most mature technology and would provide the lowest risk option. However, if more risk is acceptable, AMTEC not only provides benefits in the spacecraft interface but is also predicted to outperform the SEC. It was proposed that if AMTEC were selected, funding should be provided at a reasonable level to support back-up technology to be developed in a parallel fashion until AMTEC has proven its capability. The panel report and conclusion were provided to DOE in February 1997

  13. 77 FR 61756 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-10-11

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grant, PAR 10-288, initial review...

  14. ALDS 1978 panel review. [PNL

    Energy Technology Data Exchange (ETDEWEB)

    Hall, D.L. (ed.)

    1979-08-01

    Pacific Northwest Laboratory (PNL) is examining the analysis of large data sets (ALDS). After one year's work, a panel was convened to evaluate the project. This document is the permanent record of that panel review. It consists of edited transcripts of presentations made to the panel by the PNL staff, a summary of the responses of the panel to these presentations, and PNL's plans for the development of the ALDS project. The representations of the PNL staff described various aspects of the project and/or the philosophy surrounding the project. Supporting materials appear in appendixes. 20 figures, 4 tables. (RWR)

  15. Atomic Safety and Licensing Board Panel annual report, Fiscal year 1992

    International Nuclear Information System (INIS)

    1993-09-01

    In Fiscal Year 1992, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 38 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license from the Nuclear Regulatory Commission. This reports sets out the Panel's caseload during the year and summarizes, highlights, and analyzes how the wide-ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

  16. Seismic hazard analysis. Review panel, ground motion panel, and feedback results

    International Nuclear Information System (INIS)

    Bernreuter, D.L.

    1981-10-01

    The Site Specific Spectra Project (SSSP) was a multi-year study funded by the U.S. Nuclear Regulatory Commission to provide estimates of the seismic hazards at a number of nuclear power plant sites in the Eastern U.S. A key element of our approach was the Peer Review Panel, which we formed in order to ensure that our use of expert opinion was reasonable. We discuss the Peer Review Panel results and provide the complete text of each member's report. In order to improve the ground motion model, an Eastern U.S. Ground Motion Model Panel was formed. In Section 4 we tabulate the responses from the panel members to our feedback questionnaire and discuss the implications of changes introduced by them. We conclude that the net difference in seismic hazard values from those presented in Volume 4 is small and does not warrant a reanalysis. (author)

  17. 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...

  18. 76 FR 78263 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-12-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grants, Program Announcement PAR 10...

  19. Final report of the Cosmetic Ingredient Review Expert Panel amended safety assessment of Calendula officinalis-derived cosmetic ingredients.

    Science.gov (United States)

    Andersen, F Alan; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W

    2010-01-01

    Calendula officinalis extract, C officinalis flower, C officinalis flower extract, C officinalis flower oil, and C officinalis seed oil are cosmetic ingredients derived from C officinalis. These ingredients may contain minerals, carbohydrates, lipids, phenolic acids, flavonoids, tannins, coumarins, sterols and steroids, monoterpenes, sesquiterpenes, triterpenes, tocopherols, quinones, amino acids, and resins. These ingredients were not significantly toxic in single-dose oral studies using animals. The absence of reproductive/developmental toxicity was inferred from repeat-dose studies of coriander oil, with a similar composition. Overall, these ingredients were not genotoxic. They also were not irritating, sensitizing, or photosensitizing in animal or clinical tests but may be mild ocular irritants. The Cosmetic Ingredient Review (CIR) Expert Panel concluded that these ingredients are safe for use in cosmetics in the practices of use and concentration given in this amended safety assessment.

  20. 78 FR 60879 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns National Center for Construction Safety and Health Research and Translation (U60...

  1. 78 FR 60877 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grants (T03), PAR-10-288, initial...

  2. 78 FR 60875 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Occupational Safety and Health Training Project Grants (T03), PAR-10-288, initial...

  3. 77 FR 5026 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-02-01

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting... SEP: Occupational Safety and Health Education and Research Centers, PAR 10-217. Contact Person For...

  4. Differing professional opinions: 1987 Special Review Panel

    International Nuclear Information System (INIS)

    1987-11-01

    In mid-1987, the Executive Director for Operations of the US Nuclear Regulatory Commission appointed a Special Review Panel to review the existing NRC policy for expressing differing professional views and to recommend possible improvements to the policy, if warranted. Through its own efforts and those of three subpanels and three consultants, the Panel developed recommendations for changes and improvements in five major areas. This report presents those recommendations, along with a detailed explanation of the Panel's findings, copies of the reports of the subpanels and consultants, and the results of a survey of NRC non-clerical employees on the issue

  5. Human factors evaluation of man-machine interface for periodic safety review of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang; Hwang, In Koo; Lee, Hyun Cheol; Jang, Tong Il; Ku, Jin Young; Kim, Soo Jin

    2004-12-01

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Nuclear Power Plants(NPPs). As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

  6. Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (``the Panel``) handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel`s caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel`s judges and licensing boards.

  7. 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...

  8. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang

    2006-01-01

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

  9. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

    2006-01-15

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area.

  10. 34 CFR 350.52 - What is the composition of a peer review panel?

    Science.gov (United States)

    2010-07-01

    ... 34 Education 2 2010-07-01 2010-07-01 false What is the composition of a peer review panel? 350.52... composition of a peer review panel? (a) The Secretary selects as members of a peer review panel scientists and... information, or conferences, must be reviewed by a peer review panel that consists of a majority of non...

  11. Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

    International Nuclear Information System (INIS)

    1995-08-01

    In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel's caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

  12. 78 FR 77495 - Hearings of the Review Panel on Prison Rape

    Science.gov (United States)

    2013-12-23

    ... Review Panel on Prison Rape AGENCY: Office of Justice Programs, Justice. ACTION: Notice of Hearing. SUMMARY: The Office of Justice Programs (OJP) announces that the Review Panel on Prison Rape (Panel) will... and lowest incidence of rape, respectively, based on anonymous surveys by the BJS of inmates and youth...

  13. 76 FR 20711 - Hearings of the Review Panel on Prison Rape

    Science.gov (United States)

    2011-04-13

    ... Review Panel on Prison Rape AGENCY: Office of Justice Programs, Justice. ACTION: Notice of hearing. SUMMARY: The Office of Justice Programs (OJP) announces that the Review Panel on Prison Rape (Panel) will... characteristics of prisons with the highest and lowest incidence of rape, respectively, based on an anonymous...

  14. 75 FR 27000 - Hearings of the Review Panel on Prison Rape

    Science.gov (United States)

    2010-05-13

    ... Review Panel on Prison Rape AGENCY: Office of Justice Programs, Justice. ACTION: Notice of hearing. SUMMARY: The Office of Justice Programs (OJP) announces that the Review Panel on Prison Rape (Panel) will... characteristics of juvenile facilities with the highest and lowest incidence of rape, respectively, based on an...

  15. 76 FR 56481 - Hearings of the Review Panel on Prison Rape

    Science.gov (United States)

    2011-09-13

    ... Review Panel on Prison Rape AGENCY: Office of Justice Programs, Justice. ACTION: Notice of hearing. SUMMARY: The Office of Justice Programs (OJP) announces that the Review Panel on Prison Rape (Panel) will... Law School; David L. Moss Criminal Justice Center (Tulsa, OK)--facility with a low prevalence of...

  16. Global status of recycling waste solar panels: A review.

    Science.gov (United States)

    Xu, Yan; Li, Jinhui; Tan, Quanyin; Peters, Anesia Lauren; Yang, Congren

    2018-05-01

    With the enormous growth in the development and utilization of solar-energy resources, the proliferation of waste solar panels has become problematic. While current research into solar panels has focused on how to improve the efficiency of the production capacity, the dismantling and recycling of end-of-life (EOL) panels are seldom considered, as can be seen, for instance, in the lack of dedicated solar-panel recycling plants. EOL solar-panel recycling can effectively save natural resources and reduce the cost of production. To address the environmental conservation and resource recycling issues posed by the huge amount of waste solar panels regarding environmental conservation and resource recycling, the status of the management and recycling technologies for waste solar panels are systemically reviewed and discussed in this article. This review can provide a quantitative basis to support the recycling of PV panels, and suggests future directions for public policy makers. At present, from the technical aspect, the research on solar panel recovery is facing many problems, and we need to further develop an economically feasible and non-toxic technology. The research on solar photovoltaic panels' management at the end of life is just beginning in many countries, and there is a need for further improvement and expansion of producer responsibility. Copyright © 2018 Elsevier Ltd. All rights reserved.

  17. Atomic safety and licensing board panel: Annual report, Fiscal Year 1988

    International Nuclear Information System (INIS)

    1989-03-01

    This is the fiscal year 1988 annual report of the Atomic Safety and Licensing Board Panel. In response to further reduction in is authorized staffing level and with an eye toward the proposed full- text, electronic docket of the expected High-Level Waste Repository proceedings, the Panel stepped up efforts during fiscal year 1988 to extend the scope, depth and availability of its Computer Assistance Project (CAP) through INQUIRE. INQUIRE, and the Panel's ability to use the system to expeditiously manage and search the massive records that characterize our most complex cases, has generated great interest among legal practitioners and adjudicatory bodies throughout the United States and Canada

  18. Safety Assessment of Polyether Lanolins as Used in Cosmetics.

    Science.gov (United States)

    Becker, Lillian C; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan; Heldreth, Bart

    The Cosmetic Ingredient Review (CIR) Expert Panel (Panel) assessed the safety of 39 polyether lanolin ingredients as used in cosmetics. These ingredients function mostly as hair conditioning agents, skin conditioning agent-emollients, and surfactant-emulsifying agents. The Panel reviewed available animal and clinical data, from previous CIR safety assessments of related ingredients and components. The similar structure, properties, functions, and uses of these ingredients enabled grouping them and using the available toxicological data to assess the safety of the entire group. The Panel concluded that these polyether lanolin ingredients are safe in the practices of use and concentration as given in this safety assessment.

  19. Integrated thermal treatment systems study. Internal review panel report

    International Nuclear Information System (INIS)

    Cudahy, J.; Escarda, T.; Gimpel, R.

    1995-04-01

    The U.S. Department of Energy (DOE) Office of Technology Development (OTD) commissioned two studies to evaluate nineteen thermal treatment technologies for treatment of DOE mixed low-level waste. These studies were called the Integrated Thermal Treatment System (ITTS) Phase I and Phase II. With the help of the DOE Office of Environmental Management (EM) Mixed Waste Focus Group, OTD formed an ITTS Internal Review Panel to review and comment on the ITTS studies. This Panel was composed of scientists and engineers from throughout the DOE complex, the U.S. Environmental Protection Agency, the California EPA, and private experts. The Panel met from November 15-18, 1994 to review the ITTS studies and to make recommendations on the most promising thermal treatment systems for DOE mixed low-level wastes and on research and development necessary to prove the performance of the technologies. This report describes the findings and presents the recommendations of the Panel

  20. The Integrated Safety Management System Verification Enhancement Review of the Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    BRIGGS, C.R.

    2000-01-01

    The primary purpose of the verification enhancement review was for the DOE Richland Operations Office (RL) to verify contractor readiness for the independent DOE Integrated Safety Management System Verification (ISMSV) on the Plutonium Finishing Plant (PFP). Secondary objectives included: (1) to reinforce the engagement of management and to gauge management commitment and accountability; (2) to evaluate the ''value added'' benefit of direct public involvement; (3) to evaluate the ''value added'' benefit of direct worker involvement; (4) to evaluate the ''value added'' benefit of the panel-to-panel review approach; and, (5) to evaluate the utility of the review's methodology/adaptability to periodic assessments of ISM status. The review was conducted on December 6-8, 1999, and involved the conduct of two-hour interviews with five separate panels of individuals with various management and operations responsibilities related to PFP. A semi-structured interview process was employed by a team of five ''reviewers'' who directed open-ended questions to the panels which focused on: (1) evidence of management commitment, accountability, and involvement; and, (2) consideration and demonstration of stakeholder (including worker) information and involvement opportunities. The purpose of a panel-to-panel dialogue approach was to better spotlight: (1) areas of mutual reinforcement and alignment that could serve as good examples of the management commitment and accountability aspects of ISMS implementation, and, (2) areas of potential discrepancy that could provide opportunities for improvement. In summary, the Review Team found major strengths to include: (1) the use of multi-disciplinary project work teams to plan and do work; (2) the availability and broad usage of multiple tools to help with planning and integrating work; (3) senior management presence and accessibility; (4) the institutionalization of worker involvement; (5) encouragement of self-reporting and self

  1. Safety assessment of Vitis vinifera (grape)-derived ingredients as used in cosmetics.

    Science.gov (United States)

    Fiume, Monice M; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan

    2014-01-01

    The Cosmetic Ingredient Review Expert Panel (Panel) assessed the safety of 24 Vitis vinifera (grape)-derived ingredients and found them safe in the present practices of use and concentration in cosmetics. These ingredients function in cosmetics mostly as skin-conditioning agents, but some function as antioxidants, flavoring agents, and/or colorants. The Panel reviewed the available animal and clinical data to determine the safety of these ingredients. Additionally, some constituents of grapes have been assessed previously for safety as cosmetic ingredients by the Panel, and others are compounds that have been discussed in previous Panel safety assessments. © The Author(s) 2014.

  2. Pantex Falling Man - Independent Review Panel Report.

    Energy Technology Data Exchange (ETDEWEB)

    Brannon, Nathan Gregory; L. Bertolini, N. Brannon, J. Olsen, B. Price, M. Steinzig, R. Wardle, & M. Winfield

    2014-11-01

    Consolidated Nuclear Security (CNS) Pantex took the initiative to organize a Review Panel of subject matter experts to independently assess the adequacy of the Pantex Tripping Man Analysis methodology. The purpose of this report is to capture the details of the assessment including the scope, approach, results, and detailed Appendices. Along with the assessment of the analysis methodology, the panel evaluated the adequacy with which the methodology was applied as well as congruence with Department of Energy (DOE) standards 3009 and 3016. The approach included the review of relevant documentation, interactive discussion with Pantex staff, and the iterative process of evaluating critical lines of inquiry.

  3. 75 FR 81315 - Earth Sciences Proposal Review Panel; Notice of Meeting

    Science.gov (United States)

    2010-12-27

    ... NATIONAL SCIENCE FOUNDATION Earth Sciences Proposal Review Panel; Notice of Meeting In accordance... announces the following meeting. Name: Proposal Review Panel in Earth Sciences (1569). Date and Time... Kelz, Program Director, Instrumentation & Facilities Program, Division of Earth Sciences, Room 785...

  4. 77 FR 72325 - North American Free-Trade Agreement, Article 1904 NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2012-12-05

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free-Trade Agreement... Free Trade Agreement. Panel Review was requested of the Final resolution of the Countervailing Duty... 19 of the North American Free-Trade Agreement (``Agreement'') established a mechanism to replace...

  5. 75 FR 13494 - North American Free-Trade Agreement, Article 1904; NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2010-03-22

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free-Trade Agreement... Secretariat pursuant to Article 1904 of the North American Free Trade Agreement. Panel Review was requested of... Section, International Trade Administration, Department of Commerce. ACTION: Notice of First Request for...

  6. 76 FR 10005 - North American Free Trade Agreement, Article 1904 NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2011-02-23

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement... Secretariat pursuant to Article 1904 of the North American Free Trade Agreement. Panel Review was requested of...-5438. SUPPLEMENTARY INFORMATION: Chapter 19 of the North American Free Trade Agreement (``Agreement...

  7. 77 FR 66798 - North American Free-Trade Agreement, Article 1904; NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2012-11-07

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free-Trade Agreement... Trade Agreement. Panel Review was requested of the Final Results of the Antidumping Administrative... INFORMATION: Chapter 19 of the North American Free-Trade Agreement (``Agreement'') established a mechanism to...

  8. 76 FR 72677 - North American Free-Trade Agreement, Article 1904 NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2011-11-25

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free-Trade Agreement... Trade Agreement. Panel review was requested of the final determination of the effective examination and... 20230, (202) 482-5438. SUPPLEMENTARY INFORMATION: Chapter 19 of the North American Free-Trade Agreement...

  9. 78 FR 5778 - North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2013-01-28

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... the Panel Order and Rule 80 of the Article 1904 Panel Rules, the Panel Review was completed and the...

  10. 75 FR 15460 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-03-29

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation announces the following meeting. Name: Proposal Review Panel for Physics, LIGO Site Visit in Louisiana (1208...

  11. 77 FR 74174 - North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2012-12-13

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section.... Therefore, on the basis of the Panel Order and Rule 80 of the Article 1904 Panel Rules, the Panel Review was...

  12. 76 FR 16728 - North American Free Trade Agreement, Article 1904; NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2011-03-25

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement... American Free Trade Agreement. Panel Review was requested of the U.S. Department of Commerce's final... INFORMATION: Chapter 19 of the North American Free Trade Agreement (``Agreement'') established a mechanism to...

  13. 76 FR 42115 - North American Free-Trade Agreement, Article 1904 NAFTA Panel Reviews; Request for Panel Review

    Science.gov (United States)

    2011-07-18

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free-Trade Agreement... Free Trade Agreement. Panel Review was requested of the Final Results of the 2008- 2009 and 2009-2010.... SUPPLEMENTARY INFORMATION: Chapter 19 of the North American Free Trade Agreement (``Agreement'') established a...

  14. Patient safety in out-of-hours primary care: a review of patient records

    Directory of Open Access Journals (Sweden)

    Wensing Michel

    2010-12-01

    Full Text Available Abstract Background Most patients receive healthcare in primary care settings, but relatively little is known about patient safety. Out-of-hours contacts are of particular importance to patient safety. Our aim was to examine the incidence, types, causes, and consequences of patient safety incidents at general practice cooperatives for out-of-hours primary care and to examine which factors were associated with the occurrence of patient safety incidents. Methods A retrospective study of 1,145 medical records concerning patient contacts with four general practice cooperatives. Reviewers identified records with evidence of a potential patient safety incident; a physician panel determined whether a patient safety incident had indeed occurred. In addition, the panel determined the type, causes, and consequences of the incidents. Factors associated with incidents were examined in a random coefficient logistic regression analysis. Results In 1,145 patient records, 27 patient safety incidents were identified, an incident rate of 2.4% (95% CI: 1.5% to 3.2%. The most frequent incident type was treatment (56%. All incidents had at least partly been caused by failures in clinical reasoning. The majority of incidents did not result in patient harm (70%. Eight incidents had consequences for the patient, such as additional interventions or hospitalisation. The panel assessed that most incidents were unlikely to result in patient harm in the long term (89%. Logistic regression analysis showed that age was significantly related to incident occurrence: the likelihood of an incident increased with 1.03 for each year increase in age (95% CI: 1.01 to 1.04. Conclusion Patient safety incidents occur in out-of-hours primary care, but most do not result in harm to patients. As clinical reasoning played an important part in these incidents, a better understanding of clinical reasoning and guideline adherence at GP cooperatives could contribute to patient safety.

  15. EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2015. Scientific Opinion on the safety of caffeine

    DEFF Research Database (Denmark)

    Tetens, Inge

    2015-01-01

    Following a request from the European Commission, the EFSA Panel on Dietetic Products, Nutrition and Allergies was asked to deliver a scientific opinion on the safety of caffeine, providing advice on caffeine intakes, from all dietary sources that do not give rise to concerns about adverse health...... not give rise to safety concerns. The same amount does not give rise to safety concerns when consumed .../L of caffeine, taurine and d-glucurono-γ-lactone, respectively), as well as alcohol at doses up to about 0.65 g/kg bw, would not affect the safety of single doses of caffeine up to 200 mg. Habitual caffeine consumption up to 400 mg per day does not give rise to safety concerns for non-pregnant adults. Habitual...

  16. Selling Albertans short : Alberta's royalty review panel fails the public interest

    International Nuclear Information System (INIS)

    Gibson, D.

    2007-10-01

    This document commented on the release of Alberta's 2007 Royalty Review Panel regarding the province's royalty system for petroleum and oil sands development. It argued that the report does not fulfill the spirit of Alberta's royalty system, which is to expect nothing less than 100 per cent of the rent collection. This document provided an analysis of the set of recommendations made by the panel. It began with a general discussion of the problems in which the royalties review was structured and flaws in the base assumptions made by the panel. It also provided an analysis of the specific recommendations within the panel's report. Last, the report proposed a set of recommendations on how a royalties reform should proceed. The authors found specific recommendations Alberta's 2007 Royalty Review Panel report to be problematic. These included the 1 per cent royalty holiday on tar sands oil; higher net royalty rate; windfall profits tax; coal bed methane and cuts in royalties for low producing wells; and value added incentives. It was concluded that the panel's report was a compromise between the public interest and those of the oil and gas sector and that the panel's goal of ensuring that Alberta remained one of the lowest tax and royalty jurisdictions in the world was fundamentally flawed. 32 refs., 4 figs

  17. 78 FR 17639 - North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2013-03-22

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... Order and Rule 80 of the Article 1904 Panel Rules, the Panel Review was completed and the panelists were...

  18. 78 FR 10600 - North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2013-02-14

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... Order and Rule 80 of the Article 1904 Panel Rules, the Panel Review was completed and the panelists were...

  19. 78 FR 11627 - North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2013-02-19

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... Order and Rule 80 of the Article 1904 Panel Rules, the Panel Review was completed and the panelists were...

  20. 77 FR 72325 - North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2012-12-05

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... Order and Rule 80 of the Article 1904 Panel Rules, the Panel Review was completed and the panelists were...

  1. EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2014 . Scientific Opinion on the safety of vitamin D - enriched UV - treated baker‘s yeast

    DEFF Research Database (Denmark)

    Tetens, Inge; Poulsen, Morten

    2014-01-01

    , fine pastry and food supplements. The Panel considers that the provided compositional data, the specification, the data from batch testing, data on the stability on the production process are sufficient and do not give rise to safety concerns. The Panel concludes that the data provided are sufficient...... and do not give rise to safety concerns.The applicant intends to use the NFI as an alternative source of vitamin D for food supplements and for fortification of yeast-leavened bread, rolls and fine pastry at maximum concentrations of 5 μg vitamin D2 per 100 g of these foods. The applicant provided....../100 g bread, rolls and fine pastry, it is highly unlikely that Tolerable Upper Intake Levels as established by EFSA (EFSA NDA Panel, 2012) are exceeded. The Panel considers that UV-treated baker’s yeast exhibiting an enhanced content of vitamin D2 is safe under the intended conditions of use....

  2. 76 FR 32957 - Hydrographic Services Review Panel

    Science.gov (United States)

    2011-06-07

    .... SUMMARY: This notice responds to the Hydrographic Service Improvements Act Amendments of 2002, Public Law...), to solicit nominations for membership on the Hydrographic Services Review Panel (HSRP). The HSRP, a...; fisheries management; coastal and marine spatial planning; geodesy; water levels; and other science-related...

  3. 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

  4. Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

    Science.gov (United States)

    Duarte, Alberto

    2007-01-01

    Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

  5. Safety Assessment of Amino Acid Alkyl Amides as Used in Cosmetics.

    Science.gov (United States)

    Burnett, Christina L; Heldreth, Bart; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan

    The Cosmetic Ingredient Review Expert Panel (Panel) reviewed the product use, formulation, and safety data of 115 amino acid alkyl amides, which function as skin and hair conditioning agents and as surfactants-cleansing agents in personal care products. Safety test data on dermal irritation and sensitization for the ingredients with the highest use concentrations, lauroyl lysine and sodium lauroyl glutamate, were reviewed and determined to adequately support the safe use of the ingredients in this report. The Panel concluded that amino acid alkyl amides are safe in the present practices of use and concentration in cosmetics, when formulated to be nonirritating.

  6. 76 FR 60934 - Proposal Review Panel for Human Resource Development; Notice of Meeting

    Science.gov (United States)

    2011-09-30

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Human Resource Development; Notice of...; Proposal Review Panel Human Resource Development ( 1199). Date/Time: November 1, 2011; 5 p.m. to 10 p.m...: Part-Open. Contact Person: Kelly Mack, Division of Human Resource Development, Room 815, National...

