WorldWideScience

Sample records for safety program progress

  1. HTGR safety research program. Progress report, April--June 1975

    International Nuclear Information System (INIS)

    Kirk, W.L.

    1975-09-01

    Progress in HTGR safety research is reported under the following headings: fission product technology; primary coolant impurities; structural investigation; safety instrumentation and control systems; phenomena modeling and systems analysis. (JWR)

  2. Progress report - reports on reactor safety research programs sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1982-09-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC and the OECD. The reports are arranged in the sequence of their project numbers. (orig./HP) [de

  3. Fast reactor safety program. Progress report, January-March 1980

    International Nuclear Information System (INIS)

    1980-05-01

    The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development

  4. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J W; Boccio, J L; Diamond, D; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Higgins, J C; Weiss, A J [comp.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987.

  5. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988.

  6. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    International Nuclear Information System (INIS)

    Baum, J.W.; Boccio, J.L.; Diamond, D.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987

  7. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J [comp.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs.

  8. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs

  9. Waste Tank Organic Safety Program: Analytical methods development. Progress report, FY 1994

    International Nuclear Information System (INIS)

    Campbell, J.A.; Clauss, S.A.; Grant, K.E.

    1994-09-01

    The objectives of this task are to develop and document extraction and analysis methods for organics in waste tanks, and to extend these methods to the analysis of actual core samples to support the Waste Tank organic Safety Program. This report documents progress at Pacific Northwest Laboratory (a) during FY 1994 on methods development, the analysis of waste from Tank 241-C-103 (Tank C-103) and T-111, and the transfer of documented, developed analytical methods to personnel in the Analytical Chemistry Laboratory (ACL) and 222-S laboratory. This report is intended as an annual report, not a completed work

  10. General-purpose heat source project and space nuclear safety and fuels program. Progress report

    International Nuclear Information System (INIS)

    Maraman, W.J.

    1980-02-01

    Studies related to the use of 238 PuO 2 in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of LASL are presented. The three programs involved are: general-purpose heat source development; space nuclear safety; and fuels program. Three impact tests were conducted to evaluate the effects of a high temperature reentry pulse and the use of CBCF on impact performance. Additionally, two 238 PuO 2 pellets were encapsulated in Ir-0.3% W for impact testing. Results of the clad development test and vent testing are noted. Results of the environmental tests are summarized. Progress on the Stirling isotope power systems test and the status of the improved MHW tests are indicated. The examination of the impact failure of the iridium shell of MHFT-65 at a fuel pass-through continued. A test plan was written for vibration testing of the assembled light-weight radioisotopic heater unit. Progress on fuel processing is reported

  11. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    International Nuclear Information System (INIS)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis

  12. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    Energy Technology Data Exchange (ETDEWEB)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)

  13. Environment, safety and health progress assessment manual

    International Nuclear Information System (INIS)

    1992-12-01

    On June 27, 1989, the Secretary of Energy announced a 1O-Point Initiative to strengthen environment,safety, and health (ES ampersand H) programs, and waste management activities at involved conducting DOE production, research, and testing facilities. One of the points independent Tiger Team Assessments of DOE operating facilities. The Office of Special Projects (OSP), EH-5, in the Office of the Assistant Secretary for Environment, Safety and Health, EH-1, was assigned the responsibility to conduct the Tiger Team Assessments. Through June 1992, a total of 35 Tiger Team Assessments were completed. The Secretary directed that Corrective Action Plans be developed and implemented to address the concerns identified by the Tiger Teams. In March 1991, the Secretary approved a plan for assessments that are ''more focused, concentrating on ES ampersand H management, ES ampersand H corrective actions, self-assessment programs, and root-cause related issues.'' In July 1991, the Secretary approved the initiation of ES ampersand H Progress Assessments, as a followup to the Tiger Team Assessments, and in the continuing effort to institutionalize the self-assessment process and line management accountability in the ES ampersand H areas. This volume contains appendices to the Environment, Safety and Health Progress Assessment Manual

  14. Improving patient safety in radiology: a work in progress

    International Nuclear Information System (INIS)

    Sze, Raymond W.

    2008-01-01

    The purpose of this paper is to share the experiences, including successes and failures, as well as the ongoing process of developing and implementing a safety program in a large pediatric radiology department. Building a multidisciplinary pediatric radiology safety team requires successful recruitment of team members, selection of a team leader, and proper and ongoing training and tools, and protected time. Challenges, including thorough examples, are presented on improving pediatric radiology safety intradepartmentally, interdepartmentally, and institutionally. Finally, some major challenges to improving safety in pediatric radiology, and healthcare in general, are presented along with strategies to overcome these challenges. Our safety program is a work in progress; this article is a personal account and the reader is asked for tolerance of its occasional subjective tone and contents. (orig.)

  15. Environment, safety and health progress assessment manual

    International Nuclear Information System (INIS)

    1992-12-01

    On June 27, 1989, the Secretary of Energy announced a 10-Point Initiative to strengthen environment, safety, and health (ES ampersand H) programs, and waste management activities at DOE production, research, and testing facilities. One of the points involved conducting dent Tiger Team Assessments of DOE operating facilities. The Office of Special independent Projects (OSP), EH-5, in the Office of the Assistant Secretary for Environment, Safety and Health, EH-1, was assigned the responsibility to conduct the Tiger Team Assessments. Through June 1992, a total of 35 Tiger Team Assessments were completed. The Secretary directed that Corrective Action Plans be developed and implemented to address the concerns identified by the Tiger Teams. In March 1