  7. Citizen Review Panels for Child Protective Services: A National Profile

    Science.gov (United States)

    Jones, Blake L.; Royse, David

    2008-01-01

    Citizen Review Panels (CRPs) for Child Protective Services are groups of citizen-volunteers throughout the United States who are federally mandated to evaluate local and state child protection systems. This study presents a profile of 332 CRP members in 20 states with regards to their demographic information, length of time on the panel, and …

  8. The Cosmetic Ingredient Review Program-Expert Safety Assessments of Cosmetic Ingredients in an Open Forum.

    Science.gov (United States)

    Boyer, Ivan J; Bergfeld, Wilma F; Heldreth, Bart; Fiume, Monice M; Gill, Lillian J

    The Cosmetic Ingredient Review (CIR) is a nonprofit program to assess the safety of ingredients in personal care products in an open, unbiased, and expert manner. Cosmetic Ingredient Review was established in 1976 by the Personal Care Products Council (PCPC), with the support of the US Food and Drug Administration (USFDA) and the Consumer Federation of America (CFA). Cosmetic Ingredient Review remains the only scientific program in the world committed to the systematic, independent review of cosmetic ingredient safety in a public forum. Cosmetic Ingredient Review operates in accordance with procedures modeled after the USFDA process for reviewing over-the-counter drugs. Nine voting panel members are distinguished, such as medical professionals, scientists, and professors. Three nonvoting liaisons are designated by the USFDA, CFA, and PCPC to represent government, consumer, and industry, respectively. The annual rate of completing safety assessments accelerated from about 100 to more than 400 ingredients by implementing grouping and read-across strategies and other approaches. As of March 2017, CIR had reviewed 4,740 individual cosmetic ingredients, including 4,611 determined to be safe as used or safe with qualifications, 12 determined to be unsafe, and 117 ingredients for which the information is insufficient to determine safety. Examples of especially challenging safety assessments and issues are presented here, including botanicals. Cosmetic Ingredient Review continues to strengthen its program with the ongoing cooperation of the USFDA, CFA, the cosmetics industry, and everyone else interested in contributing to the process.

  9. 76 FR 60933 - Proposal Review Panel for Human Resource Development; Notice of Meeting

    Science.gov (United States)

    2011-09-30

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Human Resource Development; Notice of..., Proposal Review Panel Human Resource Development ( 1199). Date/Time: October 17, 2011; 5 p.m. to 10 p.m... Meeting: Part-Open. Contact Person: Kelly Mack, Division of Human Resource Development, Room 815, National...

  10. 78 FR 57838 - North American Free Trade Agreement Binational Panel Reviews

    Science.gov (United States)

    2013-09-20

    ... DEPARTMENT OF COMMERCE International Trade Administration [Secretariat File No. USA-MEX-2011- 1904-02] North American Free Trade Agreement Binational Panel Reviews AGENCY: NAFTA Secretariat, United... Decision and Order of the North American Free Trade Agreement (NAFTA) Binational Panel dated August 6, 2013...

  11. 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)

  12. 76 FR 11415 - Federal Motor Vehicle Safety Standards; Power-Operated Window, Partition, and Roof Panel Systems

    Science.gov (United States)

    2011-03-02

    ... [Docket No. NHTSA-2011-0027] RIN 2127-AK52 Federal Motor Vehicle Safety Standards; Power-Operated Window, Partition, and Roof Panel Systems AGENCY: National Highway Traffic Safety Administration (NHTSA), Department... automatic reversal systems (ARS) for power windows and to make a final decision. The agency has decided not...

  13. Atomic Safety and Licensing Board Panel annual report, fiscal year 1989

    International Nuclear Information System (INIS)

    Cotter, B.P. Jr.

    1990-07-01

    In Fiscal Year 1989, the Atomic Safety and Licensing Board Panel (ASLBP) handled 40 proceedings involving the construction, operation and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights and analyzes how the wide-ranging issues raised in these proceedings were addressed by the Judges and Licensing Boards of the ASLBP during the year. 5 figs., 3 tabs

  14. 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)

  15. 77 FR 65864 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2012-10-31

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... law of the country that made the determination. Under Article 1904 of the Agreement, which came into... Government of Mexico established Rules of Procedure for Article 1904 Binational Panel Reviews (``Rules...

  16. 77 FR 74174 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2012-12-13

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... duty law of the country that made the determination. Under Article 1904 of the Agreement, which came... Government of Mexico established Rules of Procedure for Article 1904 Binational Panel Reviews (``Rules...

  17. 76 FR 4633 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2011-01-26

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... duty law of the country that made the determination. Under Article 1904 of the Agreement, which came... Government of Mexico established Rules of Procedure for Article 1904 Binational Panel Reviews (``Rules...

  18. 76 FR 14917 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2011-03-18

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... that made the determination. Under Article 1904 of the Agreement, which came into force on January 1... established Rules of Procedure for Article 1904 Binational Panel Reviews (``Rules''). These Rules were...

  19. 76 FR 56404 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2011-09-13

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... law of the country that made the determination. Under Article 1904 of the Agreement, which came into... Government of Mexico established Rules of Procedure for Article 1904 Binational Panel Reviews (``Rules...

  20. 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.

  1. 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

  2. Safety assessment of decyl glucoside and other alkyl glucosides as used in cosmetics.

    Science.gov (United States)

    Fiume, Monice M; Heldreth, Bart; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan

    2013-01-01

    The Cosmetic Ingredient Review (CIR) Expert Panel assessed the safety of 19 alkyl glucosides as used in cosmetics and concluded that these ingredients are safe in the present practices of use and concentration when formulated to be nonirritating. Most of these ingredients function as surfactants in cosmetics, but some have additional functions as skin-conditioning agents, hair-conditioning agents, or emulsion stabilizers. The Panel reviewed the available animal and clinical data on these ingredients. Since glucoside hydrolases in human skin are likely to break down these ingredients to release their respective fatty acids and glucose, the Panel also reviewed CIR reports on the safety of fatty alcohols and were able to extrapolate data from those previous reports to support safety.

  3. 78 FR 51708 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2013-08-21

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... determination. Under Article 1904 of the Agreement, which came into force on January 1, 1994, the Government of... Procedure for Article 1904 Binational Panel Reviews (``Rules''). These Rules were published in the Federal...

  4. 75 FR 74686 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2010-12-01

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... determination. Under Article 1904 of the Agreement, which came into force on January 1, 1994, the Government of... Procedure for Article 1904 Binational Panel Reviews (``Rules''). These Rules were published in the Federal...

  5. 77 FR 29965 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2012-05-21

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... determination. Under Article 1904 of the Agreement, which came into force on January 1, 1994, the Government of... Procedure for Article 1904 Binational Panel Reviews (``Rules''). These Rules were published in the Federal...

  6. 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)

  7. 77 FR 18268 - Proposal Review Panel for Engineering Education and Centers; Notice of Meeting

    Science.gov (United States)

    2012-03-27

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Engineering Education and Centers; Notice of... Science Foundation announces the following meeting: Name: Proposal Review Panel for Engineering Education...--ERC Research Program 3:30 p.m.--7:30 p.m. Closed--ERC Education Program Thursday, March 29, 2012 8 a.m...

  8. 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)

  9. A review of sensing technologies for small and large-scale touch panels

    Science.gov (United States)

    Akhtar, Humza; Kemao, Qian; Kakarala, Ramakrishna

    2017-06-01

    A touch panel is an input device for human computer interaction. It consists of a network of sensors, a sampling circuit and a micro controller for detecting and locating a touch input. Touch input can come from either finger or stylus depending upon the type of touch technology. These touch panels provide an intuitive and collaborative workspace so that people can perform various tasks with the use of their fingers instead of traditional input devices like keyboard and mouse. Touch sensing technology is not new. At the time of this writing, various technologies are available in the market and this paper reviews the most common ones. We review traditional designs and sensing algorithms for touch technology. We also observe that due to its various strengths, capacitive touch will dominate the large-scale touch panel industry in years to come. In the end, we discuss the motivation for doing academic research on large-scale panels.

  10. Safety Assessment of Talc as Used in Cosmetics.

    Science.gov (United States)

    Fiume, Monice M; Boyer, Ivan; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan

    2015-01-01

    The Cosmetic Ingredient Review Expert Panel (Panel) assessed the safety of talc for use in cosmetics. The safety of talc has been the subject of much debate through the years, partly because the relationship between talc and asbestos is commonly misunderstood. Industry specifications state that cosmetic-grade talc must contain no detectable fibrous, asbestos minerals. Therefore, the large amount of available animal and clinical data the Panel relied on in assessing the safety of talc only included those studies on talc that did not contain asbestos. The Panel concluded that talc is safe for use in cosmetics in the present practices of use and concentration (some cosmetic products are entirely composed of talc). Talc should not be applied to the skin when the epidermal barrier is missing or significantly disrupted. © The Author(s) 2015.

  11. An expert panel approach to support risk-informed decision making

    International Nuclear Information System (INIS)

    Pulkkinen, U.; Simola, K.

    2000-01-01

    The report describes the expert panel methodology developed for supporting risk-informed decision making. The aim of an expert panel is to achieve a balanced utilisation of information and expertise from several disciplines in decision-making including probabilistic safety assessment as one decision criterion. We also summarise the application of the methodology in the STUK's RI-ISI (Risk-Informed In-Service Inspection) pilot study, where the expert panel approach was used to combine the deterministic information on degradation mechanisms and probabilistic information on pipe break consequences. The expert panel served both as a critical review of the preliminary results and as a decision support for the final definition of risk categories of piping. (orig.)

  12. 78 FR 15745 - Proposal Review Panel for Social and Economic Sciences; Notice of Meeting

    Science.gov (United States)

    2013-03-12

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Social and Economic Sciences; Notice of... Science Foundation (NSF) announces the following Site Visit. Name: Proposal Review Panel for Social and Economic Sciences, 10748. Date and Time: March 21, 2013 8:30 a.m. to 5:00 p.m., March 22, 2013 8:00 a.m. to...

  13. 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

  14. Effects of a Citizens Review Panel in Preventing Child Maltreatment Fatalities

    Science.gov (United States)

    Palusci, Vincent J.; Yager, Steve; Covington, Theresa M.

    2010-01-01

    Objective: Child maltreatment (CM) fatalities are often preventable, and reviewing these deaths often highlights problems in law, policy or practice that can be addressed to prevent future deaths. Citizen Review Panels (CRPs) comprised of medical and child welfare professionals were established in 1996 to review Child Protective Services (CPS)…

  15. 78 FR 16301 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2013-03-14

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Annual Review Site Visit at Hanford Observatory for Physics... Physics, National Science Foundation, Arlington, VA (703) 292-4432. [[Page 16302

  16. Minutes of the Tank Waste Science Panel meeting, July 20, 1990: Hanford Tank Safety Project

    International Nuclear Information System (INIS)

    Strachan, D.M.; Morgan, L.G.

    1991-02-01

    The second meeting of the Tank Waste Science Panel was held July 20, 1990. Science Panel members discussed the prioritization of various analyses to be performed on core samples from tank 101-SY, and were asked to review and comment on the draft Westinghouse Hanford Company document ''Analytical Chemistry Plan.'' They also reviewed and discussed the initial contributions to the report titled Chemical and Physical Processes in Tank 101-SY: A Preliminary Report. Science Panel members agreed that a fundamental understanding of the physical and chemical processes in the tank is essential, and strongly recommended that no remediation measures be taken until there is a better understanding of the chemical and physical phenomena that result in the episodic gas release from tank 101-SY. 1 ref

  17. Panel 5: Microbiology and Immunology Panel

    Science.gov (United States)

    Murphy, Timothy F.; Chonmaitree, Tasnee; Barenkamp, Stephen; Kyd, Jennelle; Nokso-Koivisto, Johanna; Patel, Janak A.; Heikkinen, Terho; Yamanaka, Noboru; Ogra, Pearay; Swords, W. Edward; Sih, Tania; Pettigrew, Melinda M.

    2014-01-01

    Objective The objective is to perform a comprehensive review of the literature from January 2007 through June 2011 on the virology, bacteriology, and immunology related to otitis media. Data Sources PubMed database of the National Library of Medicine. Review Methods Three subpanels with co-chairs comprising experts in the virology, bacteriology, and immunology of otitis media were formed. Each of the panels reviewed the literature in their respective fields and wrote draft reviews. The reviews were shared with all panel members, and a second draft was created. The entire panel met at the 10th International Symposium on Recent Advances in Otitis Media in June 2011 and discussed the review and refined the content further. A final draft was created, circulated, and approved by the panel. Conclusion Excellent progress has been made in the past 4 years in advancing an understanding of the microbiology and immunology of otitis media. Advances include laboratory-based basic studies, cell-based assays, work in animal models, and clinical studies. Implications for Practice The advances of the past 4 years formed the basis of a series of short-term and long-term research goals in an effort to guide the field. Accomplishing these goals will provide opportunities for the development of novel interventions, including new ways to better treat and prevent otitis media. PMID:23536533

  18. 76 FR 66998 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2011-10-28

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Annual Review Site Visit at Hanford Observatory for Physics...: Partially Closed. Contact Person: Thomas Carruthers, Program Director, Division of Physics, National Science...

  19. 77 FR 14441 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2012-03-09

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Annual Review Site Visit at Hanford Observatory for Physics...: Partially Closed. Contact Person: Thomas Carruthers, Program Director, Division of Physics, National Science...

  20. 76 FR 19147 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2011-04-06

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Laboratory Annual Review at Livingston Observatory for Physics...: Partially Closed. Contact Person: Thomas Carruthers, Program Director, Division of Physics, National Science...

  1. Password Based Distribution Panel and Circuit Breaker Operation for the Safety of Lineman during Maintenance Work

    OpenAIRE

    Hudedmani, Mallikarjun G; Ummannanavar, Nitin; Mudaliar, Mani Dheeraj; Sooji, Chandana; Bogar, Mala

    2017-01-01

    Security is the prime concern in our day to day life while performing any activity. In the current scenario, accidental death of lineman is often read and evidenced. In this direction, a safety measure to safe guard the operator is found very necessary looking into the present working style. The electric lineman safety system is designed to control the control panel doors and circuit breaker by using a password for the safety. Critical electrical accidents to lineman are on the rise during el...

  2. Supporting public involvement in interview and other panels: a systematic review.

    Science.gov (United States)

    Baxter, Susan; Clowes, Mark; Muir, Delia; Baird, Wendy; Broadway-Parkinson, Andrea; Bennett, Carole

    2017-10-01

    Members of the public are increasingly being invited to become members of a variety of different panels and boards. This study aimed to systematically search the literature to identify studies relating to support or training provided to members of the public who are asked to be members of an interview panel. A systematic search for published and unpublished studies was carried out from June to September 2015. The search methods included electronic database searching, reference list screening, citation searching and scrutinizing online sources. We included studies of any design including published and unpublished documents which outlined preparation or guidance relating to public participants who were members of interview panels or representatives on other types of panels or committees. Results were synthesised via narrative methods. Thirty-six documents were included in the review. Scrutiny of this literature highlighted ten areas which require consideration when including members of the public on interview panels: financial resources; clarity of role; role in the interview process; role in evaluation; training; orientation/induction; information needs; terminology; support; and other public representative needs such as timing, accessibility and support with information technology. The results of the review emphasize a range of elements that need to be fully considered when planning the involvement of public participants on interview panels. It highlights potential issues relating to the degree of involvement of public representatives in evaluating/grading decisions and the need for preparation and on-going support. © 2016 The Authors. Health Expectations Published by John Wiley & Sons Ltd.

  3. 75 FR 70951 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-11-19

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: LIGO Laboratory Annual Review at Hanford Observatory for Physics... Physics, National Science Foundation, (703) 292-7373. Purpose of Meeting: To provide an evaluation of the...

  4. Literature Review of Shear Performance of Light-weight Steel Framing Wall Panels

    Science.gov (United States)

    Zhang, Zhuangnan; Liu, Shen; Liu, Hong

    2018-03-01

    In this paper, a comprehensive review of light-weight steel framing wall panels was carried out. The structure and force characteristics of light-weight steel framing wall panels were introduced. The testing and theoretical research results on the shear behaviour of light-weight steel framing wall panels were summarized in the domestic and foreign. And combined with the existing standards in China, the author's views and ideas are put forward to the problems in the research field of this kind of structural system.

  5. 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

  6. 77 FR 69505 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2012-11-19

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation announces the following meeting. Name: LIGO Operations Proposal and Annual Review in Physics (1208). Date...

  7. Radically Reducing the Costs of Panel Critical Reviews According to ISO 14040

    DEFF Research Database (Denmark)

    Weidema, Bo Pedersen; Christiansen, Kim; Wernet, Gregor

    2013-01-01

    We suggest a procedure that radically reduces the critical review costs without compromising their thoroughness and overall quality. This procedure has 3 elements: A fixed panel for all reviews, an already critically reviewed background database, and a software-supported review procedure. The pre....... The presentation discusses these elements in the light of the upcoming ISO 14071 on critical review....

  8. Track 2: business outlook and the significance of safety - safety of nuclear power reactor installations in a deregulated environment. Panel Discussion

    International Nuclear Information System (INIS)

    Schultz, Stephen P.; Floyd, Stephen; Berkow, Herbert N.; Quinn, Edward L.; Hagen, Ronald E.; Esselman, Thomas C.

    2001-01-01

    Full text of publication follows: Deregulation in the nuclear industry sets the stage for a new production environment with cost and profit-based competition. This not only affects the commercial reactor sector but also is a key element of the U.S. Department of Energy's (DoE's) strategy for facility deployment and commercialization. This panel is designed to explore how these transitions are being made with the assurance of the principle of safety in operations. Panelists have been assembled from industry, the U.S. Nuclear Regulatory Commission (NRC), and DOE to explore these challenges and opportunities in the deregulated operational environment from a variety of perspectives. Presentations by each panelist will be followed by a panel session that will explore both technical and process elements of these major transitions. Success in a deregulated environment requires both safety and economic operation of facilities. With respect to each of these attributes, competition may be expected to result in substantially higher levels of performance. This panel will examine how these expectations are likely to be set, how they will be measured, and what will constitute success. The baseline for evaluation begins with assessment of past performance. The panelists have examined this for both the commercial nuclear reactor sector, as well as for the DOE complex. The Nuclear Energy Institute and the NRC have been working over the past few years on a program to establish new performance indicators for monitoring safety of reactor operation. The session participants will first examine the effectiveness of this system as it is designed to measure performance in today's environment. Second, the panelists will project the capabilities and attributes of this system in monitoring safety in transition to a deregulated, consolidated market. Will these systems have the capability to identify trends that will be significant in this new environment? Will today's system and metrics be

  9. Plasma Facing Components Generic Facilities Review Panel (PFC-GFRP): Final report

    International Nuclear Information System (INIS)

    McGrath, R.; Allen, S.; Hill, D.; Brooks, J.; Mattas, R.; Davis, J.; Lipschultz, B.; Ulrickson, M.

    1993-10-01

    The Plasma Facing Components (PFC) Facilities Review Panel was chartered by the US Department of Energy, Office of Fusion Energy, ITER (International Thermonuclear Experimental Reactor) and Technology Division, to outline the program plan and identify the supporting test facilities that lead to reliable, long-lived plasma facing components for ITER. This report summarizes the panel's findings and identifies the necessary and sufficient set of test facilities required for ITER PFC development

  10. 77 FR 66441 - North American Free Trade Agreement, Article 1904 NAFTA Panel Reviews; First Request for Panel...

    Science.gov (United States)

    2012-11-05

    ... DEPARTMENT OF COMMERCE International Trade Administration North American Free Trade Agreement... North American Free Trade Agreement. Panel Review was requested of the U.S. Department of Commerce's..., (202) 482-5438. SUPPLEMENTARY INFORMATION: Chapter 19 of the North American Free Trade Agreement...

  11. 76 FR 29746 - Science Advisory Board Staff Office Notification of a Public Meeting of the SAB Mercury Review Panel

    Science.gov (United States)

    2011-05-23

    ... Public Meeting of the SAB Mercury Review Panel AGENCY: Environmental Protection Agency (EPA). ACTION... Office announces a public meeting of the SAB Mercury Review Panel. DATES: The meeting will be held on... FACA and EPA policy, notice is hereby given that the SAB Mercury Review Panel will hold a public...

  12. International Cooperation in the Field of International Space Station Payload Safety: Overcoming Differences and Working for Future

    Science.gov (United States)

    Nakamura, Yasuhiro; Ozawa, Masayuki; Takeyasu, Yoshioka; Griffith, Gerald; Goto, Katsuhito; Mitsui, Masami

    2010-09-01

    The importance of international cooperation among the International Space Station(ISS) Program participants is ever increasing as the ISS nears assembly complete. In the field of payload safety assurance, NASA and JAXA have enhanced their cooperation level. The authors describe the evolution of cooperation between the two agencies and the challenges encountered and overcame. NASA and JAXA have been working toward development of a NASA Payload Safety Review Panel(PSRP) franchise panel at JAXA for several years. When the JAXA Safety Review Panel(SRP) becomes a fully franchised panel of the NASA PSRP, the JAXA SRP will have the authority review and approve all JAXA ISS payloads operated on USOS and JEM, although NASA and JAXA joint reviews may be conducted as necessary. A NASA PSRP franchised panel at JAXA will streamline the conventional review process. Japanese payload organizations will not have to go through both JAXA and NASA payload safety reviews, while NASA will be relieved of a certain amount of review activities. The persistent efforts have recently born fruit. For the past two years, NASA and JAXA have increased emphasis on efforts to develop a NASA PSRP Franchised Panel at JAXA with concrete results. In 2009, NASA and JAXA signed Charter and Joint Development Plan. At the end of 2009, NASA PSRP transferred some review responsibility to the JAXA SRP under the franchising charter. Although JAXA had long history of reviewing payloads by their own panel prior to NASA PSRP reviews, it took several years for JAXA to receive NASA PSRP approval for delegation of franchised review authority to JAXA. This paper discusses challenges JAXA and NAXA faced. Considerations were required in developing a franchise at JAXA for history and experiences of the JAXA SRP as well as language and cultural differences. The JAXA panel, not only had its own well-established processes and supporting organizational structures which had some differences from its NASA PSRP counterparts

  13. 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

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. Three Mile Island, Unit 2, radiation protection program: report of the special panel

    International Nuclear Information System (INIS)

    Meinhold, C.B.; Murphy, T.D.; Neely, D.R.; Kathren, R.L.; Rich, B.L.; Stone, G.F.; Casey, W.R.

    1979-12-01

    A special panel was appointed by the Director of Nuclear Reactor Regulation, NRC, to review the radiation protection program at Three Mile Island Unit 2. The Panel confirmed several management and technical deficiencies in the program. Recent major GPU/Met Ed commitments and actions demonstrated a major change in management attitude. The Panel concluded that exposures to personnel can be maintained to as low as is reasonably achievable while limited preparatory recovery work continues and when further needed improvements are implemented as needed, the radiation safety program will be able to support major recovery activities

  20. Three Mile Island, Unit 2, radiation protection program: report of the special panel

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, C. B. [Brookhaven National Lab., Upton, NY (United States); Murphy, T. D. [Nuclear Regulatory Commission, Washington, DC (United States); Neely, D. R. [Nuclear Regulatory Commission, Washington, DC (United States); Kathren, R. L. [Batelle Pacific Northwest Lab. (United States); Rich, B. L. [Exxon Nuclear Idaho Co., Inc. ID (United States); Stone, G. F. [Tennessee Valley Authority, Chattanooga, TN (United States); Casey, W. R. [Brookhaven National Lab., Upton, NY (United States)

    1979-12-01

    A special panel was appointed by the Director of Nuclear Reactor Regulation, NRC, to review the radiation protection program at Three Mile Island Unit 2. The Panel confirmed several management and technical deficiencies in the program. Recent major GPU/Met Ed commitments and actions demonstrated a major change in management attitude. The Panel concluded that exposures to personnel can be maintained to as low as is reasonably achievable while limited preparatory recovery work continues and when further needed improvements are implemented as needed, the radiation safety program will be able to support major recovery activities.

  1. 2014 Behavioral Health and Performance Standing Review Panel

    Science.gov (United States)

    Steinberg, Susan; Leon, Gloria; Dimsdale, Joel; Balkin, Thomas; Bono, Joyce; Caldwell, John; Joiner, Thomas; Paulus, Martin; Zaccaro, Stephen

    2015-01-01

    The 2014 Behavioral Health and Performance (BHP) Standing Review Panel (from here on referred to as the SRP) met for a site visit in Houston, TX on December 17 - 18, 2014. The SRP reviewed the updated research plan for the Risk of Performance Errors Due to Fatigue Resulting from Sleep Loss, Circadian Desynchronization, Extended Wakefulness, and Work Overload (Sleep Risk) and also received a status update on the Risk of Adverse Behavioral Conditions and Psychiatric Disorders (BMed Risk) and the Risk of Performance Decrements Due to Inadequate Cooperation, Coordination, Communication, and Psychosocial Adaptation within a Team (Team Risk).

  2. Development of web-based safety review advisory system

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  3. Aid to Families with Dependent Children Quality Control Review Panel Decisions

    Data.gov (United States)

    U.S. Department of Health & Human Services — Decisions issued by the Aid to Families with Dependent Children (AFDC) Quality Control Review Panel of the Departmental Appeals Board concerning the AFDC program...

  4. 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)

  5. 75 FR 57779 - Science Advisory Board Staff Office; Notification of a Public Meeting of the SAB Dioxin Review Panel

    Science.gov (United States)

    2010-09-22

    ... a Public Meeting of the SAB Dioxin Review Panel AGENCY: Environmental Protection Agency (EPA...) Staff Office announces a public meeting of the SAB Dioxin Review Panel to continue its review of EPA's Reanalysis of Key Issues Related to Dioxin Toxicity and Response to NAS Comments, External Review Draft...

  6. Osteoporosis in Latin America: panel expert review

    Directory of Open Access Journals (Sweden)

    Patricia Clark

    2013-09-01

    Full Text Available Background. The Latin American region is undergoing a demographic and epidemiological transition, which is leading to an increase in chronic and degenerative diseases. Osteoporosis (OP and fragility fractures (FF are emerging as main causes of disease burden with great impact on health institutions. Purpose. This review article provides an updated overview of trends in the epidemiology and economic impact of OP and FF, as well as in diagnosis and available treatments in Latin America, including calcium, vitamin D and prevention programs. Methods. Expert panel. Conclusions. According to this review, there is a lack of epidemiological and economic information in the region. It is desirable to obtain information regarding quality of life in OP and FF as well as to highlight prevention as a tool to reduce FF.

  7. Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium

    International Nuclear Information System (INIS)

    1998-04-01

    The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper

  8. Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper Refs, figs, tabs

  9. 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.

  10. 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

  11. EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2014. Statement on the safety of ‘Cetyl Myristoleate Complex’ as an ingredient in food supplements

    DEFF Research Database (Denmark)

    Tetens, Inge; Poulsen, Morten

    Following a request from the European Commission, the Panel on Dietetic Products, Nutrition and Allergies was asked to update its opinion on the safety of ‘Cetyl Myristoleate Complex’ (CMC) as a novel food ingredient in the light of additional information submitted by the applicant. In its previous...... 90-day study cannot serve as a reliable source of information supporting the absence of adverse effects of CMC. The dossier of this new mandate contains three new references which were not submitted and hence not considered in the previous assessments. The Panel notes that two references do...

  12. 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)

  13. Performance assessment review for DOE LLW disposal facilities

    International Nuclear Information System (INIS)

    Wilhite, Elmer L.

    1992-01-01

    The United States Department of Energy (US DOE) disposes of low-level radioactive waste in near-surface disposal facilities. Safety of the disposal operations is evaluated for operational safety as well as long-term safety. Operational safety is evaluated based on the perceived level of hazard of the operation and may vary from a simple safety assessment to a safety analysis report. Long-term safety of all low-level waste disposal systems is evaluated through the conduct of a radiological performance assessment. The US DOE has established radiological performance objectives for disposal of low-level waste. They are to protect a member of the general public from receiving over 25 mrem/y, and an inadvertent intruder into the waste from receiving over 100 mrem/y continuous exposure or 500 mrem from a single exposure. For a disposal system to be acceptable, a performance assessment must be prepared which must be technically accurate and provide reasonable assurance that these performance objectives are met. Technical quality of the performance assessments is reviewed by a panel of experts. The panel of experts is used in two ways to assure the technical quality of performance assessment. A preliminary (generally 2 day) review by the panel is employed in the late stages of development to provide guidance on finalizing the performance assessment. The comments from this review are communicated to the personnel responsible for the performance assessment for consideration and incorporation. After finalizing the performance assessment, it is submitted for a formal review. The formal review is accomplished by a much more thorough analysis of the performance assessment over a multi-week time period. The panel then formally reports their recommendations to the US DOE waste management senior staff who make the final determination on acceptability of the performance assessment. A number of lessons have been learned from conducting several preliminary reviews of performance

  14. International Cooperation in the Field of International Space Station (ISS) Payload Safety

    Science.gov (United States)

    Grayson, C.; Sgobba, T.; Larsen, A.; Rose, S.; Heimann, T.; Ciancone, M.; Mulhern, V.

    2005-12-01

    In the frame of the International Space Station (ISS) Program cooperation, in 1998 the European Space Agency (ESA) approached the National Aeronautics and Space Administration (NASA) with the unique concept of a Payload Safety Review Panel (PSRP) "franchise" based at the European Space Technology Center (ESTEC), where the panel would be capable of autonomously reviewing flight hardware for safety. This paper will recount the course of an ambitious idea as it progressed into a fully functional reality. It will show how a panel initially conceived at NASA to serve a national programme has evolved into an international safety cooperation asset. The PSRP established at NASA began reviewing ISS payloads approximately in late 1994 or early 1995 as an expansion of the pre- existing Shuttle Program PSRP. This paper briefly describes the fundamental Shuttle safety process and the establishment of the safety requirements for payloads intending to use the Space Transportation System and ISS. The paper will also offer some historical statistics about the experiments that completed the payload safety process for Shuttle and ISS. The paper then presents the background of ISS agreements and international treaties that had to be considered when establishing the ESA PSRP. The paper will expound upon the detailed franchising model, followed by an outline of the cooperation charter approved by the NASA Associate Administrator, Office of Space Flight, and ESA Director of Manned Spaceflight and Microgravity. The paper will then address the resulting ESA PSRP implementation and its success statistics to date. Additionally, the paper presents ongoing developments with the Japan Aerospace Exploration Agency (JAXA). The discussion will conclude with ideas for future developments, such to achieve a fully integrated international system of payload safety panels for ISS.

  15. International Cooperation in the Field of International Space Station (ISS) Payload Safety

    Science.gov (United States)

    Heimann, Timothy; Larsen, Axel M.; Rose, Summer; Sgobba, Tommaso

    2005-01-01

    In the frame of the International Space Station (ISS) Program cooperation, in 1998, the European Space Agency (ESA) approached the National Aeronautics and Space Administration (NASA) with the unique concept of a Payload Safety Review Panel (PSRP) "franchise" based at the European Space Technology Center (ESTEC), where the panel would be capable of autonomously reviewing flight hardware for safety. This paper will recount the course of an ambitious idea as it progressed into a fully functional reality. It will show how a panel initially conceived at NASA to serve a national programme has evolved into an international safety cooperation asset. The PSRP established at NASA began reviewing ISS payloads approximately in late 1994 or early 1995 as an expansion of the pre-existing Shuttle Program PSRP. This paper briefly describes the fundamental Shuttle safety process and the establishment of the safety requirements for payloads intending to use the Space Transportation System and International Space Station (ISS). The paper will also offer some historical statistics about the experiments that completed the payload safety process for Shuttle and ISS. The paper 1 then presents the background of ISS agreements and international treaties that had to be taken into account when establishing the ESA PSRP. The detailed franchising model will be expounded upon, followed by an outline of the cooperation charter approved by the NASA Associate Administrator, Office of Space Flight, and ESA Director of Manned Spaceflight and Microgravity. The resulting ESA PSRP implementation and its success statistics to date will then be addressed. Additionally the paper presents the ongoing developments with the Japan Aerospace Exploration Agency. The discussion will conclude with ideas for future developments, such to achieve a fully integrated international system of payload safety panels for ISS.

  16. Rabbit Lake uranium mining a-zone, d-zone, eagle point: report of the environmental assessment panel

    International Nuclear Information System (INIS)

    1993-11-01

    A report of the environmental assessment panel on Rabbit Lake, Saskatchewan. A review of the proposed development of the uranium mining facility at Rabbit Lake with respect to the environmental, health, safety, and socioeconomic impacts

  17. Rabbit Lake uranium mining a-zone, d-zone, eagle point: report of the environmental assessment panel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-11-01

    A report of the environmental assessment panel on Rabbit Lake, Saskatchewan. A review of the proposed development of the uranium mining facility at Rabbit Lake with respect to the environmental, health, safety, and socioeconomic impacts.

  18. 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.

  19. 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)

  20. 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)

  1. Safety Assessment of Chlorphenesin as Used in Cosmetics.

    Science.gov (United States)

    Johnson, Wilbur; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan

    2014-05-26

    Chlorphenesin functions as a biocide in cosmetics and is used at concentrations up to 0.32% in rinse-off products and up to 0.3% in leave-on products. The Cosmetic Ingredient Review Expert Panel (Panel) noted that chlorphenesin was well absorbed when applied to the skin of rats; however, any safety concern was minimized because available data demonstrated an absence of toxicity. The Panel concluded that chlorphenesin is safe in the present practices of use and concentration. © The Author(s) 2014.

  2. 78 FR 25309 - Proposal Review Panel Physics; Notice of Meeting

    Science.gov (United States)

    2013-04-30

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel Physics; Notice of Meeting In accordance with..., 2013 8:30 a.m.-6:30 p.m. May 15, 2013 8:30 a.m.-6:00 p.m. Place: University of Maryland, College Park... Physics Frontier Center; National Science Foundation, 4201 Wilson Blvd., Arlington, VA 22230. Telephone...

  3. 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)

  4. 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.

  5. 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

  6. Development of photovoltaic array and module safety requirements

    Science.gov (United States)

    1982-01-01

    Safety requirements for photovoltaic module and panel designs and configurations likely to be used in residential, intermediate, and large-scale applications were identified and developed. The National Electrical Code and Building Codes were reviewed with respect to present provisions which may be considered to affect the design of photovoltaic modules. Limited testing, primarily in the roof fire resistance field was conducted. Additional studies and further investigations led to the development of a proposed standard for safety for flat-plate photovoltaic modules and panels. Additional work covered the initial investigation of conceptual approaches and temporary deployment, for concept verification purposes, of a differential dc ground-fault detection circuit suitable as a part of a photovoltaic array safety system.

  7. 77 FR 27804 - Proposal Review Panel for Chemistry; Notice of Meeting

    Science.gov (United States)

    2012-05-11

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Chemistry; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation announces the following meeting: Name: Centers for Chemical Innovation (CCI) Solar Fuels: Powering the...

  8. 75 FR 3493 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-01-21

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: University of Nebraska Site Visit in Physics (1208). Date and Time... Director for Elementary Particle Physics, National Science Foundation, 4201 Wilson Blvd., Arlington, VA...

  9. 75 FR 57298 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-09-20

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: University of Notre Dame Site Visit in Physics (1208). Date and Time..., Program Director for Physics Education and Disciplinary Research, National Science Foundation, 4201 Wilson...

  10. 75 FR 63865 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-10-18

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting. Name: Michigan State University Site Visit in Physics (1208). Date and Time... Reidy, Program Director for Elementary Particle Physics, National Science Foundation, 4201 Wilson Blvd...

  11. 75 FR 70952 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-11-19

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation... Director for Elementary Particle Physics, National Science Foundation, 4201 Wilson Blvd., Arlington, VA...

  12. 76 FR 24921 - Proposal Review Panel for Chemistry; Notice of Meeting

    Science.gov (United States)

    2011-05-03

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Chemistry; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation..., Program Director, Chemistry Centers Program, Division of Chemistry, Room 1055, National Science Foundation...

  13. 78 FR 4464 - Proposal Review Panel for Chemistry; Notice of Meeting

    Science.gov (United States)

    2013-01-22

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Chemistry; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463, as amended), the National Science Foundation... Chemistry, Room 1055, National Science Foundation, 4201 Wilson Boulevard, Arlington, VA 22230, (703) 292...

  14. 76 FR 12996 - Proposal Review Panel for Chemistry; Notice of Meeting

    Science.gov (United States)

    2011-03-09

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Chemistry; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463 as amended), the National Science Foundation... Director, Chemistry Centers Program, Division of Chemistry, Room 1055, National Science Foundation, 4201...

  15. 76 FR 6499 - Proposal Review Panel for Chemistry; Notice of Meeting

    Science.gov (United States)

    2011-02-04

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Chemistry; Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92- 463 as amended), the National Science Foundation... Director, Chemistry Centers Program, Division of Chemistry, Room 1055, National Science Foundation, 4201...

  16. Vacuum insulation panels for building applications: A review and beyond

    Energy Technology Data Exchange (ETDEWEB)

    Baetens, Ruben [Department of Building Materials and Structures, SINTEF Building and Infrastructure, NO-7465 Trondheim (Norway); Department of Civil and Transport Engineering, Norwegian University of Science and Technology (NTNU), NO-7491 Trondheim (Norway); Laboratory of Building Physics, Department of Civil Engineering, Catholic University of Leuven (KUL), BE-3001 Heverlee (Belgium); Jelle, Bjoern Petter [Department of Building Materials and Structures, SINTEF Building and Infrastructure, NO-7465 Trondheim (Norway); Department of Civil and Transport Engineering, Norwegian University of Science and Technology (NTNU), NO-7491 Trondheim (Norway); Thue, Jan Vincent [Department of Civil and Transport Engineering, Norwegian University of Science and Technology (NTNU), NO-7491 Trondheim (Norway); Tenpierik, Martin J. [Faculty of Architecture, Urbanism and Building Sciences, Delft University of Technology, Julianalaan 134, 2628 BL Delft (Netherlands); Grynning, Steinar; Uvsloekk, Sivert [Department of Building Materials and Structures, SINTEF Building and Infrastructure, NO-7465 Trondheim (Norway); Gustavsen, Arild [Department of Architectural Design, History and Technology, Norwegian University of Science and Technology (NTNU), NO-7491 Trondheim (Norway)

    2010-02-15

    Vacuum insulation panels (VIPs) are regarded as one of the most promising high performance thermal insulation solutions on the market today. Thermal performances three to six times better than still-air are achieved by applying a vacuum to an encapsulated micro-porous material, resulting in a great potential for combining the reduction of energy consumption in buildings with slim constructions. However, thermal bridging due to the panel envelope and degradation of thermal performance through time occurs with current technology. Furthermore, VIPs cannot be cut on site and the panels are fragile towards damaging. These effects have to be taken into account for building applications as they may diminish the overall usability and thermal performance. This paper is as far as the authors know the first comprehensive review on VIPs. Properties, requirements and possibilities of foil encapsulated VIPs for building applications are studied based on available literature, emphasizing thermal bridging and degradation through time. An extension is made towards gas-filled panels and aerogels, showing that other high performance thermal insulation solutions do exist. Combining the technology of these solutions and others may lead to a new leap forward. Feasible paths beyond VIPs are investigated and possibilities such as vacuum insulation materials (VIMs) and nano insulation materials (NIMs) are proposed. (author)

  17. Panel 1: Safety design criteria

    International Nuclear Information System (INIS)

    Yllera, Javier

    2013-01-01

    There is general consensus in the nuclear community, and more after the Fukushima accident, that the deployment of nuclear energy has to be done at the highest levels of nuclear safety and that safety cannot be compromised by other factors. It is well understood that reactors that are being licensed and the new generations of reactors that will be constructed in the future will need to reach higher safety levels than the existing ones. Several countries and international organizations or international groups are launching initiatives to harmonise safety goals, safety requirements, safety objectives, regulations, criteria or safety reference levels. There are differences in the meanings of these terms and the working approaches, but the overall purpose is the same: to specify how new plants can be safer. In this context, the IAEA has an statutory function for developing international nuclear safety standards. The IAEA safety standards are per se not mandatory for IAEA Member States. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA’s standards for use in their national regulations in different ways. The IAEA Safety Standards represent international consensus on what must constitute a high level of safety for nuclear installations. In the area of NPP design, IAEA safety standards that are published are intended to apply primarily to new plants. It might not be practicable to apply all the requirements to plants that are already in operation. In addition, the focus is primarily on plants with water cooled reactors

  18. 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)

  19. EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2013 . S tatement on the safety of ' Cetyl Myristoleate Complex ' as an ingredient in food supplements

    DEFF Research Database (Denmark)

    Tetens, Inge

    Following a request from the European Commission, the Panel on Dietetic Products, Nutrition and Allergies was asked to update its opinion on the safety of „Cetyl Myristoleate Complex‟ (CMC) as a novel food ingredient in the light of a new repeated dose 90-day oral toxicity study in mice. In its p...

  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. EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2014. Scientific Opinion on the safety of astaxanthin-rich ingredients (AstaREAL A1010 and AstaREAL L10) as novel food ingredients

    DEFF Research Database (Denmark)

    Tetens, Inge; Poulsen, Morten

    2014-01-01

    /day. Mean and high-level (95th percentile) daily intakes of 0.106 mg/kg bw and 0.256 mg/kg bw astaxanthin from the NFIs were estimated, based on European consumption data of the proposed food categories. The consumption of the NFIs is not considered to be nutritionally disadvantageous. There are no safety....... The Panel notes that the maximum recommended intake of 4 mg astaxanthin per day (0.06 mg/kg bw) and the estimated mean intake based on the use levels in the proposed food categories (0.106 mg/kg bw per day) exceed the ADI by approximately two- and three-fold, respectively. The Panel therefore concludes......Following a request from the European Commission, the EFSA Panel on Dietetic Products, Nutrition and Allergies (NDA) was asked to deliver a scientific opinion on the safety of astaxanthin-rich ingredients AstaREAL A1010 and AstaREAL L10 as novel food ingredients (NFIs) in the context of Regulation...

  2. 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

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  4. Second public meeting of Governor Kaine's Independent Virginia Tech Incident Review Panel

    OpenAIRE

    Owczarski, Mark

    2007-01-01

    The second public meeting of Governor Kaine's Independent Virginia Tech Incident Review Panel will convene on Monday, May 21, at The Inn at Virginia Tech and Skelton Conference Center Latham Ballroom, 901 Prices Fork Road in Blacksburg.

  5. 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

  6. 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

  7. 77 FR 24228 - Proposal Review Panel for Social and Economic Sciences; Notice of Meeting

    Science.gov (United States)

    2012-04-23

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Social and Economic Sciences; Notice of...; Division of Social and Economic Sciences, Room 990, National Science Foundation, 4201 Wilson Boulevard... Science Foundation announces the following meeting: Name: Site visit review of the Nanoscale Science and...

  8. 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

  9. 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.

  10. 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

  11. 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.

  12. 78 FR 25101 - Proposal Review Panel for Physics, Notice of Meeting

    Science.gov (United States)

    2013-04-29

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics, Notice of Meeting In accordance... Physics, 1208 Date and Time: Tuesday, April 30, 2013; 8:00 a.m.-6:00 p.m., Wednesday, May 1, 2013, 8:00 a... Meeting: Partially Closed. Contact Person: Mark Coles, Director of Large Facilities, Division of Physics...

  13. 75 FR 67142 - Proposal Review Panel for Physics; Notice of Meeting

    Science.gov (United States)

    2010-11-01

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Physics; Notice of Meeting In accordance... announces the following meeting: Name: Site Visit to the Center for the Physics of Living Cells 1208. Dates... Physics of Living Cells (CPLC). Agenda Monday, November 8, 2010 9 a.m.-11:55 a.m.--Open--Directors...

  14. 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

  15. 76 FR 52330 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-08-22

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Member Conflict Review, Program Announcement (PA) 07-318, initial review. In...

  16. 78 FR 25743 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-05-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Member Conflict Review, Program Announcement (PA) 07-318, initial review. In...

  17. 77 FR 7164 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-02-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Member Conflict Review, Program Announcement (PA) 07-318, initial review. In...

  18. 76 FR 28790 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-05-18

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Member Conflict Review, Program Announcement (PA) 07-318, initial review. In...

  19. 77 FR 48986 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-08-15

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Member Conflict Review, Program Announcement (PA) 07-318, initial review. In...

  20. 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

  1. Integrated Thermal Treatment Systems study: US Department of Energy Internal Review Panel report

    International Nuclear Information System (INIS)

    Cudahy, J.; Escarda, T.; Gimpel, R.

    1995-04-01

    The U.S. Department of Energy's (DOE) Office of Technology Development (OTD) commissioned two studies to uniformly evaluate nineteen thermal treatment technologies. These studies were called the Integrated Thermal Treatment System (ITTS) Phase I and Phase II. With the advice and guidance of the DOE Office of Environmental Management's (EM's) Mixed Waste Focus Group, OTD formed an ITTS Internal Review Panel, composed of scientists and engineers from throughout the DOE complex, the U.S. Environmental Protection Agency (EPA), the California EPA, and private experts. The Panel met from November 15-18, 1994, to review and comment on the ITTS studies, to make recommendations on the most promising thermal treatment systems for DOE mixed low level wastes (MLLW), and to make recommendations on research and development necessary to prove the performance of the technologies on MLLW

  2. 78 FR 56236 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-09-12

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns NIOSH Member Conflict Review, PA 07-318, initial review. In accordance with Section...

  3. Peer review panel summary report for technical determination of mixed waste incineration off-gas systems for Rocky Flats

    International Nuclear Information System (INIS)

    1992-01-01

    A Peer Review Panel was convened on September 15-17, 1992 in Boulder, Co. The members of this panel included representatives from DOE, EPA, and DOE contractors along with invited experts in the fields of air pollution control and waste incineration. The primary purpose of this review panel was to make a technical determination of a hold, test and release off gas capture system should be implemented in the proposed RF Pland mixed waste incineration system; or if a state of the art continuous air pollution control and monitoring system should be utilized as the sole off-gas control system. All of the evaluations by the panel were based upon the use of the fluidized bed unit proposed by Rocky Flats and cannot be generalized to other systems

  4. 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...

  5. 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

  6. 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

  7. 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.

  8. 76 FR 4113 - Independent Scientific Peer Review Panel Meeting on an In Vitro

    Science.gov (United States)

    2011-01-24

    ... antagonist activity. These studies were funded primarily by a Small Business Innovation Research (SBIR) grant... Vitro Estrogen Receptor Transcriptional Activation Test Method for Endocrine Disruptor Chemical... Toxicological Methods (NICEATM); Announcement of an Independent Scientific Peer Review Panel Meeting on an In...

  9. Comments of the PRA Senior Review Panel on the meeting held December 1--3, 1987

    International Nuclear Information System (INIS)

    Sharp, D.A.

    1988-01-01

    This memorandum records the minutes of the PRA Senior Review Panel meeting held at Savannah River Laboratory (SRL) on December 1--3, 1987, and the report on that meeting written subsequently by the panel members. The minutes are contained as Attachment 2 of this memorandum, and the report as Attachment 1. The Panel indicated two principal concerns in their report: (1) that insufficient emphasis is being placed on the reliability data development program, and (2) that excessive detail is being built into the fault trees. These concerns have been addressed in a subsequent meeting with the Panel, held March 2--4, 1988. In addition, the members have been provided with a program document (Reference 1) indicating the extent, the timing, and the limitations of the data analysis effort for the PRA

  10. Final report of the cosmetic ingredient review expert panel on the safety assessment of Polyisobutene and Hydrogenated Polyisobutene as used in cosmetics.

    Science.gov (United States)

    2008-01-01

    controls. Neither Polyisobutene nor Hydrogenated Polyisobutene were ocular irritants, nor were they dermal irritants or sensitizers. Polyisobutene was not comedogenic in a rabbit ear study. Polyisobutene did not induce transformation in the Syrian hamster embryo (SHE) cell transformation assay, but did enhance 3-methylcholanthrene-induced transformation of C3H/10T1/2 cells. In a carcinogenicity study in mice, Polyisobutene was not carcinogenic, nor did it promote the carcinogenicity of 7,12-dimethylbenz(alpha)anthracene. Clinical patch tests uncovered no evidence of dermal irritation and repeat-insult patch tests with a product containing 4% Hydrogenated Polyisobutene or 1.44% Hydrogenated Polyisobutene found no reactions greater than slight erythema. These products also were not phototoxic or photoallergenic. The product containing 4% Hydrogenated Polyisobutene was not an ocular irritant in a clinical test. The Cosmetic Ingredient Review (CIR) Expert Panel recognized that there are data gaps regarding use and concentration of these ingredients. However, the overall information available on the types of products in which these ingredients are used and at what concentrations indicate a pattern of use, which was considered by the Expert Panel in assessing safety. Although there is an absence of dermal absorption data for Polyisobutene and Hydrogenated Polyisobutene, the available octanol water partition coefficient data and the low solubility in water suggest very slow absorption, so additional data are not needed. Gastrointestinal absorption is also not a major concern due to the low solubility of these chemicals. Although one in vitro study did report that Polyisobutene did promote cellular transformation, a mouse study did not find evidence of tumor promotion. Because lifetime exposure studies using rats and dogs exposed to Polybutene failed to demonstrate any carcinogenic or tumor promotion effect, and a three-generation reproductive/developmental toxicity study produced

  11. 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)

  12. A retrospective analysis of the effect of discussion in teleconference and face-to-face scientific peer-review panels

    Science.gov (United States)

    Carpenter, Afton S; Sullivan, Joanne H; Deshmukh, Arati; Glisson, Scott R; Gallo, Stephen A

    2015-01-01

    Objective With the use of teleconferencing for grant peer-review panels increasing, further studies are necessary to determine the efficacy of the teleconference setting compared to the traditional onsite/face-to-face setting. The objective of this analysis was to examine the effects of discussion, namely changes in application scoring premeeting and postdiscussion, in these settings. We also investigated other parameters, including the magnitude of score shifts and application discussion time in face-to-face and teleconference review settings. Design The investigation involved a retrospective, quantitative analysis of premeeting and postdiscussion scores and discussion times for teleconference and face-to-face review panels. The analysis included 260 and 212 application score data points and 212 and 171 discussion time data points for the face-to-face and teleconference settings, respectively. Results The effect of discussion was found to be small, on average, in both settings. However, discussion was found to be important for at least 10% of applications, regardless of setting, with these applications moving over a potential funding line in either direction (fundable to unfundable or vice versa). Small differences were uncovered relating to the effect of discussion between settings, including a decrease in the magnitude of the effect in the teleconference panels as compared to face-to-face. Discussion time (despite teleconferences having shorter discussions) was observed to have little influence on the magnitude of the effect of discussion. Additionally, panel discussion was found to often result in a poorer score (as opposed to an improvement) when compared to reviewer premeeting scores. This was true regardless of setting or assigned reviewer type (primary or secondary reviewer). Conclusions Subtle differences were observed between settings, potentially due to reduced engagement in teleconferences. Overall, further research is required on the psychology of

  13. 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)

  14. Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA)

    DEFF Research Database (Denmark)

    Leuschner, R. G. K.; Robinson, T. P.; Hugas, M.

    2010-01-01

    Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA) to notified biological agents aiming at simplifying risk assessments across different scientific Panels and Units. The aim of this review is to outline the implementation...... and value of the QPS assessment for EFSA and to explain its principles such as the unambiguous identity of a taxonomic unit, the body of knowledge including potential safety concerns and how these considerations lead to a list of biological agents recommended for QPS which EFSA keeps updated through...

  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. 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

  17. 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

  18. 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

  19. Micro-inverter solar panel mounting

    Science.gov (United States)

    Morris, John; Gilchrist, Phillip Charles

    2016-02-02

    Processes, systems, devices, and articles of manufacture are provided. Each may include adapting micro-inverters initially configured for frame-mounting to mounting on a frameless solar panel. This securement may include using an adaptive clamp or several adaptive clamps secured to a micro-inverter or its components, and using compressive forces applied directly to the solar panel to secure the adaptive clamp and the components to the solar panel. The clamps can also include compressive spacers and safeties for managing the compressive forces exerted on the solar panels. Friction zones may also be used for managing slipping between the clamp and the solar panel during or after installation. Adjustments to the clamps may be carried out through various means and by changing the physical size of the clamps themselves.

  20. 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

  1. 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

  2. 77 FR 28392 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-05-14

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Alcohol-related Motor Vehicle Injury Research, FOA CE12-006, initial review. In...

  3. 77 FR 31018 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-05-24

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Member Conflict Review, Program Announcement (PA) 07-318, and Centers of Excellence...

  4. 77 FR 28393 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-05-14

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Research to Prevent Prescription Drug Overdoses, FOA CE12-007, initial review. In...

  5. Safety Culture: Lessons Learned from the US Chemical Safety and Hazard Investigations Board

    International Nuclear Information System (INIS)

    Griffon, M.

    2016-01-01

    The U.S. Chemical Safety and Hazard Investigation Board (CSB) investigation of the 2005 BP Texas City Refinery disaster as well as the Baker Panel Report have set the stage for the consideration of human and organizational factors and safety culture as contributing causes of major accidents in the oil and gas industry. The investigation of the BP Texas City tragedy in many ways started a shift in the way the oil and chemical industry sectors looked at process safety and the importance of human and organizational factors in improving safety. Since the BP Texas City incident the CSB has investigated several incidents, including the 2010 Macondo disaster in the Gulf of Mexico, where organizational factors and safety culture, once again, were contributing causes of the incidents. In the Texas City incident the CSB found that “while most attention was focused on the injury rate, the overall safety culture and process safety management (PSM) program had serious deficiencies.” The CSB concluded that “safety campaigns, goals, and rewards focused on improving personal safety metrics and worker behaviors rather than on process safety and management safety systems.” The Baker panel, established as a result of a CSB recommendation, did a more extensive review of BPs safety culture. The Baker panel found that ‘while BP has aspirational goals of “no accidents, no harm to people” BP has not provided effective leadership in making certain it’s management and US refining workforce understand what is expected of them regarding process safety performance.’ This may have been in part due to a misinterpretation of positive trends in personal injury rates as an indicator of effective process safety. The panel also found that “at some of its US refineries BP has not established a positive, trusting and open environment with effective lines of communication between management and the workforce, including employee representatives.” In 2010 when the CSB began to

  6. EFSA BIOHAZ Panel (EFSA Panel on Biological Hazards), 2013. Scientific Opinion on the maintenance of the list of QPS biological agents intentionally added to food and feed (2013 update)

    DEFF Research Database (Denmark)

    Licht, Tine Rask; Baggesen, Dorte Lau

    EFSA is requested to assess the safety of a broad range of biological agents in the context of notifications for market authorisation as sources of food and feed additives, enzymes and plant protection products. The qualified presumption of safety (QPS) assessment was developed to provide...... a harmonised generic pre-assessment to support safety risk assessments performed by EFSA’s scientific Panels. The safety of unambiguously defined biological agents (at the highest taxonomic unit appropriate for the purpose for which an application is intended), and the completeness of the body of knowledge...... is the one in the most recently published scientific opinion. The 2013 update reviews previously assessed microorganisms including bacteria, yeasts, filamentous fungi, oomycetes and viruses used for plant protection purposes. All taxonomic units previously recommended for the QPS list had their status...

  7. 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...

  8. 77 FR 24227 - Proposal Review Panel for Social and Economic Sciences; Notice of Meeting

    Science.gov (United States)

    2012-04-23

    ... NATIONAL SCIENCE FOUNDATION Proposal Review Panel for Social and Economic Sciences; Notice of... Engineering Center (NSEC) at Arizona State University by the Division Social and Economic Sciences ( 10748... Kronz, Program Director; Science, Technology and Society Program; Division of Social and Economic...

  9. 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

  10. 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

  11. 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

  12. 2015 Space Human Factors Engineering Standing Review Panel

    Science.gov (United States)

    Steinberg, Susan

    2015-01-01

    The 2015 Space Human Factors Engineering (SHFE) Standing Review Panel (from here on referred to as the SRP) met for a site visit in Houston, TX on December 2 - 3, 2015. The SRP reviewed the updated research plans for the Risk of Inadequate Design of Human and Automation/Robotic Integration (HARI Risk), the Risk of Inadequate Human-Computer Interaction (HCI Risk), and the Risk of Inadequate Mission, Process and Task Design (MPTask Risk). The SRP also received a status update on the Risk of Incompatible Vehicle/Habitat Design (Hab Risk) and the Risk of Performance Errors Due to Training Deficiencies (Train Risk). The SRP is pleased with the progress and responsiveness of the SHFE team. The presentations were much improved this year. The SRP is also pleased with the human-centered design approach. Below are some of the more extensive comments from the SRP. We have also made comments in each section concerning gaps/tasks in each. The comments below reflect more significant changes that impact more than just one particular section.

  13. Predicting panel scores by linguistic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Van den Besselaar, P.; Stout, L.; Gou, X

    2016-07-01

    In this paper we explore the use of text analysis for deriving quality indicators of project proposals. We do full text analysis of 3030 review reports. After term extraction, we aggregate the term occurrences to linguistic categories. Using thse linguistic categories as independent variables, we study how well these predict the grading by the review panels. Together, the different linguistic categories explain about 50% of the variance in the grading of the applications. The relative importance of the different linguistic categories inform us about the way the panels work. This can be used to develop altmetrics for the quality of the peer and panel review processes. (Author)

  14. 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)

  15. 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.

  16. 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)

  17. Geochemistry Review Panel report on the SRP geochemistry program and draft geochemistry summary program plan (May, 1986) and discussion of panel recommendations

    International Nuclear Information System (INIS)

    1986-12-01

    The Geochemistry Review Panel (GRP) was established by the Salt Repository Project Office (SRPO) to help evaluate geochemistry-related issues in the US Department of Energy's nuclear waste repository program. The May 1986 meeting of the GRP reviewed the Salt Repository Program (SRP) geochemistry program developed by the Office of Nuclear Waste Isolation (ONWI). This program is described in the Draft Geochemistry Plan of April 9, 1986. This report documents the GRP's comments and recommendations on this subject and the ONWI responses to the specific points raised by the GRP

  18. 2013 Nutrition Risk Evidence Review Panel. Evidence Review for: The Risk Factor of Inadequate Nutrition

    Science.gov (United States)

    2014-01-01

    The 2013 Nutrition Risk Standing Review Panel (from here on referred to as the SRP) met for a site visit in Houston, TX on November 20 - 21, 2013. The SRP reviewed the new Evidence Report for the Risk Factor of Inadequate Nutrition (from here on referred to as the 2013 Nutrition Evidence Report), as well as the Research Plan for this Risk. Overall, the SRP thinks the well-qualified research team has compiled an excellent summary of background information in the 2013 Nutrition Evidence Report. The SRP would like to commend the authors in general and particularly note that while the 2013 Nutrition Evidence Report has been written using a single nutrient approach, the research plan takes a much more integrated and physiologically based approach.

  19. Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

    International Nuclear Information System (INIS)

    2010-01-01

    A panel of three members has been asked by the Ministry of Employment and the Economy (MEE) to evaluate SAFIR2010, the Finnish research program on nuclear power plant safety. The program was established for the period 2007-2010 to help maintain expertise in nuclear safety, to integrate young people into the research in order to help assure the future availability of expertise, and to support international collaborations. The program is directed by a Steering Group, appointed by MEE, with representatives from all organizations involved with nuclear safety in Finland. SAFIR2010 has consisted of approximately 30 projects from year to year that fall into eight subject areas: 1. Organization and human factors 2. Automation and control room 3. Fuel and reactor physics 4. Thermal hydraulics 5. Severe accidents 6. Structural safety of reactor circuit 7. Construction safety 8. Probabilistic safety analysis (PSA) For each of these areas there are Reference Groups that provide oversight of the projects within their jurisdiction. The panel carried out its evaluation by reviewing copies of relevant documents and, during a one-week period 17-22 January 2010, meeting with key individuals. The results of the panel are provided as general conclusions, responses to questions posed by MEE, challenges and recommendations and comments on specific projects in each subject area. The general conclusions reflect the panel's view that SAFIR2010 is meeting its objectives and carrying out quality research. The questions addressed are: (a.) Are the achieved results in balance with the funding? Are the results exploited efficiently in practice? (b.) How well does the expertise cover the field? Is the entire SAFIR2010 programme balanced to all different fields in nuclear safety? Does it raise efficiently new experts? (c.) Have the 2006 evaluation results been implemented successfully into SAFIR2010 program? (d.) Challenges and recommendations. In general the panel was very positive about SAFIR

  20. 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

  1. Uncertainty analysis for Ulysses safety evaluation report

    International Nuclear Information System (INIS)

    Frank, M.V.

    1991-01-01

    As part of the effort to review the Ulysses Final Safety Analysis Report and to understand the risk of plutonium release from the Ulysses spacecraft General Purpose Heat Source---Radioisotope Thermal Generator (GPHS-RTG), the Interagency Nuclear Safety Review Panel (INSRP) and the author performed an integrated, quantitative analysis of the uncertainties of the calculated risk of plutonium release from Ulysses. Using state-of-art probabilistic risk assessment technology, the uncertainty analysis accounted for both variability and uncertainty of the key parameters of the risk analysis. The results show that INSRP had high confidence that risk of fatal cancers from potential plutonium release associated with calculated launch and deployment accident scenarios is low

  2. 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

  3. 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

  4. 75 FR 20567 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2010-04-20

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... Article 1904 of the Agreement, which came into force on January 1, 1994, the Government of the United States, the Government of Canada and the Government of Mexico established Rules of Procedure for Article...

  5. 76 FR 56156 - North American Free-Trade Agreement (NAFTA), Article 1904 Binational Panel Reviews

    Science.gov (United States)

    2011-09-12

    ... (NAFTA), Article 1904 Binational Panel Reviews AGENCY: NAFTA Secretariat, United States Section... Article 1904 of the Agreement, which came into force on January 1, 1994, the Government of the United States, the Government of Canada and the Government of Mexico established Rules of Procedure for Article...

  6. 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

  7. Submission to the Georges Bank Review Panel

    Energy Technology Data Exchange (ETDEWEB)

    Rankin, E.; Butler, M.; Church, T.

    1999-01-01

    The Georges Bank, off southwestern Nova Scotia, is one of the most biologically productive continental shelf ecosystems in the world. It supports a wide diversity of species, including many seabirds. In 1988, federal and provincial legislation placed a moratorium on petroleum exploration and drilling on the Georges Bank, directing the ministers of Natural Resources Canada, and of the Nova Scotia Department of Natural Resources to make a decision regarding the moratorium by January 1, 2000. This report by the Ecology Action Centre (EAC) asks the Georges Bank Review Panel to recommend extending the moratorium on Georges Bank and adjacent areas until 2012, in part to match the American moratorium. Other reasons why the panel made this recommendation were explored. The principal reason is the EAC concern that when the moratorium is lifted, several oil and gas developments will proceed in this ecologically significant offshore area that could result in the loss of the ecological integrity of Georges Bank. The EAC contends that before oil and gas development in the region could begin, the following issues would have to be resolved: (1) disposal of drill muds and cuttings, (2) volume and disposal of produced water, (3) effects of small and large spills, (4) impact of seismic activities on whales and turtles, and (5) carbon dioxide emission through venting and flaring. Also, the EAC does not believe that developing Georges Bank will create as many jobs in the affected communities as some people suggest. Lifting the moratorium by Canada would also frustrate American environmental goals, as well as compromise Canada`s position in international environmental partnerships such as the Gulf of Maine Council. 19 refs., tabs., figs.

  8. Submission to the Georges Bank Review Panel

    International Nuclear Information System (INIS)

    Rankin, E.; Butler, M.; Church, T.

    1999-01-01

    The Georges Bank, off southwestern Nova Scotia, is one of the most biologically productive continental shelf ecosystems in the world. It supports a wide diversity of species, including many seabirds. In 1988, federal and provincial legislation placed a moratorium on petroleum exploration and drilling on the Georges Bank, directing the ministers of Natural Resources Canada, and of the Nova Scotia Department of Natural Resources to make a decision regarding the moratorium by January 1, 2000. This report by the Ecology Action Centre (EAC) asks the Georges Bank Review Panel to recommend extending the moratorium on Georges Bank and adjacent areas until 2012, in part to match the American moratorium. Other reasons why the panel made this recommendation were explored. The principal reason is the EAC concern that when the moratorium is lifted, several oil and gas developments will proceed in this ecologically significant offshore area that could result in the loss of the ecological integrity of Georges Bank. The EAC contends that before oil and gas development in the region could begin, the following issues would have to be resolved: (1) disposal of drill muds and cuttings, (2) volume and disposal of produced water, (3) effects of small and large spills, (4) impact of seismic activities on whales and turtles, and (5) carbon dioxide emission through venting and flaring. Also, the EAC does not believe that developing Georges Bank will create as many jobs in the affected communities as some people suggest. Lifting the moratorium by Canada would also frustrate American environmental goals, as well as compromise Canada's position in international environmental partnerships such as the Gulf of Maine Council. 19 refs., tabs., figs

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  10. Proceedings of the twenty-fifth annual institute on mining health, safety and research

    Energy Technology Data Exchange (ETDEWEB)

    Tinney, G.R.; Bacho, A.; Karmis, M. [eds.

    1994-12-31

    The keynote session included papers on the US Bureau of Mines - a vision for the future; clean, green and lean; and the psychology of occupational safety. The technical sessions include panel discussions on Virginia`s revised mine safety regulations, and on independent contractors. Other papers covered: criminal enforcement of regulatory violations; accidents during surface mine mobile equipment; Federal Mine Safety and Health Review Commission; safety, technological and productivity potentials of highwall mining; and accidents caused by falls of unsupported roof.

  11. 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

  12. 77 FR 66855 - Center for Scientific Review; Notice of Closed Meetings

    Science.gov (United States)

    2012-11-07

    ... personal privacy. Name of Committee: Center for Scientific Review Special Emphasis Panel; Gene Discover...-HIV Diagnostics, Food Safety, Sterilization/Disinfection and Bioremediation. Date: November 15-16...

  13. 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.

  14. 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...

  15. Tracking the New Technology. A Summary of the Second Invitational Postsecondary Educational Review Panel.

    Science.gov (United States)

    Sterling, C. H.

    The second educational technology review panel addressed problems with forecasting the trends and impact of newer telecomunications technologies in both home and institution of higher education settings, and the role of several grant programs in educational technology. Paul Mertins provided an update on a National Center for Education Statistics…

  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 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

  18. Government of Canada response to the report of the Expert Review Panel on medical isotope production

    International Nuclear Information System (INIS)

    Paradis, C.

    2010-01-01

    Recent supply disruptions have highlighted the fragility of the supply chain that delivers essential medical isotopes to patients globally. A new and more reliable way of supplying isotopes to Canadians needs to be found. That is why the Government of Canada established the Expert Review Panel on Medical Isotope Production (the Panel) in June 2009. The Government recognizes the relatively long lead times associated with the development of any new source of medical. isotopes. To ensure that appropriate action is taken now for the long term, the Government tasked the Panel with reporting to the Minister. of Natural Resources on its assessment of the most viable options for securing supplies of technetium-99m (Tc99r) for the Canadian health care system over the medium and long term and the actions that may be required by governments and others to facilitate realization of these options. The Panel reported to the Minister of Natural Resources on November 30, 2009. Since then, the Government has been carefully considering the recommendations of the Panel within the context of the broader nuclear and health care landscape. What follows is the Government's response to the Panel's thoughtful, comprehensive and insightful report, including actions that are planned based on its recommendations. (author)

  19. 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.

  20. Puncture panel optimization

    International Nuclear Information System (INIS)

    Glass, R.E.; Longenbaugh, R.S.

    1986-01-01

    Sandia National Laboratories developed the TRansUranic PACkage Transporter (TRUPACT) to transport defense contact-handled transuranic wastes. The package has been designed to meet the normal and hypothetical accident conditions in 10CFR71 which includes the demonstrated ability to survive a 1-meter drop onto a mild steel pin. The puncture protection is provided by puncture resistant panels. In conjunction with the development of TRUPACT, a series of experiments has been conducted to reduce the weight of the puncture resistant panels. The initial scoping tests resulted in a preliminary design incorporating 30 layers of Kevlar. This design has been shown to meet the regulatory puncture test. To reduce the weight of this panel, subscale tests were conducted on panels utilizing Kevlar yarns with varying mass per unit length (denier) as well as different resins. This paper reviews the testing undertaken in the original panel development and discusses the results obtained from the recent subscale and full-scale optimization tests

  1. 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

  2. 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.

  3. Report of the Panel on Kinetics and Applications of Pulsed Research Reactors

    International Nuclear Information System (INIS)

    1966-03-01

    The question of the dynamic behaviour of a reactor subjected to a highly supercritical condition has had special interest for reactor physicists because of the reactor safety implications involved. The large amount of experimental and theoretical work done during the past dozen years or sc to understand fast transient behaviour and the inherent safety characteristics of reactors has not only helped to ease the concern of reactor designers about the consequences of a prompt critical excursion, but, by demonstrating the feasibility of operating certain types of reactors in a pulsed fashion has led to the development of an extremely useful research tool. Pulsed research reactors of a number of different kinds are in operation, while newer, higher performance systems are presently being designed and constructed. Such devices are being used more and more for research in physics, chemistry and reactor engineering, and with the advent of the newer machines, new research areas will become accessible. Because of the rapidly growing interest in the utilization of pulsed reactors for research, the IAEA convened a panel of experts in this field to review recent progress in the design and application of pulsed reactors to consider the problems of converting an existing pool type research reactor to a pulsing types and to consider future potentialities. The panel met in Vienna from 17 to 21 May 1965. This report of the panel summarizes the discussions

  4. 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...

  5. 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

  6. 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

  7. 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).

  8. 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).

  9. 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

  10. 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

  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. [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.

  13. 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.

  14. Hanford Tank Safety Project: Minutes of the Tank Waste Science Panel meeting, February 7--8, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Strachan, D.M. [comp.

    1991-06-01

    The Tank Waste Science Panel met February 7--8, 1991, to review the latest data from the analyses of the October 24, 1990, gas release from Tank 241-SY-101 (101-SY) at Hanford; discuss the results of work being performed in support of the Hanford Tank Safety Project; and be briefed on the ferrocyanide issues included in the expanded scope of the Science Panel. The shapes of the gas release curves from the past three events are similar and correlate well with changes in waste level, but the correlation between the released volume of gas and the waste height is not as good. An analysis of the kinetics of gas generation from waste height measurements in Tank 101-SY suggests that the reaction giving rise to the gases in the tank is independent of the gas pressure and independent of the physical processes that give rise to the episodic release of the gases. Tank waste height data were also used to suggest that a floating crust formed early in the history of the tank and that the current crust is being made thicker in the eastern sector of the tank by repeated upheaval of waste slurry onto the surface. The correlation between the N{sub 2}O and N{sub 2} generated in the October release appears to be 1:1, suggesting a single mechanistic pathway. Analysis of other gas generation ratios, however, suggests that H{sub 2} and N{sub 2}O are evolved together, whereas N{sub 2} is from the air. If similar ratios are observed in planned radiolysis experiments are Argonne National Laboratory, radiolysis would appear to be generating most of the gases in Tank 101-SY. Data from analysis of synthetic waste crust using a dynamic x-ray diffractometer suggest that, in air, organics are being oxidized and liberating CO{sub 2} and NO{sub x}. Experiments at Savannah River Laboratory indicate that irradiation of solutions containing NO{sub 3} and organics can produce N{sub 2}O.

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

    International Nuclear Information System (INIS)

    1987-06-01

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

  16. 76 FR 18766 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-04-05

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Epidemiologic Research and Surveillance in Epilepsy, Funding Opportunity...

  17. 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...

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  19. 78 FR 19490 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial Review

    Science.gov (United States)

    2013-04-01

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial Review The meeting announced below concerns Monitoring Cause-Specific School Absenteeism for Estimating Community Wide...

  20. 77 FR 25180 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-04-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Conducting Research on Moderate Acute Malnutrition in Humanitarian Emergencies...

  1. 77 FR 20822 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-04-06

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Detecting Emerging Vector- Borne Zoonotic Pathogens in Indonesia, Funding...

  2. 78 FR 15015 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial Review

    Science.gov (United States)

    2013-03-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial Review The meeting announced below concerns Epidemiology, Prevention and Treatment of Influenza and other Respiratory...

  3. 77 FR 14806 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-03-13

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Epidemiology, Prevention and Treatment of Influenza and Other Respiratory...

  4. 78 FR 78966 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-12-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Epidemiology, Prevention, and Treatment of Influenza and Other Respiratory...

  5. 77 FR 4048 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-01-26

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Evaluation of Dengue Epidemiology, Outcomes, and Prevention in Sentinel...

  6. 77 FR 4047 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-01-26

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Epidemiology, Prevention and Treatment of Influenza and Other Respiratory...

  7. 78 FR 13677 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial Review

    Science.gov (United States)

    2013-02-28

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial Review The meeting announced below concerns Monitoring Cause-Specific School Absenteeism for Estimating Community Wide...

  8. 78 FR 60878 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Health Promotion and Disease Prevention Research Centers, Funding Opportunity...

  9. 77 FR 12844 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-03-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Detecting Emerging Vector- Borne Zoonotic Pathogens in Indonesia, Funding...

  10. 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

  11. Safety and Mission Assurance Knowledge Management Retention: Managing Knowledge for Successful Mission Operations

    Science.gov (United States)

    Johnson, Teresa A.

    2006-01-01

    Knowledge Management is a proactive pursuit for the future success of any large organization faced with the imminent possibility that their senior managers/engineers with gained experiences and lessons learned plan to retire in the near term. Safety and Mission Assurance (S&MA) is proactively pursuing unique mechanism to ensure knowledge learned is retained and lessons learned captured and documented. Knowledge Capture Event/Activities/Management helps to provide a gateway between future retirees and our next generation of managers/engineers. S&MA hosted two Knowledge Capture Events during 2005 featuring three of its retiring fellows (Axel Larsen, Dave Whittle and Gary Johnson). The first Knowledge Capture Event February 24, 2005 focused on two Safety and Mission Assurance Safety Panels (Space Shuttle System Safety Review Panel (SSRP); Payload Safety Review Panel (PSRP) and the latter event December 15, 2005 featured lessons learned during Apollo, Skylab, and Space Shuttle which could be applicable in the newly created Crew Exploration Vehicle (CEV)/Constellation development program. Gemini, Apollo, Skylab and the Space Shuttle promised and delivered exciting human advances in space and benefits of space in people s everyday lives on earth. Johnson Space Center's Safety & Mission Assurance team work over the last 20 years has been mostly focused on operations we are now beginning the Exploration development program. S&MA will promote an atmosphere of knowledge sharing in its formal and informal cultures and work processes, and reward the open dissemination and sharing of information; we are asking "Why embrace relearning the "lessons learned" in the past?" On the Exploration program the focus will be on Design, Development, Test, & Evaluation (DDT&E); therefore, it is critical to understand the lessons from these past programs during the DDT&E phase.

  12. 76 FR 32213 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP); Initial Review

    Science.gov (United States)

    2011-06-03

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP); Initial Review The meeting announced below concerns Human Immunodeficiency Virus (HIV) Prevention Projects for Young Men of Color...

  13. 77 FR 19018 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-03-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Conducting Public Health Research in South Africa, Funding Opportunity Announcement...

  14. 77 FR 39497 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-07-03

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Special Interest Projects (SIPs): Nutrition and Obesity Policy Research and...

  15. 78 FR 78964 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-12-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns The Cooperative Re-Engagement Controlled Trial (CoRECT), Funding Opportunity...

  16. 77 FR 39498 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-07-03

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Special Interest Project (SIP): Assessing the Pregnancy Prevention Needs of HIV...

  17. 76 FR 18555 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-04-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Virologic Evaluation of the Modes of Influenza Virus Transmission among Humans...

  18. 78 FR 35035 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial review

    Science.gov (United States)

    2013-06-11

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial review The meeting announced below concerns Centers for Disease Control and Prevention Public Health Preparedness and Response...

  19. 78 FR 17412 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-03-21

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Strengthening the Monitoring and Evaluation of Programs for the Elimination and...

  20. 78 FR 36785 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-06-19

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Centers for Disease Control and Prevention Public Health Preparedness and Response...

  1. 78 FR 1212 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-01-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Natural History and Prevention of Viral Hepatitis Among Alaska Natives, Funding...

  2. 78 FR 62636 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-10-22

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Cooperative Agreement on Occupational Health with the World Health Organization...

  3. 76 FR 29756 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-05-23

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Centers for Agricultural Disease and Injury Research, Education, and Prevention...

  4. 76 FR 67458 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-11-01

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Emerging Infections Programs, Funding Opportunity Announcement (FOA) CK12-1202...

  5. 78 FR 17410 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial review

    Science.gov (United States)

    2013-03-21

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panels (SEP): Initial review The meeting announced below concerns Epi-Centers for the Prevention of Healthcare-Associated Infections, Antimicrobial...

  6. 78 FR 37542 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-06-21

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns NIOSH Cooperative Agreement Research to Aid Recovery from Hurricane Sandy, Request...

  7. 78 FR 732 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-01-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Identification, Surveillance, and Control of Vector-Borne and Zoonotic Infectious...

  8. 76 FR 33305 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-06-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Program to Support New Implementation of State or Territorial Public Health...

  9. 78 FR 74175 - Meetings of Humanities Panel

    Science.gov (United States)

    2013-12-10

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to section 10(a)(2) of the... Humanities Panel will be held during January 2014 as follows. The purpose of the meetings is for panel review...

  10. 32 CFR 724.104 - NDRB Traveling Panel.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false NDRB Traveling Panel. 724.104 Section 724.104 National Defense Department of Defense (Continued) DEPARTMENT OF THE NAVY PERSONNEL NAVAL DISCHARGE REVIEW BOARD Definitions § 724.104 NDRB Traveling Panel. An NDRB Panel that travels for the purpose of...

  11. Review of Issues Associated with Safe Operation and Management of the Space Shuttle Program

    Science.gov (United States)

    Johnstone, Paul M.; Blomberg, Richard D.; Gleghorn, George J.; Krone, Norris J.; Voltz, Richard A.; Dunn, Robert F.; Donlan, Charles J.; Kauderer, Bernard M.; Brill, Yvonne C.; Englar, Kenneth G.; hide

    1996-01-01

    At the request of the President of the United States through the Office of Science and Technology Policy (OSTP), the NASA Administrator tasked the Aerospace Safety Advisory Panel with the responsibility to identify and review issues associated with the safe operation and management of the Space Shuttle program arising from ongoing efforts to improve and streamline operations. These efforts include the consolidation of operations under a single Space Flight Operations Contract (SFOC), downsizing the Space Shuttle workforce and reducing costs of operations and management. The Panel formed five teams to address the potentially significant safety impacts of the seven specific topic areas listed in the study Terms of Reference. These areas were (in the order in which they are presented in this report): Maintenance of independent safety oversight; implementation plan for the transition of Shuttle program management to the Lead Center; communications among NASA Centers and Headquarters; transition plan for downsizing to anticipated workforce levels; implementation of a phased transition to a prime contractor for operations; Shuttle flight rate for Space Station assembly; and planned safety and performance upgrades for Space Station assembly. The study teams collected information through briefings, interviews, telephone conversations and from reviewing applicable documentation. These inputs were distilled by each team into observations and recommendations which were then reviewed by the entire Panel.

  12. Genotoxicity Expert Panel review: weight of evidence evaluation of the genotoxicity of glyphosate, glyphosate-based formulations, and aminomethylphosphonic acid.

    Science.gov (United States)

    Brusick, David; Aardema, Marilyn; Kier, Larry; Kirkland, David; Williams, Gary

    2016-09-01

    In 2015, the International Agency for Research on Cancer (IARC) published a monograph concluding there was strong evidence for genotoxicity of glyphosate and glyphosate formulations and moderate evidence for genotoxicity of the metabolite aminomethylphosphonic acid (AMPA). These conclusions contradicted earlier extensive reviews supporting the lack of genotoxicity of glyphosate and glyphosate formulations. The IARC Monograph concluded there was strong evidence of induction of oxidative stress by glyphosate, glyphosate formulations, and AMPA. The Expert Panel reviewed the genotoxicity and oxidative stress data considered in the IARC Monograph, together with other available data not considered by IARC. The Expert Panel defined and used a weight of evidence (WoE) approach that included ranking of studies and endpoints by the strength of their linkage to events associated with carcinogenic mechanisms. Importantly, the Expert Panel concluded that there was sufficient information available from a very large number of regulatory genotoxicity studies that should have been considered by IARC. The WoE approach, the inclusion of all relevant regulatory studies, and some differences in interpretation of individual studies led to significantly different conclusions by the Expert Panel compared with the IARC Monograph. The Expert Panel concluded that glyphosate, glyphosate formulations, and AMPA do not pose a genotoxic hazard and the data do not support the IARC Monograph genotoxicity evaluation. With respect to carcinogenicity classification and mechanism, the Expert Panel concluded that evidence relating to an oxidative stress mechanism of carcinogenicity was largely unconvincing and that the data profiles were not consistent with the characteristics of genotoxic carcinogens.

  13. 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

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

    Directory of Open Access Journals (Sweden)

    Emily Gartshore

    2017-11-01

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

  15. 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

  16. Building on the Past - Looking to the Future: A Focus on Payload Safety

    Science.gov (United States)

    Nash, Sally K.; Rehm, Raymond B.; Samtoagp. Darren M.; Wong, Teresa K.; Wolf, Scott L.

    2008-01-01

    The history of the space industry stretches far and above lunar landings to the construction of the International Space Station. For years, humans have sought to understand the nature of the universe. As society grows in knowledge and curiosity of space, the focus of maintaining the safety of the crew and vehicle habitability is of utmost importance to the National Aeronautics and Space Administration (NASA) community. Through the years, Payload Safety has developed not only as a Panel, but also as part of the NASA community, striving to enhance the efficiency and understanding of how business should be conducted as more International Partners become involved. This is the first in a series of papers and presentations in what is hoped to be an annual update that provides continuous challenges and lessons learned in the areas of communication, safety requirements and processes and other areas which have been vital to the Payload Safety Review Panel (PSRP).

  17. 77 FR 291 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-01-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns National HIV Behavioral Surveillance For Young Men Who Have Sex With Men, Funding...

  18. 77 FR 30015 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-05-21

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Characterizing the Short and Long Term Consequences of Traumatic Brain Injury (TBI...

  19. 76 FR 33304 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-06-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Strategies to Improve Vaccination Coverage of Children in Child Care Centers (CCCs...

  20. 77 FR 22326 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Extension of the World Trade Center Health Registry (U50) Request for Applications...

  1. 77 FR 25181 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-04-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Research Technical Assistance To The Ministry Of Public Health Of Haiti To Support...

  2. 76 FR 24031 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-04-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Strategies to Improve Vaccination Coverage of Children in Child Care Centers (CCCs...

  3. 76 FR 39879 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-07-07

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Human Immunodeficiency Virus (HIV) Prevention Projects for Young Men of Color Who...

  4. 77 FR 27460 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-05-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Conducting Public Health Research in China RFA GH-12-005, and Conducting Public...

  5. 76 FR 59133 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-09-23

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Human Immunodeficiency Virus (HIV) Prevention Projects for Young Men of Color Who...

  6. 78 FR 9926 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-02-12

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Medicaid Expansion and Reproductive Health Care for Women, FOA DP 13-002, initial...

  7. 78 FR 17411 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-03-21

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Monitoring and Evaluation of Malaria Control and Elimination Activities, FOA GH13...

  8. 76 FR 45575 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2011-07-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Human Immunodeficiency Virus (HIV) Prevention Projects for Young Men of Color Who...

  9. 77 FR 36544 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2012-06-19

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting announced below concerns Coordinating Center for Research and Training to Promote the Health of People with...

  10. 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

  11. Stakeholders' Perspectives About and Priorities for Economic Evaluation of Health and Safety Programs in Healthcare.

    Science.gov (United States)

    Tompa, Emile; de Boer, Henriette; Macdonald, Sara; Alamgir, Hasanat; Koehoorn, Mieke; Guzman, Jaime

    2016-04-01

    This study identified and prioritized resources and outcomes that should be considered in more comprehensive and scientifically rigorous health and safety economic evaluations according to healthcare sector stakeholders. A literature review and stakeholder interviews identified candidate resources and outcomes and then a Delphi panel ranked them. According to the panel, the top five resources were (a) health and safety staff time; (b) training workers; (c) program planning, promotion, and evaluation costs; (d) equipment purchases and upgrades; and (e) administration costs. The top five outcomes were (a) number of injuries, illnesses, and general sickness absences; (b) safety climate; (c) days lost due to injuries, illnesses, and general sickness absences; (d) job satisfaction and engagement; and (e) quality of care and patient safety. These findings emphasize stakeholders' stated priorities and are useful as a benchmark for assessing the quality of health and safety economic evaluations and the comprehensiveness of these findings. © 2016 The Author(s).

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

    International Nuclear Information System (INIS)

    Rzentkowski, G.

    2016-01-01

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

  13. 78 FR 19269 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-03-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review Notice of Cancellation: This document corrects a notice that was published in the Federal Register on March 21, 2013 (78...

  14. 78 FR 66938 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-11-07

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review Notice of..., Number 181, Page 57391). This SEP, scheduled to convene on November 12-15, 2013, is canceled. Notice will...

  15. 78 FR 19490 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-04-01

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review Notice of Cancellation: A notice was published in the Federal Register on February 12, 2013, Volume 78, Number 29, page...

  16. 78 FR 66937 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-11-07

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review Notice of... Volume 78, Number 191, Page 60877). This SEP, scheduled to convene on November 6, 2013, is canceled...

  17. 78 FR 23768 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-04-22

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting... Centers for Disease Control and Prevention (CDC) announces the aforementioned SEP: Time and Date: 1:00 p.m...

  18. 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

  19. 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.

  20. Quo Vadis Payload Safety?

    Science.gov (United States)

    Fodroci, Michael P.; Schwartz, MaryBeth

    2008-01-01

    As we complete the preparations for the fourth Hubble Space Telescope (HST) servicing mission, we note an anniversary approaching: it was 30 years ago in July that the first HST payload safety review panel meeting was held. This, in turn, was just over a year after the very first payload safety review, a Phase 0 review for the Tracking and Data Relay Satellite and its Inertial Upper Stage, held in June of 1977. In adapting a process that had been used in the review and certification of earlier Skylab payloads, National Aeronautics and Space Administration (NASA) engineers sought to preserve the lessons learned in the development of technical payload safety requirements, while creating a new process that would serve the very different needs of the new space shuttle program. Their success in this undertaking is substantiated by the fact that this process and these requirements have proven to be remarkably robust, flexible, and adaptable. Furthermore, the payload safety process has, to date, served us well in the critical mission of safeguarding our astronauts, cosmonauts, and spaceflight participants. Both the technical requirements and their interpretation, as well as the associated process requirements have grown, evolved, been streamlined, and have been adapted to fit multiple programs, including the International Space Station (ISS) program, the Shuttle/Mir program, and most recently the United States Constellation program. From its earliest days, it was anticipated that the payload safety process would be international in scope, and so it has been. European Space Agency (ESA), Japan Aerospace Exploration Agency (JAXA), German Space Agency (DLR), Canadian Space Agency (CSA), Russian Space Agency (RSA), and many additional countries have flown payloads on both the space shuttle and on the ISS. Our close cooperation and long-term working relationships have culminated in the franchising of the payload safety review process itself to our partners in ESA, which in

  1. 45 CFR 1801.22 - Interview of Finalists with panel.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Interview of Finalists with panel. 1801.22 Section... FOUNDATION HARRY S. TRUMAN SCHOLARSHIP PROGRAM The Competition § 1801.22 Interview of Finalists with panel. The Foundation invites each Finalist to an interview with a regional review panel. Panels evaluate...

  2. 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

  3. 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.

  4. 78 FR 24751 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-04-26

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting... Control and Prevention (CDC) announces the aforementioned SEP: Time and Date: 12:00 p.m.-3:30 p.m., June...

  5. 78 FR 28221 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-05-14

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting... aforementioned SEP: Time and Date: 12:30 p.m.-5:00 p.m. EDT, July 24, 2013 (Closed). Place: Teleconference...

  6. 78 FR 57391 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review

    Science.gov (United States)

    2013-09-18

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review The meeting... aforementioned SEP: Times and Dates: 8:00 a.m.-8:00 p.m., November 12-15, 2013 (Closed). Place: Teleconference...

  7. Exascale Workshop Panel Report Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Khaleel, Mohammad A.

    2010-07-01

    The Exascale Review Panel consists of 12 scientists and engineers with experience in various aspects of high-performance computing and its application, development, and management. The Panel hear presentations by several representatives of the workshops and town meetings convened over the past few years to examine the need for exascale computation capability and the justification for a U.S. Department of Energy (DOE) program to develop such capability. This report summarizes information provided by the presenters and substantial written reports to the Panel in advance of the meeting in Washington D.C. on January 19-20, 2010. The report also summarizes the Panel's conclusions with regard to the justification of a DOE-led exascale initiative.

  8. 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...

  9. 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

  10. 78 FR 20319 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review.

    Science.gov (United States)

    2013-04-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel (SEP): Initial Review. The meeting... aforementioned SEP: Time and Date: 9:00 a.m.-6:00 p.m., May 15-16, 2013 (Closed). Place: Georgian Terrace, 659...

  11. 2008 DOE Hydrogen Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2008-06-13

    This report summarizes comments from the Peer Review Panel at the 2008 DOE Hydrogen Program Annual Merit Review, held on June 9-13, 2008, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; technology validation; safety, codes, and standards; education; systems analysis; and manufacturing.

  12. Federal Government response to the September 12, 2000 environmental assessment report of the EUB-CEAA Joint Review Panel on the Cheviot Coal Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-04-01

    The Federal Court noted four deficiencies in the joint EUB-CEAA environmental review dated September 12, 2000 for the Cheviot Coal Project. The Joint Review Panel reconvened to hear additional evidence about these deficiencies. This memorandum to cabinet comprises the Government of Canada's response to the additional evidence. Some of the Panel's recommendations are accepted. Comments are included regarding migratory birds, protection of traditional aboriginal sites, economic benefits, grizzly bears, and fish habitat.

  13. Panel 3: Genetics and Precision Medicine of Otitis Media.

    Science.gov (United States)

    Lin, Jizhen; Hafrén, Hena; Kerschner, Joseph; Li, Jian-Dong; Brown, Steve; Zheng, Qing Y; Preciado, Diego; Nakamura, Yoshihisa; Huang, Qiuhong; Zhang, Yan

    2017-04-01

    Objective The objective is to perform a comprehensive review of the literature up to 2015 on the genetics and precision medicine relevant to otitis media. Data Sources PubMed database of the National Library of Medicine. Review Methods Two subpanels were formed comprising experts in the genetics and precision medicine of otitis media. Each of the panels reviewed the literature in their respective fields and wrote draft reviews. The reviews were shared with all panel members, and a merged draft was created. The entire panel met at the 18th International Symposium on Recent Advances in Otitis Media in June 2015 and discussed the review and refined the content. A final draft was made, circulated, and approved by the panel members. Conclusion Many genes relevant to otitis media have been identified in the last 4 years in advancing our knowledge regarding the predisposition of the middle ear mucosa to commensals and pathogens. Advances include mutant animal models and clinical studies. Many signaling pathways are involved in the predisposition of otitis media. Implications for Practice New knowledge on the genetic background relevant to otitis media forms a basis of novel potential interventions, including potential new ways to treat otitis media.

  14. 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

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

    International Nuclear Information System (INIS)

    2013-01-01

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

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

    International Nuclear Information System (INIS)

    2004-01-01

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

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

    International Nuclear Information System (INIS)

    2005-01-01

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

  18. Nuclear fuel waste management and disposal concept: Report. Federal environmental assessment review process

    International Nuclear Information System (INIS)

    1998-01-01

    The Canadian concept for disposing CANDU reactor waste or high-level nuclear wastes from reprocessing involves underground disposal in sealed containers emplaced in buffer-filled and sealed vaults 500--1,000 meters below ground, in plutonic rock of the Canadian Shield. This document presents the report of a panel whose mandate was to review this concept (rather than a specific disposal project at a specific site) along with a broad range of related policy issues, and to conduct that review in five provinces (including reviews with First Nations groups). It first outlines the review process and then describes the nature of the problem of nuclear waste management. It then presents an overview of the concept being reviewed, its implementation stages, performance assessment analyses performed on the concept, and implications of a facility based on that concept (health, environmental, social, transportation, economic). The fourth section examines the criteria by which the safety and acceptability of the concept should be evaluated. This is followed by a safety and acceptability evaluation from both technical and social perspectives. Section six proposes future steps for building and determining acceptability of the concept, including an Aboriginal participation process, creation of a Nuclear Fuel Waste Management Agency, and a public participation process. The final section discusses some issues outside the panel's mandate, such as energy policy and renewable energy sources. Appendices include a chronology of panel activities, a review of radiation hazards, comparison between nuclear waste management and the management of other wastes, a review of other countries' approaches to long-term management of nuclear fuel wastes, and details of a siting process proposed by the panel

  19. 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.

  20. 76 FR 28781 - Independent Scientific Peer Review Panel Report: Evaluation of the Validation Status of an In...

    Science.gov (United States)

    2011-05-18

    ... Scientific Advisory Committee on Alternative Toxicological Methods (SACATM) recommended that the BG1Luc ER TA... DEPARTMENT OF HEALTH AND HUMAN SERVICES Independent Scientific Peer Review Panel Report: Evaluation of the Validation Status of an In Vitro Estrogen Receptor Transcriptional Activation Test Method...

  1. 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

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

    International Nuclear Information System (INIS)

    2011-01-01

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

  3. 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

  4. The comparison of road safety survey answers between web-panel and face-to-face; Dutch results of SARTRE-4 survey.

    Science.gov (United States)

    Goldenbeld, C; de Craen, S

    2013-09-01

    In the Netherlands, a comparison of an online and a face-to-face sample of car drivers was made to study differences on a number of selected questions from the SARTRE-4 road safety survey. Contrary to expectations, there was no indication that online respondents were more likely to come from higher educated or more privileged social groups. Confirming earlier research, the results indicated that online respondents were less inclined to give socially desirable answers and were less inclined to use more extreme ratings in their opinions about measures. Contrary to expectations, face-to-face respondents did not tend to give more positive answers in judgment of road safety measures. Weighting to make samples comparable on gender, age, and education had almost no effect on outcomes. The implications for a transition from face-to-face survey to online panel method are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  5. 2010 DOE Hydrogen Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-12-01

    This report summarizes comments from the Peer Review Panel at the 2010 DOE Hydrogen Program Annual Merit Review, held on June 7-11, 2010, in Washington, DC. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; education; and systems analysis.

  6. 2009 DOE Hydrogen Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    Satyapal, S. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

    2009-10-01

    This report summarizes comments from the Peer Review Panel at the 2009 DOE Hydrogen Program Annual Merit Review, held on May 18-22, 2009, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; education; safety, codes, and standards; technology validation; systems analysis; and manufacturing R&D.

  7. 1994 Panel 1 Utilization Plan

    International Nuclear Information System (INIS)

    1994-01-01

    The Waste Isolation Pilot Plant (WIPP) is intended to receive, handle, and permanently dispose of transuranic (TRU) waste. To fulfill this mission, the U.S. Department of Energy (DOE) constructed a full-scale facility to demonstrate both technical and operational principles of the permanent isolation of TRU waste. The WIPP consists of surface and underground facilities. Panel 1 is situated in the underground facility horizon which is located approximately 2,150 feet below the surface in the predominantly halite Salado Formation. The Panel 1 Utilization Plan provides a strategy for the optimum use of Panel 1 which is consistent with the priorities established by the DOE to accomplish the WIPP mission. These priorities, which include maintaining personnel safety, conducting performance assessment, and continued operational enhancements, are the guiding premise for the decisions on the planned usage of the WIPP underground facility. The continuation of ongoing investigations along with the planned testing and training to be carried out in Panel 1 will enhance the current knowledge and understanding of the operational and geotechnical aspects of the panel configuration. This enhancement will ultimately lead to safer, more efficient, and more cost-effective methods of operation. Excavation of the waste storage area began in May 1986 with the mining of entries to Panel 1. The original design for the waste storage rooms at the WIPP provided a limited period of time during which to mine the openings and to emplace waste. Each panel, consisting of seven storage rooms, was scheduled to be mined and filled in less than 5 years. Panel 1 was developed to receive waste for a demonstration phase that was scheduled to start in October 1988. The demonstration phase was deferred, and the experimental test program was modified to use contact-handled (CH) transuranic waste in bin-scale tests, planned for Room 1, Panel 1

  8. 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

  9. The development of an Infrared Environmental System for TOPEX Solar Panel Testing

    Science.gov (United States)

    Noller, E.

    1994-01-01

    Environmental testing and flight qualification of the TOPEX/POSEIDON spacecraft solar panels were performed with infrared (IR) lamps and a control system that were newly designed and integrated. The basic goal was more rigorous testing of the costly panels' new composite-structure design without jeopardizing their safety. The technique greatly reduces the costs and high risks of testing flight solar panels.

  10. 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.

  11. Status report : Terra Nova project environmental assessment panel : recommendations

    International Nuclear Information System (INIS)

    2002-01-01

    An application to the Canada-Newfoundland Offshore Petroleum Board (CNOPB) was submitted by Petro-Canada on August 5, 1996, notifying of its intent to develop the petroleum resources located at the Terra Nova field. The provincial and federal governments jointly appointed the Terra Nova Project Environmental Panel, and the board of the CNOPB referred to it the application documents for review. The environmental effects, considerations of human safety incorporated into the design and operation of the Project, the general approach to the development and exploitation of the petroleum resources, and the employment and industrial benefits expected to be derived from the Project were the issues under review by the Panel. On April 22, 1997, public hearings into the review began, and the final report was submitted to governments and the Board in August 1997. The report included 75 recommendations. The Project was approved in Decision 97.02 in December 1997, and the Board dealt with each of the recommendations. The respective positions of the Governments of Canada and Newfoundland and Labrador with regard to the recommendations that fell outside the jurisdiction of the Board were made public. A status report on every one of the 75 recommendations is provided in the present report. The recommendation is repeated, the verbatim response taken from Decision 97.02 included, followed by the status of the response. The production operations phase of the Project accounts for approximately 65 per cent of the recommendations. January 20, 2002 was the date the Project was begun

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  14. 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)

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

    International Nuclear Information System (INIS)

    Dverstorp, Bjoern; Stroemberg, Bo

    2008-03-01

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

  16. 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

  17. 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

  18. 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.

  19. 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...

  20. 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...

  1. 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

  2. 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

  3. 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)

  4. 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)

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

    International Nuclear Information System (INIS)

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

    2008-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-02-15

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

  7. Occupational mental health promotion: a prevention agenda based on education and treatment. The American Psychological Association/National Institute for Occupational Safety and Health, Health Promotion Panel, 1990 Work and Well-Being Conference.

    Science.gov (United States)

    1992-01-01

    PURPOSE OF THE REVIEW. Psychological disorders are one of the 10 leading work-related diseases and injuries in the United States according to the National Institute for Occupational Safety and Health. This article addresses occupational metal health and preventive stress management in the workplace. The individual and organizational costs are briefly considered with concern for reducing the burden of suffering associated with these problems. SEARCH METHOD. As an American Psychological Association interdisciplinary panel, we searched the psychological, medical, public health, and organizational literature. We selected articles relevant to the problem of psychological disorders in the workplace and to enhancing occupational mental health and preventive stress management. IMPORTANT FINDINGS. The panel proposed a national agenda of education and treatment, combined with a program of evaluation research, for addressing these issues. Target populations are identified, and the need for collaboration among a variety of national constituencies is considered. Advancing occupational mental health and promoting skills in preventive stress management is considered in the context of comprehensive health promotion. MAJOR CONCLUSIONS. The panel concluded that there is a pressing need to: 1) set a 'gold' standard concerning the current state of knowledge in the domains of occupational mental health and stress management; 2) identify Diagnostically Related Groups (DRGs) which are stress-related; 3) establish assessment standards for stress and mental health; 4) set guidelines for reasonable interventions; and 5) establish acceptable post-outcome criteria.

  8. INTERNATIONAL COLLABORATION: Panelling

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    At the meeting of the International Committee for Future Accelerators (ICFA), in Geneva in July, Chairman A.N. Skrinsky of Novosibirsk reviewed ICFA progress, particularly the activities of the specialist Panels which pursue specific Committee objectives in guiding worldwide collaboration in high energy physics

  9. INTERNATIONAL COLLABORATION: Panelling

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1991-10-15

    At the meeting of the International Committee for Future Accelerators (ICFA), in Geneva in July, Chairman A.N. Skrinsky of Novosibirsk reviewed ICFA progress, particularly the activities of the specialist Panels which pursue specific Committee objectives in guiding worldwide collaboration in high energy physics.

  10. 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

  11. 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

  12. Report of the review panel on neutron scattering

    International Nuclear Information System (INIS)

    1980-01-01

    This panel finds that neutron scattering continues to play a central role in advanced research in the materials sciences. The US research in this field has made broad and outstanding contributions to materials science, but has fallen far behind the rest of the industrialized world in the funding of such research. The steady-state reactors, HFBR at Brookhaven National Laboratory and the HFIR at Oak Ridge National Laboratory will be the mainstays of our neutron scattering research programs for at least the next decade. However, the constant level of funding of these two facilities during the 1970's has not allowed the kind of instrumentation and innovation necessary for continued vitality. The panel concludes that a plan for the systematic development of this field would provide for the enhanced funding and development of the two reactor sources and both pulsed sources, and the panel strongly urges DOE to provide this level of funding, or at least ensure the vitality of the steady-state sources and the funding by BES of the WNR/PSR request

  13. 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...

  14. IAEA Operational Safety Team Reviews Saint-Alban Nuclear Power Plant, France

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed safety practices at France's Saint-Alban Nuclear Power Plant (NPP) and has highlighted a set of strong practices as well as a series of recommendations to reinforce them. The IAEA assembled the team at the request of the Government of France to conduct an Operational Safety Review (OSART) of the Saint-Alban NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review from 20 September to 6 October 2010. The team was made up of experts from Belgium, Canada, the Czech Republic, Germany, Lithuania, the Netherlands, Slovakia, Sweden and the USA. An OSART mission is designed to review programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Saint-Alban conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely are under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: A safety guideline for outages; The use of remote video surveillance of fuel inspection and handling activities; A motivational tool for plant staff regarding the benefits of operating experience and associated corrective actions; and Use of a sophisticated key control system

  15. IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

  16. Needs for evidence-based road safety decision making in Europe.

    NARCIS (Netherlands)

    Dupont, E. Muhlrad, N. Buttler, I. Gitelman, V. Giustiniani, G. Jähi, H. Machata, K. Martensen, H. Papadimitriou, E. Persia, L. Talbot, R. Vallet, G. Wijnen, W. & Yannis, G.

    2012-01-01

    The objective of this research is the assessment of current needs for evidence-based road safety decision making in Europe, through the consultation of a panel of road safety experts. The members of this Experts Panel have extensive knowledge of road safety management processes and needs in their

  17. EFSA Panel on Dietetic Products, Nutrition and Allergi es (NDA) ; Scientific Opinion - Statement on the safety of the “conjugated linoleic acid (CLA) - rich oils” Clarinol ® and Tonalin TG 80 as Novel Food ingredients

    DEFF Research Database (Denmark)

    Tetens, Inge

    that the additional information provided does not contain evidence thath would modify its previous conclusions regarding the effects of CLA on insulin sensitivity/glucose metabolism, blood lipids, lipid peroxidation, or subclinical inflammation. The Panel also considers that the new studies provided do not address......Following a request from the European Commission, the Panel on Dietetic Products, Nutrition and Allergies was asked to update its opinions on the safety of the conjugated linoleic acid (CLA)-rich oils Clarinol® and Tonalin® TG 80 as Novel Food ingredients in the light of additional information...... uses and daily doses for up to six months. The safety of CLA consumption for periods longer than six months has not been established under the proposed conditions of use. The safety of CLA consumption by type-2 diabetic subjects has not been established. © European Food Safety Authority, 2012...

  18. 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...

  19. 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)

  20. BWR plant advanced central control panel PODIA

    International Nuclear Information System (INIS)

    Fujii, K.; Hayakawa, H.; Ikeda, Y.; Neda, T.; Suto, O.; Takamiya, S.

    1983-01-01

    BWR plant central control panels have become more and more enlarged and complicated recently due to the magnification of the scale of a plant and the requirement to reinforce safety. So, it is important to make communication between men and the complicated central control panel smooth. Toshiba has developed an advanced central control panel, named PODIA, which uses many computers and color CRTs, and PODIA is now in the stage of application to practical plants. In this article, the writers first touch upon control functions transition in the central control room, the PODIA position concerning the world-wide trend in this technology phase and the human engineering on the design. Then they present concrete design concepts for the control board and computer system which constitute PODIA

  1. 75 FR 69069 - Science Advisory Board Staff Office Notification of a Public Meeting of the SAB Lead Review Panel

    Science.gov (United States)

    2010-11-10

    ... Time) and December 7, 2010 from 8:30 a.m. to 12:30 p.m. (Eastern Time). ADDRESSES: The face-to-face... SAB Lead Review Panel will hold a public face-to-face meeting to peer review two draft EPA documents... an oral presentation at a public face-to-face meeting will be limited to five minutes, with no more...

  2. 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.

  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. 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)

  5. Review of flat panel display programs and defense applications

    Science.gov (United States)

    Gnade, Bruce; Schulze, Raymond; Henderson, Girardeau L.; Hopper, Darrel G.

    1997-07-01

    Flat panel display research has comprised a substantial portion of the national investment in new technology for economic and national security for the past nine years. These investments have ben made principally via several Defense Advanced Research Projects Agency (DARPA) programs, known collectively as the continuing High Definition Systems Program, and the Office of the Secretary of Defense Production Act Title III Program. Using input from the Army, Navy, and Air Force to focus research and identify insertion opportunities, DARPA and the Title III Program Office have made investments to develop the national technology base and manufacturing infrastructure necessary to meet the twin challenge of providing affordable displays in current systems and enabling the DoD strategy of winning future conflicts by getting more information to all participants during the battle. These research programs are reviewed and opportunities for applications are described. Future technology development, transfer, and transition requirements are identified. Strategy and vision are documented to assist the identification of areas meriting further consideration.

  6. 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.)

  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. Patient participation in patient safety and nursing input - a systematic review.

    Science.gov (United States)

    Vaismoradi, Mojtaba; Jordan, Sue; Kangasniemi, Mari

    2015-03-01

    This systematic review aims to synthesise the existing research on how patients participate in patient safety initiatives. Ambiguities remain about how patients participate in routine measures designed to promote patient safety. Systematic review using integrative methods. Electronic databases were searched using keywords describing patient involvement, nursing input and patient safety initiatives to retrieve empirical research published between 2007 and 2013. Findings were synthesized using the theoretical domains of Vincent's framework for analysing risk and safety in clinical practice: "patient", "healthcare provider", "task", "work environment", "organisation & management". We identified 17 empirical research papers: four qualitative, one mixed-method and 12 quantitative designs. All 17 papers indicated that patients can participate in safety initiatives. Improving patient participation in patient safety necessitates considering the patient as a person, the nurse as healthcare provider, the task of participation and the clinical environment. Patients' knowledge, health conditions, beliefs and experiences influence their decisions to engage in patient safety initiatives. An important component of the management of long-term conditions is to ensure that patients have sufficient knowledge to participate. Healthcare providers may need further professional development in patient education and patient care management to promote patient involvement in patient safety, and ensure that patients understand that they are 'allowed' to inform nurses of adverse events or errors. A healthcare system characterised by patient-centredness and mutual acknowledgement will support patient participation in safety practices. Further research is required to improve international knowledge of patient participation in patient safety in different disciplines, contexts and cultures. Patients have a significant role to play in enhancing their own safety while receiving hospital care. This

  9. A LITERATURE REVIEW ON GLOBAL OCCUPATIONAL SAFETY AND HEALTH PRACTICE & ACCIDENTS SEVERITY

    Directory of Open Access Journals (Sweden)

    Kassu Jilcha

    2016-06-01

    Full Text Available This literature review focuses on researches undertaken since 1980s onwards. The purpose of the study is to identify existing gaps on workplace safety and health management and propose future research areas. The review adds value to existing electronic database through integration of researches' results. To identify existing gaps, a systematic literature review approach has been used. The reviews were undertaken through keywords and safety related topics. In the literature, various characteristics of workplace safety and health problems were found emanating from the lack of operational activities of the employees, internal working environment and external environment those impose hazards on employee temporarily, permanently and on working environments. The integration of multidisciplinary approaches and collaborative model of hub and peripheral industries to protect workplace safety hazards to develop multilevel model has been undermined in many researches. The other face of finding is that knowledge transfer mechanism and industrial topology factors are left. Some researches finding showed that they have focused on single problems related to health and health factors leaving universal improving workplace safety. In general, this literature reviews compare various studies output based on their research method and findings to fills gap and add value to a body of knowledge.

  10. Development of a Safety Management Web Tool for Horse Stables.

    Science.gov (United States)

    Leppälä, Jarkko; Kolstrup, Christina Lunner; Pinzke, Stefan; Rautiainen, Risto; Saastamoinen, Markku; Särkijärvi, Susanna

    2015-11-12

    Managing a horse stable involves risks, which can have serious consequences for the stable, employees, clients, visitors and horses. Existing industrial or farm production risk management tools are not directly applicable to horse stables and they need to be adapted for use by managers of different types of stables. As a part of the InnoEquine project, an innovative web tool, InnoHorse, was developed to support horse stable managers in business, safety, pasture and manure management. A literature review, empirical horse stable case studies, expert panel workshops and stakeholder interviews were carried out to support the design. The InnoHorse web tool includes a safety section containing a horse stable safety map, stable safety checklists, and examples of good practices in stable safety, horse handling and rescue planning. This new horse stable safety management tool can also help in organizing work processes in horse stables in general.

  11. Second review meeting of the Contracting Parties to the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Rafferty, Barbara

    2002-01-01

    The Second Review Meeting of the Contracting Parties to the Convention on Nuclear Safety was held in the Headquarters of the International Atomic Energy Agency in Vienna from 15-26 April 2002, under the chairmanship of the President, Mr Miroslav Gregoric, Director of the Slovenian Nuclear Safety Authority. The Convention on Nuclear Safety entered into force in October 1996, has been signed by sixty-five States and ratified by fifty-four, bringing within its scope 428 of the 448 nuclear reactors worldwide. The Convention aims to achieve and maintain a high level of nuclear safety worldwide, through inter alia enhancement of national measures and international co-operation. Obligations on Contracting Parties in accordance with the Convention include: the establishment and maintenance of a legislative and regulatory framework to govern the safety of land-based civil nuclear installations; the allocation of adequate financial and human resources to support the safety objectives; ensuring that all reasonably practicable improvements to safety are made as a matter of urgency. Adherence to this Convention entails two basic commitments by each Contracting Party: to prepare and make available a national report for review; and to subject its national report to a peer review by the other Contracting Parties. Thus, being a Contracting Party to this Convention involves: including in the national report a self-assessment of steps and measures already taken and in progress to implement the Convention obligations; taking an active part in an open and transparent review of its national report and the Reports of other Contracting Parties; and a commitment to a continuous learning and improving process, something which is a key element of a strong safety culture. The peer review of national reports takes place every three years, the first having been held in 1999. The Second Review Meeting was attended by delegates from 46 contracting parties. During the review certain issues were

  12. 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

  13. 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

  14. 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

  15. 77 FR 76001 - Hydrographic Services Review Panel

    Science.gov (United States)

    2012-12-26

    ... disciplines and fields relating to hydrographic data and hydrographic services, marine transportation, port... represented on the Panel and encourages individuals with expertise in navigation data, products and services... variety of other data in order to fulfill this responsibility. The HSRP provides advice on current and...

  16. 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.

  17. A Review of Traditional and Novel Treatments for Seizures in Autism Spectrum Disorder: Findings from a Systematic Review and Expert Panel

    OpenAIRE

    Frye, Richard E.; Rossignol, Daniel; Casanova, Manuel F.; Brown, Gregory L.; Martin, Victoria; Edelson, Stephen; Coben, Robert; Lewine, Jeffrey; Slattery, John C.; Lau, Chrystal; Hardy, Paul; Fatemi, S. Hossein; Folsom, Timothy D.; MacFabe, Derrick; Adams, James B.

    2013-01-01

    Despite the fact that seizures are commonly associated with autism spectrum disorder (ASD), the effectiveness of treatments for seizures has not been well studied in individuals with ASD. This manuscript reviews both traditional and novel treatments for seizures associated with ASD. Studies were selected by systematically searching major electronic databases and by a panel of experts that treat ASD individuals. Only a few anti-epileptic drugs (AEDs) have undergone carefully controlled trials ...

  18. 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

  19. 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

  20. 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)

  1. Control room, emergency control system and local control panels in nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    The requirements on planning and construction of control boards including ergonomic-technical designing are specified in this rule. The specifications put the requirements on the design of place, process and environment of work, which are mentioned in the sections 90 and 91 of the labor-management relations act, into more concrete terms for the safety-relevant control panels as work places in a nuclear power station. The work places at control panels are not considered as video workstations in the sense of the 'Safety Rules for Video Workstations in the Office Sector' published by the General Association of the Industrial Trade Associations. The requirements are based on the operation and information technology realized at present in control panels of stationary nuclear power plants. (orig./HP) [de

  2. Human Research Program Human Health Countermeasures Element Nutrition Risk Standing Review Panel

    Science.gov (United States)

    Bistrian, Bruce

    2009-01-01

    The Nutrition Risk Standing Review Panel (SRP) reviewed and discussed the specific gaps and tasks for the Human Health Countermeasures (HHC) Element related to nutrition identified in the Human Research Program (HRP) Integrated Research Plan. There was general consensus that the described gaps and proposed tasks were critical to future NASA mission success. The SRP acknowledged the high scientific quality of the work currently being undertaken by the Nutritional Biochemistry group under the direction of Dr. Scott Smith. In review of the entire HRP, four new gaps were identified that complement the Element's existing research activities. Given the limitations of ground-based analogs for many of the unique physiological and metabolic alterations in space, future studies are needed to quantify nutritional factors that change during actual space flight. In addition, future tasks should seek to better evaluate the time course of physiological and metabolic alterations during flight to better predict alterations during longer duration missions. Finally, given the recent data suggesting a potential role for increased inflammatory responses during space flight, the role of inflammation needs to be explored in detail, including the development of potential countermeasures and new ground based analogs, if this possibility is confirmed.

  3. TWRS vadose zone contamination issue expert panel report

    Energy Technology Data Exchange (ETDEWEB)

    Shafer, D.S.

    1997-05-01

    When members were first canvassed for participation in the Vadose Zone Expert Panel the stated purpose for convening the Panel was to review a controversial draft report, the SX Tank Farm Report. This report was produced by a DOE Grand Junction Project Office (GJPO) contractor, RUST Geotech, now MACTEC-ERS, for the DOE Richland Office (DOERL). Three meetings were planned for June, July and August, 1995 to review the draft report and to complete a Panel report by mid-September. The Expert Panel has found its efforts confounded by various non-technical issues. The Expert Panel has chosen to address some of the non-technical issues in this Preface rather than to dilute the technical discussion that follows in the body of this independent expert panel status report (Panel Report). Rather than performing a straightforward manuscript review, the Panel was asked to resolve conflicting interpretations of gamma-ray logging measurements performed in vadose zone boreholes (drywells) surrounding the high-level radioactive wastes of the SX tank farm. There are numerous and complex technical issues that must be evaluated before the vertical and radial extent of contaminant migration at the SX tank farm can be accurately assessed. When the Panel first met in early June, 1996, it quickly became apparent that the scientific and technical issues were obscured by policy and institutional affairs which have polarized discussion among various segments of the Hanford organization. This situation reflects the kinds of institutional problems described separately in reports by the National Research Council of the National Academy of Sciences (NAS/NRC), The Hanford Tanks Environmental Impacts and Policy Choices and BmTiers to Science: Technical Management of the Department of Energy Environmental Remediation Program. The Vadose Zone Characterization Program, appears to be caught between conflicting pressures and organizational mandates, some imposed from outside DOE-RL and some self

  4. 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

  5. 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.

  6. International experts conclude IAEA peer review of Iran's safety regulation of Bushehr NPP

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of nuclear safety experts today completed an IAEA mission to review the effectiveness of Iran's safety regulation of its first nuclear power plant and to identify possible improvements before the plant begins operation. Upon invitation of the Islamic Republic of Iran, the International Atomic Energy Agency (IAEA) assembled a team of senior regulators from seven Member States for an Integrated Regulatory Review Service (IRRS) mission. The scope of the mission was limited to the safety regulation of Bushehr nuclear power plant (BNPP-1). The IRRS review took place from 20 February to 2 March at the INRA offices in Tehran and included a technical visit to the BNPP-1 site. The mission was an objective peer review based on IAEA safety standards, and was neither an inspection, nor an audit. Ms. Olena Mykolaichuk, IRRS Team Leader and Head of the State Nuclear Regulatory Committee of Ukraine, commended her INRA counterparts: 'The regulatory work performed on the Bushehr construction and in preparation for commissioning has demonstrated significant progress of INRA as a nuclear regulatory authority,' she said. Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division, added: 'Through this IRRS mission, both Iran and the international experts contribute to the enhancement of nuclear safety and worldwide experience sharing.' In the course of its review the IRRS team identified the following strengths: - INRA has a dedicated, conscientious staff, demonstrating clear commitments to further improvements. - INRA clearly recognizes the value of peer reviews and international cooperation regarding nuclear safety. - Despite a shortage of staff, INRA demonstrated strong leadership while performing both review and assessment and inspection tasks during the BNPP-1 construction and pre-commissioning. - INRA has developed an excellent computerized documentation control system. Recommendations and suggestions to improve INRA's regulatory

  7. 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

  8. 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)

  9. Deconstructing the Nature of Safety and Acceptability in Nuclear Fuel Waste Management, Canada

    International Nuclear Information System (INIS)

    Murphy, Brenda L.

    2003-01-01

    Since the Hare report was released in 1977, Canada's nuclear fuel waste management policies have been focused on one option, deep geologic disposal. However, since new legislation, called the Nuclear Fuel Waste Management Act came into force on November 15, 2002, the newly established Nuclear Waste Management Organisation has been mandated to review, over the next three years, not only deep geologic disposal but also to consider a suite of other options including reactor-site and centralised storage, and both above and below ground options. At this point in time, the process for the study and the criteria by which it will be evaluated are still quite unclear. The need for this new approach to NFW management in Canada was highlighted by an Environmental Assessment Panel (EA Panel) report in 1998. This EA Panel reviewed the 1994 environmental impact statement submitted by Atomic Energy Canada Limited (AECL) regarding the concept of deep geologic disposal in the Canadian Shield (Disposal Concept EA). The EA Panel's key conclusion was: From a technical perspective, safety of the AECL concept has been on balance adequately demonstrated for a conceptual stage of development, but from a social perspective, it has not. As it stands, the AECL concept for deep geological disposal has not been demonstrated to have broad public support. The concept in its current form does not have the required level of acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. AECL's study consisted of a review of the deep geologic disposal concept, since no site has yet been selected. It is generally understood that this type of disposal facility, if eventually sited, will be located on the Ontario portion of the Canadian Shield because Ontario power generators own and manage about 90% of Canada's NFW. This key EA Panel conclusion is predicated on the use of two key decision-making criteria - safety and acceptability. This paper reviews and assesses the specific ways

  10. 2015 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2015-10-01

    This report summarizes comments from the Peer Review Panel at the 2015 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on June 8-12, 2015, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; market transformation; and systems analysis.

  11. 2011 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-09-01

    This report summarizes comments from the Peer Review Panel at the 2011 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on May 9-13, 2011, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; education; market transformation; and systems analysis.

  12. 2013 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-10-01

    This report summarizes comments from the Peer Review Panel at the 2013 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on May 13-17, 2013, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; market transformation; and systems analysis.

  13. 2014 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2014-10-01

    This report summarizes comments from the Peer Review Panel at the 2014 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on June 16-20, 2014, in Washington, DC. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; market transformation; and systems analysis.

  14. 2012 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2012-09-01

    This report summarizes comments from the Peer Review Panel at the 2012 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on May 14-18, 2012, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; education; market transformation; and systems analysis.

  15. Aviation and healthcare: a comparative review with implications for patient safety.

    Science.gov (United States)

    Kapur, Narinder; Parand, Anam; Soukup, Tayana; Reader, Tom; Sevdalis, Nick

    2016-01-01

    Safety in aviation has often been compared with safety in healthcare. Following a recent article in this journal, the UK government set up an Independent Patient Safety Investigation Service, to emulate a similar well-established body in aviation. On the basis of a detailed review of relevant publications that examine patient safety in the context of aviation practice, we have drawn up a table of comparative features and a conceptual framework for patient safety. Convergence and divergence of safety-related behaviours across aviation and healthcare were derived and documented. Key safety-related domains that emerged included Checklists, Training, Crew Resource Management, Sterile Cockpit, Investigation and Reporting of Incidents and Organisational Culture. We conclude that whilst healthcare has much to learn from aviation in certain key domains, the transfer of lessons from aviation to healthcare needs to be nuanced, with the specific characteristics and needs of healthcare borne in mind. On the basis of this review, it is recommended that healthcare should emulate aviation in its resourcing of staff who specialise in human factors and related psychological aspects of patient safety and staff wellbeing. Professional and post-qualification staff training could specifically include Cognitive Bias Avoidance Training, as this appears to play a key part in many errors relating to patient safety and staff wellbeing.

  16. Expert panel evaluation of health information technology effects on adverse events.

    Science.gov (United States)

    Abramson, Erika L; Kern, Lisa M; Brenner, Samantha; Hufstader, Meghan; Patel, Vaishali; Kaushal, Rainu

    2014-08-01

    Adverse events (AEs) among hospitalized patients occur frequently and result in significant sequelae. Federal policy is incentivizing health information technology (HIT) use, although research demonstrating safety benefits from HIT is mixed. Our objective was to evaluate the potential effects of HIT on reducing 21 different inpatient AEs. Identifying AEs most likely to be reduced by HIT can inform the design of future studies evaluating its effectiveness. We conducted a modified Delphi panel of national experts in HIT and safety. We conducted a focused literature review to inform the experts. Using a novel framework, experts rated each AE as 'definitely reduced by health IT,' 'possibly reduced by health IT' and 'not likely to be reduced by health IT'. From our panel discussion, experts identified six AEs as 'definitely reduced by health IT': (1) adverse drug events (ADEs) associated with digoxin; (2) ADE associated with IV heparin; (3) ADE associated with hypoglycaemic agents; (4) ADE associated with low molecular weight heparin and factor Xa inhibitor; (5) contrast nephropathy associated with catheter angiography; and (6) ADE hospital-acquired antibiotic-associated Clostridium difficile. Understanding the effects of HIT on patient outcomes will be essential to ensuring that the significant federal investment results in anticipated improvements. This study serves as an important early step in helping with the design of future work evaluating level of HIT infrastructure and rates of inpatient AEs. © 2014 John Wiley & Sons, Ltd.

  17. Classification of antecedents towards safety use of health information technology: A systematic review.

    Science.gov (United States)

    Salahuddin, Lizawati; Ismail, Zuraini

    2015-11-01

    This paper provides a systematic review of safety use of health information technology (IT). The first objective is to identify the antecedents towards safety use of health IT by conducting systematic literature review (SLR). The second objective is to classify the identified antecedents based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model and an extension of DeLone and McLean (D&M) information system (IS) success model. A systematic literature review (SLR) was conducted from peer-reviewed scholarly publications between January 2000 and July 2014. SLR was carried out and reported based on the preferred reporting items for systematic reviews and meta-analyses (PRISMA) statement. The related articles were identified by searching the articles published in Science Direct, Medline, EMBASE, and CINAHL databases. Data extracted from the resultant studies included are to be analysed based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model, and also from the extended DeLone and McLean (D&M) information system (IS) success model. 55 articles delineated to be antecedents that influenced the safety use of health IT were included for review. Antecedents were identified and then classified into five key categories. The categories are (1) person, (2) technology, (3) tasks, (4) organization, and (5) environment. Specifically, person is attributed by competence while technology is associated to system quality, information quality, and service quality. Tasks are attributed by task-related stressor. Organisation is related to training, organisation resources, and teamwork. Lastly, environment is attributed by physical layout, and noise. This review provides evidence that the antecedents for safety use of health IT originated from both social and technical aspects. However, inappropriate health IT usage potentially increases the incidence of errors and produces new safety risks. The review cautions future

  18. 41 CFR 128-1.8009 - Review of Seismic Safety Program.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Review of Seismic Safety Program. 128-1.8009 Section 128-1.8009 Public Contracts and Property Management Federal Property Management Regulations System (Continued) DEPARTMENT OF JUSTICE 1-INTRODUCTION 1.80-Seismic Safety Program...

  19. Dynamic panel data models

    NARCIS (Netherlands)

    Bun, M.J.G.; Sarafidis, V.

    2013-01-01

    This Chapter reviews the recent literature on dynamic panel data models with a short time span and a large cross-section. Throughout the discussion we considerlinear models with additional endogenous covariates. First we give a broad overview of available inference methods placing emphasis on GMM.

  20. 2014 Bone and Muscle Risks Standing Review Panel

    Science.gov (United States)

    Steinberg, Susan; Glowacki, Julie; Gregor, Robert; Cullen, Diane; Drake, Almond; Enoka, Roger; Hanley, Edward, Jr.; Kraemer, William; Raven, Peter; Sumner, D. Rick

    2015-01-01

    The 2014 Bone and Muscle Risks Standing Review Panel (from here on referred to as the SRP) met for a site visit in Houston, TX on December 17 - 18, 2014. The SRP reviewed the updated Evidence Reports for the Risk of Impaired Performance Due to Reduced Muscle Mass, Strength and Endurance and (from here on referred to as the 2014 Muscle Evidence Report) and the Risk of Reduced Physical Performance Capabilities Due to Reduced Aerobic Capacity (from here on referred to as the 2014 Aerobic Evidence Report), as well as the Research Plans for these Risks. The SRP agreed the Evidence Reports were comprehensive and described a logical sequence of steps taken by NASA and the scientific community to address the risk of impaired performance as a result of muscle atrophy, i.e., reduced muscle mass, loss of strength and loss of endurance in a microgravity environment. The interdependence of the three physiological systems represented by this SRP (i.e., skeletal, muscular and cardiovascular) supports a level of discussion on system integration that is now appreciated by the Chief Scientist of the Human Research Program (HRP). The Evidence Reports cover the effects of microgravity on muscle, ranging from the cellular and molecular levels to whole muscle function. The reports also addressed other factors related to muscle (e.g., neural influences, insulin resistance, heat stress, and nutrition) that will serve as a basis for future discussions on the integration of physiological systems and the response to microgravity. The SRP agreed the Evidence Reports were balanced, provided insight to muscle function, and laid the foundation for the integrated approach now taken by the SRP.

  1. Advanced Fast Reactor - 100 (AFR-100) Report for the Technical Review Panel

    Energy Technology Data Exchange (ETDEWEB)

    Grandy, Christopher [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, James J. [Argonne National Lab. (ANL), Argonne, IL (United States); Moisseytsev, Anton [Argonne National Lab. (ANL), Argonne, IL (United States); Krajtl, Lubomir [Argonne National Lab. (ANL), Argonne, IL (United States); Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States); Kim, Taek K. [Argonne National Lab. (ANL), Argonne, IL (United States); Middleton, B. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2014-06-04

    This report is written to provide an overview of the Advanced Fast Reactor-100 in the requested format for a DOE technical review panel. This report was prepared with information that is responsive to the DOE Request for Information, DE-SOL-0003674 Advanced Reactor Concepts, dated February 27, 2012 from DOE’s Office of Nuclear Energy, Office of Nuclear Reactor Technologies. The document consists of two main sections. The first section is a summary of the AFR-100 design including the innovations that are incorporated into the design. The second section contains a series of tables that respond to the various questions requested of the reactor design team from the subject DOE RFI.

  2. Prefabricated RM Façade Panels - Search for the Safe Solution

    Science.gov (United States)

    Hulimka, Jacek; Kubica, Jan; Kałuża, Marta; Galman, Iwona

    2017-10-01

    The problem, which appeared during the design works on the untypical masonry openwork of the front elevation of the academic building in Poland was presented and discussed in this paper. The original solution of masonry external façade was too risky and practically impossible for realization from the workmanship point of view. For this reason authors were proposed to make this elevation wall as prefabricated construction consisted of medium scale prefabricated elevation panels made of openwork clinker units and masonry joints with reinforcement. Two solutions of prefabricated panels were elaborated: first by the design office and second one, significantly modified, proposed by the authors. Taking into consideration fact that proposed prefabricated panels are not the typical reinforced masonry possible to design based on Eurocode 6, the methodology of “supporting design by test” was accepted to verify the correctness of proposed solutions. The carried out tests of both types of prefabricated panels with results and their discussion are also presented here. The results have shown the lack of safety for the first type of prefabricates and good behaviour, safety and durability of the final, modified solution.

  3. Idaho National Laboratory Integrated Safety Management System FY 2012 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Farren Hunt

    2012-12-01

    Idaho National Laboratory (INL) performed an Annual Effectiveness Review of the Integrated Safety Management System (ISMS), per 48 Code of Federal Regulations (CFR) 970.5223 1, “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and identified target areas for focused improvements and assessments for fiscal year (FY) 2013. Results of the FY 2012 annual effectiveness review demonstrated that the INL’s ISMS program was significantly strengthened. Actions implemented by the INL demonstrate that the overall Integrated Safety Management System is sound and ensures safe and successful performance of work while protecting workers, the public, and environment. This report also provides several opportunities for improvement that will help further strengthen the ISM Program and the pursuit of safety excellence. Demonstrated leadership and commitment, continued surveillance, and dedicated resources have been instrumental in maturing a sound ISMS program. Based upon interviews with personnel, reviews of assurance activities, and analysis of ISMS process implementation, this effectiveness review concludes that ISM is institutionalized and is “Effective”.

  4. 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...

  5. Improving regulatory effectiveness in Federal/State siting actions. Success factor evaluation panel. Final report

    International Nuclear Information System (INIS)

    Haggard, J.

    1977-06-01

    An independent appraisal of the factors that determine efficiency in reaching environmental decisions with respect to nuclear facilities was addressed. The Panel recommended to substitute 'effectiveness' for 'efficiency.' Thus, an effective decision is: 'A timely final decision, that provides for necessary change, consistent with societal objectives and law, and which is equitable and practical, and is based upon fully and candidly expressed premises utilizing a commonly available data base.' The measurement criteria for evaluating the effectiveness of the environmental decision making process are: timely decision, final decision, provision for change, consistency with societal goals and law, equitable, practical, fully and candidly expressed premises, commonly available data base, and public confidence. The Panel evaluated the 8 policies proposed by NRC staff as essential to licensing reform: national fuels policy, regional review, early disclosure, State role, technical assistance to State, role of utilities, radiation health and safety, and modification of the Atomic Energy Act. The five NRC scenarios were evaluated in terms of regulatory effectiveness

  6. Overview of the periodic safety review of nuclear power plants as practised in India

    International Nuclear Information System (INIS)

    Jhamb, N.K.; Chande, S.K.

    1997-01-01

    In India, routine and periodic safety reviews of nuclear facilities are carried out through a multitiered hierarchy of committees at the plant level, the operating organization level and the regulatory body level. In 1993, it was decided by the Atomic Energy Regulatory Board (AERB, the regulatory body) that, as a policy, authorization for operation of nuclear power plants (NPPs) shall have a validity period of 5 years, after which this authorization will have to be renewed. NPPs have to carry out a self-assessment according to an established procedure, prepare a Safety Assessment Report for Renewal of Authorization (SARRA) and submit it to the AERB for review. The procedure defines the objectives of the report and gives guidelines on the required review of the self-assessment of the operational plant safety. The paper discusses the objectives, the elements of the SARRA review, the review process, the SARRA review carried out in 1993-1994, the basis for acceptability of continued plant operation, and the lessons learned for future periodic safety reviews in India and for exchange of operating experience feedback. (author)

  7. Human Research Program 2010 Chair Standing Review Panel Meeting

    Science.gov (United States)

    Steinberg, Susan

    2011-01-01

    The 13 Human Research Program (HRP) Standing Review Panel (SRP) Chairs, and in some cases one or two additional panel members (see section XIV, roster) referred to as the Chair (+1) SRP throughout this document, met at the NASA Johnson Space Center (JSC) on December 7, 2010 to allow the HRP Elements and Projects to report on their progress over the past year, their current status, and their plans for the upcoming year based on NASA's current goals and objectives for human space exploration. A large focus of the meeting was also used to discuss integration across the HRP scientific disciplines based on a recommendation from the 2009 HRP SRP review. During the one-day meeting, each of the HRP Elements and Projects presented the changes they made to the HRP Integrated Research Plan (IRP Rev. B) over the last year, and what their top three areas of integration are between other HRP Elements/Projects. The Chair (+1) SRP spent sufficient time addressing the panel charge, either as a group or in a separate closed session, and the Chair (+1) SRP and the HRP presenters and observers, in most cases, had sufficient time to discuss during and after the presentations. The SRP made a final debriefing to the HRP Program Scientist, Dr. John B. Charles, prior to the close of the meeting on December 7, 2010. Overall, the Chair (+1) SRP concluded that most of the HRP Elements/Projects did a commendable job during the past year in addressing integration across the HRP scientific disciplines with the available resources. The Chair (+1) SRP agreed that the idea of integration between HRP Elements/Projects is noble, but believes all parties involved should have the same definition of integration, in order to be successful. The Chair (+1) SRP also believes that a key to successful integration is communication among the HRP Elements/Projects which may present a challenge. The Chair (+1) SRP recommends that the HRP have a workshop on program integration (with HRP Element

  8. Environmental factors and puberty timing: Expert panel research needs

    Science.gov (United States)

    An expert panel reviewed the literature on endocrine disrupting chemicals (EDCs), body size and puberty. The panel concluded that available experimental animal and human data support a possible role of EDCs and body size in relation to alterations in pubertal onset and progressio...

  9. IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

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

    International Nuclear Information System (INIS)

    2005-01-01

    The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, 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 for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards; - Integrated approach to the provision for the application of safety standards; and - 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. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices; on the capability and reliability of the commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

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

    International Nuclear Information System (INIS)

    2007-01-01

    The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, 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 for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - 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. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

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

    International Nuclear Information System (INIS)

    2008-01-01

    The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, 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 for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - 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. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

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

    Energy Technology Data Exchange (ETDEWEB)

    Sagar, Budhi (Center for Nuclear Waste Regulatory Analyses, Southwest Research Inst., San Antonio, TX (US)); Egan, Michael (Quintessa Limited, Henley-on-Thames (GB)); Roehlig, Klaus-Juergen (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (DE)); Chapman, Neil (Independent Consultant (XX)); Wilmot, Roger (Galson Sciences Limited, Oakham (GB))

    2008-03-15

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

  14. 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

  15. 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.

  16. Final report : scientific review and workshop on selenium at Alberta mountain coal mines held in Hinton, Alberta, Canada on June 28 and 29, 2005 by the Selenium Science Panel

    International Nuclear Information System (INIS)

    Klaverkamp, J.F.; Adams, W.J.; Hodson, P.V.; Ohlendorf, H.M.; Skorupa, J.P.

    2005-01-01

    The effects and approaches to the management of selenium in Alberta mountain coal mines were reviewed by a Selenium Science Panel to determine if any adverse ecological impacts have occurred or will occur related to discharges of selenium associated with coal mining. The Science Panel reviewed work that has been completed in Alberta as well as technical reports on surface water quality, the aquatic food web, and monitoring programs on fish and terrestrial wildlife. It then assessed whether studies conducted to date have fulfilled recommendations made at a previous workshop held in September 2000 regarding the management of selenium. The Science Panel noted considerable progress in studies proposed in a work plan developed soon after the 2000 workshop. Building upon this foundation of knowledge and other information contained in the scientific literature, the Science Panel noted some knowledge gaps and priority issues. In order to address these gaps and issues, the Panel's recommendations were presented in this report along with supporting rationale.12 refs., 5 appendices

  17. 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...

  18. Research funding. Big names or big ideas: do peer-review panels select the best science proposals?

    Science.gov (United States)

    Li, Danielle; Agha, Leila

    2015-04-24

    This paper examines the success of peer-review panels in predicting the future quality of proposed research. We construct new data to track publication, citation, and patenting outcomes associated with more than 130,000 research project (R01) grants funded by the U.S. National Institutes of Health from 1980 to 2008. We find that better peer-review scores are consistently associated with better research outcomes and that this relationship persists even when we include detailed controls for an investigator's publication history, grant history, institutional affiliations, career stage, and degree types. A one-standard deviation worse peer-review score among awarded grants is associated with 15% fewer citations, 7% fewer publications, 19% fewer high-impact publications, and 14% fewer follow-on patents. Copyright © 2015, American Association for the Advancement of Science.

  19. Review of SKB's Safety Assessment SR-Can: Contributions in Support of SKI's and SSI's Review by External Consultants

    International Nuclear Information System (INIS)

    2008-03-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety report, SR-Site, on the repository's long-term safety and radiological consequences. As a preparation for SR-Site, SKB published the preliminary safety assessment SR-Can in November 2006. The purposes were to document a first evaluation of long-term safety for the two candidate sites at Forsmark and Laxemar and to provide feedback to SKB's future programme of work. An important objective of the authorities' review of SR-Can is to provide guidance to SKB on the complete safety reporting for the license application. The authorities have engaged external experts for independent modelling, analysis and review, with the aim to provide a range of expert opinions related to the sufficiency and appropriateness of various aspects of SR-Can. The conclusions and judgments in this report are those of the authors and may not necessarily coincide with those of SKI and SSI. The authorities own review will be published separately (SKI Report 2008:23, SSI Report 2008:04 E). This report compiles contributions from several specific research projects. The separate reviews cover topics regarding the engineered barrier system, the quality assurance, the climate evolution and its effects, and the ecosystems and environmental impacts. All contributions are in English apart from the review concerning ecosystems and environmental impacts, which is presented in Swedish

  20. 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

  1. 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

  2. IAEA Team Concludes Peer Review of Greece's Regulatory Framework for Radiation Safety

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: An international team of senior nuclear safety and radiation protection experts yesterday concluded an 11-day mission to review the regulatory framework for nuclear and radiation safety in Greece. The Integrated Regulatory Review Service (IRRS) mission, which was conducted at the request of the Government of the Hellenic Republic, noted good practices in the country's nuclear regulatory system and also identified issues for improvement for the Greek Atomic Energy Commission (GAEC) and the Greek competent authorities. These are aimed at strengthening the effectiveness of the country's regulatory framework and functions in line with IAEA Safety Standards. ''The IRRS team enjoyed excellent cooperation from the GAEC throughout its mission,'' said Tom Ryan, mission leader and Director of Regulations and Information Management at the Radiological Protection Institute of Ireland. ''The GAEC staff were very open and candid in their discussions and provided the fullest practicable assistance.'' The main observations of the IRRS Review team included: While the Greek Government's commitment to safety is being demonstrated through its actions, the development of a comprehensive national policy and strategy expressed in a consolidated statement would provide a valuable framework and guidance for future actions in terms of safety; and GAEC has effective independence. The Greek government has ensured that GAEC is effectively independent in its safety-related decision-making and that it has functional separation from entities having responsibility or interests that could unduly influence its decision making. Strengths and good practices identified by the IRRS team included: Greece actively participates in the global safety regime including all relevant safety conventions; The nation's radiation monitoring system for the detection of illicit trafficking contributes significantly to identifying potential radiation emergencies due to events within or outside the country

  3. DOE Hydrogen Program: 2005 Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    Chalk, S. G.

    2005-09-01

    This report summarizes comments from the Peer Review Panel at the FY 2005 DOE Hydrogen Program Annual Merit Review, held on May 23-26, 2005, in Arlington, Virginia. The projects evaluated support the Department of Energy and President Bush's Hydrogen Initiative. The results of this merit review and peer evaluation are major inputs used by DOE to make funding decisions. Project areas include hydrogen production and delivery; hydrogen storage; fuel cells; technology validation; safety, codes and standards; education; and systems analysis.

  4. DOE Hydrogen Program: 2006 Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    Milliken, J.

    2006-09-01

    This report summarizes comments from the Peer Review Panel at the FY 2006 DOE Hydrogen Program Annual Merit Review, held on May 16-19, 2006, in Arlington, Virginia. The projects evaluated support the Department of Energy and President Bush's Hydrogen Initiative. The results of this merit review and peer evaluation are major inputs used by DOE to make funding decisions. Project areas include hydrogen production and delivery; hydrogen storage; fuel cells; technology validation; safety, codes and standards; education; and systems analysis.

  5. 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.

  6. [Evidence-based effectiveness of road safety interventions: a literature review].

    Science.gov (United States)

    Novoa, Ana M; Pérez, Katherine; Borrell, Carme

    2009-01-01

    Only road safety interventions with scientific evidence supporting their effectiveness should be implemented. The objective of this study was to identify and summarize the available evidence on the effectiveness of road safety interventions in reducing road traffic collisions, injuries and deaths. All literature reviews published in scientific journals that assessed the effectiveness of one or more road safety interventions and whose outcome measure was road traffic crashes, injuries or fatalities were included. An exhaustive search was performed in scientific literature databases. The interventions were classified according to the evidence of their effectiveness in reducing road traffic injuries (effective interventions, insufficient evidence of effectiveness, ineffective interventions) following the structure of the Haddon matrix. Fifty-four reviews were included. Effective interventions were found before, during and after the collision, and across all factors: a) the individual: the graduated licensing system (31% road traffic injury reduction); b) the vehicle: electronic stability control system (2 to 41% reduction); c) the infrastructure: area-wide traffic calming (0 to 20%), and d) the social environment: speed cameras (7 to 30%). Certain road safety interventions are ineffective, mostly road safety education, and others require further investigation. The most successful interventions are those that reduce or eliminate the hazard and do not depend on changes in road users' behavior or on their knowledge of road safety issues. Interventions based exclusively on education are ineffective in reducing road traffic injuries.

  7. Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; and Bzostek, J.

    2009-09-30

    The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M&T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M&Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M&Ts. The M&Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M&Ts for each trend, and (2) whether M&Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M&T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

  8. Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; Bzostek, J.

    2009-01-01

    The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M and T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M and Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M and Ts. The M and Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M and Ts for each trend, and (2) whether M and Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M and T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

  9. Designing for human performance - CANDU electrical panels - then and now

    International Nuclear Information System (INIS)

    Patterson, B.K.

    2003-01-01

    Experience has shown that few changes are made to CANDU control center panels once plants are in service. There are several reasons for this, for example, operational conservatism, outage minimization, avoidance of retraining effort, and perhaps lack of appreciation of improvement opportunities. Since the initial CANDU 6 plants were designed, the industry has moved forward with adoption of new approaches to control room interface design that have introduced changes in design principles and emphasis. At Point Lepreau, the electrical panels have remained virtually unchanged since initial design. The author, the original electrical system commissioning engineer, reviews the design considerations that led to the initial panel design, reviews some of the operational limitations discovered during use, and offers some suggestions on improvement directions, if these panels were being designed today, that would offer an implementation to better support operator tasks. (author)

  10. 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

  11. Measures to strengthen international co-operation in nuclear, radiation and transport safety and waste management. Nuclear safety review for the year 2003

    International Nuclear Information System (INIS)

    2004-01-01

    The Nuclear Safety Review for the Year 2003 presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety during 2003. As in 2002 the overview is supported by more detailed Notes by the Secretariat: Safety Related Events and Issues Worldwide during 2003 (document 2004/Note 6), The Agency's Safety Standards: Activities during 2003 (document 2004/Note 7) and Providing for the Application of the Safety Standards (document 2004/Note 8). In January 2003, the Agency implemented an organization change and developed an integrated approach to reflect a broader assignment of nuclear safety and nuclear security and to better exploit synergy between them. The Office of Physical Protection and Material Security renamed to Office of Nuclear Security was transferred from the Department of Safeguards to the Department of Nuclear Safety, which became the Department of Nuclear Safety and Security to reflect the change. This Review provides information primarily on nuclear safety, and nuclear security will be addressed in a separate report

  12. Preliminary standard review guide for Environmental Restoration/Decontamination and Decommissioning safety analyses

    International Nuclear Information System (INIS)

    Ellingson, D.R.

    1993-06-01

    The review guide is based on the shared experiences, approaches, and philosophies of the Environmental Restoration/Decontamination and Decommissioning (ER/D ampersand D) subgroup members. It is presented in the form of a review guide to maximize the benefit to both the safety analyses practitioner and reviewer. The guide focuses on those challenges that tend to be unique to ER/D ampersand D cleanup activities. Some of these experiences, approaches, and philosophies may find application or be beneficial to a broader spectrum of activities such as terminal cleanout or even new operations. Challenges unique to ER/D ampersand D activities include (1) consent agreements requiring activity startup on designated dates; (2) the increased uncertainty of specific hazards; and (3) the highly variable activities covered under the broad category of ER/D ampersand D. These unique challenges are in addition to the challenges encountered in all activities; e.g., new and changing requirements and multiple interpretations. The experiences in approaches, methods, and solutions to the challenges are documented from the practitioner and reviewer's perspective, thereby providing the viewpoints on why a direction was taken and the concerns expressed. Site cleanup consent agreements with predetermined dates for restoration activity startup add the dimension of imposed punitive actions for failure to meet the date. Approval of the safety analysis is a prerequisite to startup. Actions that increase expediency are (1) assuring activity safety; (2) documenting that assurance; and (3) acquiring the necessary approvals. These actions increase the timeliness of startup and decrease the potential for punitive action. Improvement in expediency has been achieved by using safety analysis techniques to provide input to the line management decision process rather than as a review of line management decisions. Expediency is also improved by sharing the safety input and resultant decisions with

  13. 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.

  14. Conclusions on the two technical panels on HLW-disposal and waste treatment processes respectively

    International Nuclear Information System (INIS)

    Dinkespiller, J.A.; Dejonghe, P.; Feates, F.

    1986-01-01

    The paper reports the concluding panel session at the European Community Conference on radioactive waste management and disposal, Luxembourg 1985. The panel considered the conclusions of two preceeding technical panels on high level waste (HLW) disposal and waste treatment processes. Geological disposal of HLW, waste management, safety assessment of waste disposal, public opinion, public acceptance of the manageability of radioactive wastes, international cooperation, and waste management in the United States, are all discussed. (U.K.)

  15. Panel discussion on rock mechanics issues in repository design

    International Nuclear Information System (INIS)

    Bieniawski, Z.T.; Kim, K.S.; Nataraja, M.

    1996-01-01

    The panel discussion was introduced by Mr. Z.T.(Richard) Bieniawski and then continued with five additional speakers. The topics covered in the discussion included rock mechanics pertaining to the design of underground facilities for the disposal of radioactive wastes and the safety of such facilities. The speakers included: Mr. Kun-Soo Kim who is a specialist in the area of rock mechanics testing during the Basalt Waste Isolation Project; Dr. Mysore Nataraja who is the senior project manager with the NRC; Dr. Michael Voegele who is the project manager for Science Applications International Corporation (SAIC) on the Yucca Mountain Project; Dr. Edward Cording who is a member of the Nuclear Waste Technical Review Board; and Dr. Hemendra Kalia who is employed by Los Alamos National Laboratory and coordinates various activities of testing programs at the Yucca Mountain Site

  16. 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...

  17. 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

  18. 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.

  19. Occupational health and safety issues affecting young workers: a literature review.

    Science.gov (United States)

    Laberge, Marie; Ledoux, Elise

    2011-01-01

    Many overview articles, reports, book chapters and literature reviews have examined the health and safety of young workers. These sources discuss the relationships between the work conditions of young workers and the various indicators of accidents and occupational diseases. Breslin et al. [12,13] conducted two literature reviews of quantitative studies to determine which factors best predicted work accidents and occupational disorders in young people. The present article proposes a review of young people's occupational health and safety (OHS) factors (e.g., demographic, individual, professional, organizational, temporal and operational factors) in both qualitative and quantitative studies. Five types of problems were analyzed in greater depth, namely MSD symptoms, respiratory, allergy and toxicological problems, mental health and well-being, alcohol and drug consumption, and fatigue. This review likewise examines related dimensions that allow us to adopt a more global perspective on this subject by considering such elements as young people's values, their knowledge and attitudes, safety practices in companies, the safe integration of young people, and rehabilitation. A total of 189 scientific articles were selected on the basis of certain criteria. These articles came from refereed OHS journals published between 1994 and 2005.

  20. 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

  1. International Nuclear Safety Experts Conclude IAEA Peer Review of Korea's Regulatory System

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: An international team of senior nuclear safety experts concluded today a two-week mission to review the regulatory framework for nuclear safety in the Republic of Korea. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Korea, while the final report will be submitted by the end of summer 2011. At the request of the Korean Government, the IAEA assembled a team of 16 senior regulatory experts from 14 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Korean Ministry for Education, Science and Technology (MEST) and the Korean Institute for Nuclear Safety (KINS). The mission is a peer-review based on the IAEA Safety Standards. ''This was the first IRRS mission organized after Japan's Fukushima Daiichi nuclear accident and it included a review of the regulatory implications of that event,' explains Denis Flory, IAEA Deputy Director General and Head of the Department of Nuclear Safety and Security. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission and Team Leader of this mission commended the Korean authorities for their openness and commitment to sharing their experience with the world's nuclear safety community. ''IRRS missions such as the one that was just concluded here in the Republic of Korea are crucial to the enhancement of nuclear safety worldwide,'' he said. The IRRS team reviewed Korea's current regulatory framework while acknowledging the fact that the country's Government has already decided to establish, as of October 2011, a new independent regulatory body to be called Nuclear Safety Commission (NSC). As a consequence, KINS role will be as a regulatory expert organization reporting to the NSC, while MEST's role will be restricted to promoting the utilization of nuclear energy. The IRRS team identified particular strengths in the Korean regulatory system

  2. Vacuum Insulation Panels (VIPs) for building construction industry - A review of the contemporary developments and future directions

    International Nuclear Information System (INIS)

    Alam, M.; Singh, H.; Limbachiya, M.C.

    2011-01-01

    Highlights: → Vacuum Insulation Panels (VIP), a high thermal resistance building insulation. → Review of research into VIPs for building applications. → High cost and uncertainty of service life are two barriers for VIP use in buildings. → SiO 2 /SiN x coated PET laminate- candidate for high barrier VIP envelope. → The optimum combination of VIP core and envelope yet to be determined. -- Abstract: Demand for energy efficient buildings has increased drastically in recent years and this trend will continue in the future. Insulating building elements will play a key role in meeting this demand by reducing heat losses through the building fabric. Due to their higher thermal resistance, Vacuum Insulation Panels (VIPs) would be a more energy efficient alternative to conventional building insulation materials. Thus, efforts to develop VIPs with characteristics suitable for applications to new and existing buildings are underway. This paper provides a review of important contemporary developments towards producing VIPs using various materials such as glass fibre, foams, perlite and fibre/powder composites. The limitations of the materials currently used to fabricate VIPs have not been emphasised in detail in previous review papers published. Selection criteria, methods to measure important properties of VIPs and analytical and numerical models presented in the past have been detailed. Limitations of currently employed design tools along with potential future materials such as Nano/microcellular foams and SiO x /SiN x coatings for use in VIPs are also described.

  3. 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

  4. 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)

  5. 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

  6. Centers for Disease Control review panel's recommendations on health effects and epidemiological studies of operations at the Savannah River Plant, Aiken, South Carolina. Public comment and meeting report

    International Nuclear Information System (INIS)

    1985-05-01

    Based on the request of the US Department of Energy, the Centers for Disease Control of the US Department of Health and Human Services organized a panel to review the feasibility and usefulness of conducting further epidemiologic studies of delayed health effects around the Department of Energy's Savannah River Plant. The review and recommendations of the panel were documented in a report entitled Epidemiologic Projects Considered Possible to Undertake in Populations Around the Savannah River Plant. On November 30, 1984, the Department of Energy announced in the Federal Register (49 FR 47095) the conduct of a public meeting and a 30-day public comment period between December 1 and December 30, 1984, on the recommendations of the review panel. Based on the requests of individuals and representatives of organizations attending the December 18, 1984, public meetings, the Department of Energy subsequently announced in the Federal Register on December 31, 1984 (49 FR 50767) an extension of the public comment period to January 31, 1985. This report documents the public meeting and comment process, and provides responses to the public comments that were submitted during this process. In addition, this report contains the Department of Energy's position based on the recommendations of the Centers for Disease Control review panel and the public comments. 23 refs., 16 tabs

  7. TWRS vadose zone contamination issue expert panel status report

    International Nuclear Information System (INIS)

    Shafer, D.S.

    1997-01-01

    When members were first canvassed for participation in the Vadose Zone Expert Panel the stated purpose for convening the Panel was to review a controversial draft report, the SX Tank Farm Report. This report was produced by a DOE Grand Junction Project Office (GJPO) contractor, RUST Geotech, now MACTEC-ERS, for the DOE Richland Office (DOERL). Three meetings were planned for June, July and August, 1995 to review the draft report and to complete a Panel report by mid-September. The Expert Panel has found its efforts confounded by various non-technical issues. The Expert Panel has chosen to address some of the non-technical issues in this Preface rather than to dilute the technical discussion that follows in the body of this independent expert panel status report (Panel Report). Rather than performing a straightforward manuscript review, the Panel was asked to resolve conflicting interpretations of gamma-ray logging measurements performed in vadose zone boreholes (drywells) surrounding the high-level radioactive wastes of the SX tank farm. There are numerous and complex technical issues that must be evaluated before the vertical and radial extent of contaminant migration at the SX tank farm can be accurately assessed. When the Panel first met in early June, 1996, it quickly became apparent that the scientific and technical issues were obscured by policy and institutional affairs which have polarized discussion among various segments of the Hanford organization. This situation reflects the kinds of institutional problems described separately in reports by the National Research Council of the National Academy of Sciences (NAS/NRC), The Hanford Tanks Environmental Impacts and Policy Choices and BmTiers to Science: Technical Management of the Department of Energy Environmental Remediation Program. The Vadose Zone Characterization Program, appears to be caught between conflicting pressures and organizational mandates, some imposed from outside DOE-RL and some self

  8. DOE Hydrogen Program: 2007 Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    Milliken, J.

    2007-09-01

    This report summarizes comments from the Peer Review Panel at the FY 2007 DOE Hydrogen Program Annual Merit Review, held on May 14-18, 2007, in Washington, D.C. The projects evaluated support the Department of Energy and President Bush's Hydrogen Initiative. The results of this merit review and peer evaluation are major inputs used by DOE to make funding decisions. Project areas include hydrogen production and delivery; hydrogen storage; fuel cells; technology validation; safety, codes and standards; education; and systems analysis.

  9. Re-assessment of seismic loads in conjunction with periodic safety review

    International Nuclear Information System (INIS)

    Jonczyk, Josef

    2002-01-01

    The objective of this paper is the fundamental consideration of a safeguard-aim-oriented approach for use in the re-assessment of seismic events with regard to the periodic safety review (PSR) of nuclear power plants (NPP). The re-assessment aspects of site-specific design earthquakes (DEQ), specially the procedure for seismic hazard analysis, will not, however, be considered in detail here. The proposed assessment concept clearly presents a general approach for safety assessments. The approach is based on a successive screening review of components that are considered sufficiently earthquake-resistant. In this respect, the principle of maximum practical application of the design documentation has been considered in the re-assessment process. On the other hand, the safeguard-aim-oriented evaluation will also be applied with regard to whether the requirements of the safety regulations are fulfilled with respect to the safety goals. The review in conjunction with PSR does not, however, attempt to perform this under all technical aspects. Moreover, it is possible to make extensive use of experimental knowledge and engineering judgement with regard to the structural capacity behaviour in case of a seismic event. Compared with design procedures, however, this proposed approach differs from the one applied in licensing procedures, in which such assessment freedom will not usually be exhausted. (author)

  10. Environmental factors and puberty timing: expert panel research needs

    DEFF Research Database (Denmark)

    Louis, G.M. Buck; Jr, L.E. Gray; Marcus, M.

    2008-01-01

    Serono Symposia International convened an expert panel to review the impact of environmental influences on the regulation of pubertal onset and progression while identifying critical data gaps and future research priorities. An expert panel reviewed the literature on endocrine-disrupting chemicals......, body size, and puberty. The panel concluded that available experimental animal and human data support a possible role of endocrine-disrupting chemicals and body size in relation to alterations in pubertal onset and progression in boys and girls. Critical data gaps prioritized for future research......, and (3) basic research to identify the primary signal(s) for the onset of gonadotropin-releasing hormone-dependent/central puberty and gonadotropin-releasing hormone-independent/peripheral puberty. Prospective studies of couples who are planning pregnancies or pregnant women are needed to capture...

  11. Development of a draft of human factors safety review procedures for the Korean Next Generation Reactor

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C.

    2000-02-01

    In this study, a draft of Human Factors Engineering (HFE) Safety Review Procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE program management, human factors analyses, human factors design, and HFE verification and validation, based on section 15.1 'human factors engineering design process' and 15.2 'control room human factors engineering' of KNGR specific safety requirements and chapter 15 'human factors engineering' of KNGR safety regulatory guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system

  12. Microbiological specifications and testing methods for irradiated food. Report of a panel of experts

    International Nuclear Information System (INIS)

    1970-01-01

    In recent years there has been increased interest in the development of food items processed by means of ionizing radiation, wherever that form of preservation might show advantage over other methods. If this method becomes successful, the various items will be commercially exploited; it would then be convenient to have similar legislation in many countries of the world to control this type of processing and to facilitate international trade. To gather information and suggestions in order to devise legislation on irradiated food, a Joint FAO/IAEA/ WHO Expert Committee on the Technical Basis for Legislation on Irradiated Food was held in Rome on 21-28 April 1964. The Committee's report, 'The technical basis for legislation on irradiated food', was published as FAO Atomic Energy Series No.6 and WHO Technical Series No. 316. The Committee's terms of reference were to consider the available evidence on the effect on food of treatment with ionizing radiation in the context of wholesomeness and safety for consumption. Nutritional aspects were taken into account, but microbiological safety and microbiological methods for irradiated food were excluded since these subjects were believed to be too broad for adequate coverage in the working time available at the meeting. However, realizing the importance of radiation microbiology and the need for guidance in formulating regulations in this field, the committee drafted the following recommendation: 'The methods and standards used to ensure the microbiological safety of the irradiated product should, as a matter of urgency, be subject to review by competent international bodies in order that internationally acceptable methods and standards may be agreed upon'. In response to this recommendation an FAO/IAEA Panel on Microbiological Standards and Testing Methods for Irradiated Food was held in Vienna on 22-26 June 1965, in collaboration with the International Association of Microbiological Societies (IAMS). This was a working

  13. Microbiological specifications and testing methods for irradiated food. Report of a panel of experts

    International Nuclear Information System (INIS)

    1971-01-01

    In recent years there has been increased interest in the development of food items processed by means of ionizing radiation, wherever that form of preservation might show advantage over other methods. If this method becomes successful, the various items will be commercially exploited; it would then be convenient to have similar legislation in many countries of the world to control this type of processing and to facilitate international trade. To gather information and suggestions in order to devise legislation on irradiated food, a Joint FAO/IAEA/ WHO Expert Committee on the Technical Basis for Legislation on Irradiated Food was held in Rome on 21-28 April 1964. The Committee's report, 'The technical basis for legislation on irradiated food', was published as FAO Atomic Energy Series No.6 and WHO Technical Series No. 316. The Committee's terms of reference were to consider the available evidence on the effect on food of treatment with ionizing radiation in the context of wholesomeness and safety for consumption. Nutritional aspects were taken into account, but microbiological safety and microbiological methods for irradiated food were excluded since these subjects were believed to be too broad for adequate coverage in the working time available at the meeting. However, realizing the importance of radiation microbiology and the need for guidance in formulating regulations in this field, the committee drafted the following recommendation: 'The methods and standards used to ensure the microbiological safety of the irradiated product should, as a matter of urgency, be subject to review by competent international bodies in order that internationally acceptable methods and standards may be agreed upon'. In response to this recommendation an FAO/IAEA Panel on Microbiological Standards and Testing Methods for Irradiated Food was held in Vienna on 22-26 June 1965, in collaboration with the International Association of Microbiological Societies (IAMS). This was a working

  14. Microbiological specifications and testing methods for irradiated food. Report of a panel of experts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-04-01

    In recent years there has been increased interest in the development of food items processed by means of ionizing radiation, wherever that form of preservation might show advantage over other methods. If this method becomes successful, the various items will be commercially exploited; it would then be convenient to have similar legislation in many countries of the world to control this type of processing and to facilitate international trade. To gather information and suggestions in order to devise legislation on irradiated food, a Joint FAO/IAEA/ WHO Expert Committee on the Technical Basis for Legislation on Irradiated Food was held in Rome on 21-28 April 1964. The Committee's report, 'The technical basis for legislation on irradiated food', was published as FAO Atomic Energy Series No.6 and WHO Technical Series No. 316. The Committee's terms of reference were to consider the available evidence on the effect on food of treatment with ionizing radiation in the context of wholesomeness and safety for consumption. Nutritional aspects were taken into account, but microbiological safety and microbiological methods for irradiated food were excluded since these subjects were believed to be too broad for adequate coverage in the working time available at the meeting. However, realizing the importance of radiation microbiology and the need for guidance in formulating regulations in this field, the committee drafted the following recommendation: 'The methods and standards used to ensure the microbiological safety of the irradiated product should, as a matter of urgency, be subject to review by competent international bodies in order that internationally acceptable methods and standards may be agreed upon'. In response to this recommendation an FAO/IAEA Panel on Microbiological Standards and Testing Methods for Irradiated Food was held in Vienna on 22-26 June 1965, in collaboration with the International Association of Microbiological Societies (IAMS). This was a working

  15. Flaws found in Los Alamos safety procedures

    Science.gov (United States)

    Gwynne, Peter

    2017-12-01

    A US government panel on nuclear safety has discovered a series of safety issues at the Los Alamos National Laboratory, concluding that government oversight of the lab's emergency preparation has been ineffective.

  16. 75 FR 4406 - Disease, Disability, and Injury Prevention and Control Special Emphasis Panel: Occupational...

    Science.gov (United States)

    2010-01-27

    ... recommendations to the Disease, Disability, and Injury Prevention and Control SEP: Occupational Safety and Health... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Disease, Disability, and Injury Prevention and Control Special Emphasis Panel: Occupational Safety and Health Training...

  17. Developing and Testing the Health Care Safety Hotline: A Prototype Consumer Reporting System for Patient Safety Events.

    Science.gov (United States)

    Schneider, Eric C; Ridgely, M Susan; Quigley, Denise D; Hunter, Lauren E; Leuschner, Kristin J; Weingart, Saul N; Weissman, Joel S; Zimmer, Karen P; Giannini, Robert C

    2017-06-01

    This article describes the design, development, and testing of the Health Care Safety Hotline, a prototype consumer reporting system for patient safety events. The prototype was designed and developed with ongoing review by a technical expert panel and feedback obtained during a public comment period. Two health care delivery organizations in one metropolitan area collaborated with the researchers to demonstrate and evaluate the system. The prototype was deployed and elicited information from patients, family members, and caregivers through a website or an 800 phone number. The reports were considered useful and had little overlap with information received by the health care organizations through their usual risk management, customer service, and patient safety monitoring systems. However, the frequency of reporting was lower than anticipated, suggesting that further refinements, including efforts to raise awareness by actively soliciting reports from subjects, might be necessary to substantially increase the volume of useful reports. It is possible that a single technology platform could be built to meet a variety of different patient safety objectives, but it may not be possible to achieve several objectives simultaneously through a single consumer reporting system while also establishing trust with patients, caregivers, and providers.

  18. 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

  19. Results of 6th Review Meeting and Perspective of the 7th Review Meeting of the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Lee, Sukho; Kim, Manwoong; You, Jeongwon; Lee, Youngeal

    2017-01-01

    This paper highlighted the objective and role of the Convention on Nuclear Safety organized by the IAEA. The Convention provides Member States to demonstrate and share how to maintain and improve the level of nuclear safety. The results of the 6 th review meeting were implemented for safety improvements and to prepare for 7 th national report. Seven and a half months before the 7 th Review Meeting, the National Report has submitted on steps and measures taken to implement Convention obligations. The Contracting Parties reviewed each other’s reports, and exchanged written questions, written answers and comments. The discussions in the Country Group sessions were generally good with a lively and frank exchange of information. The Country Groups noted the significant measures taken by Contracting Parties to improve nuclear safety and identified a number of good practices to be shared with all Contracting Parties.

  20. Human Research Program Space Human Factors Engineering (SHFE) Standing Review Panel (SRP)

    Science.gov (United States)

    Wichansky, Anna; Badler, Norman; Butler, Keith; Cummings, Mary; DeLucia, Patricia; Endsley, Mica; Scholtz, Jean

    2009-01-01

    The Space Human Factors Engineering (SHFE) Standing Review Panel (SRP) evaluated 22 gaps and 39 tasks in the three risk areas assigned to the SHFE Project. The area where tasks were best designed to close the gaps and the fewest gaps were left out was the Risk of Reduced Safety and Efficiency dire to Inadequate Design of Vehicle, Environment, Tools or Equipment. The areas where there were more issues with gaps and tasks, including poor or inadequate fit of tasks to gaps and missing gaps, were Risk of Errors due to Poor Task Design and Risk of Error due to Inadequate Information. One risk, the Risk of Errors due to Inappropriate Levels of Trust in Automation, should be added. If astronauts trust automation too much in areas where it should not be trusted, but rather tempered with human judgment and decision making, they will incur errors. Conversely, if they do not trust automation when it should be trusted, as in cases where it can sense aspects of the environment such as radiation levels or distances in space, they will also incur errors. This will be a larger risk when astronauts are less able to rely on human mission control experts and are out of touch, far away, and on their own. The SRP also identified 11 new gaps and five new tasks. Although the SRP had an extremely large quantity of reading material prior to and during the meeting, we still did not feel we had an overview of the activities and tasks the astronauts would be performing in exploration missions. Without a detailed task analysis and taxonomy of activities the humans would be engaged in, we felt it was impossible to know whether the gaps and tasks were really sufficient to insure human safety, performance, and comfort in the exploration missions. The SRP had difficulty evaluating many of the gaps and tasks that were not as quantitative as those related to concrete physical danger such as excessive noise and vibration. Often the research tasks for cognitive risks that accompany poor task or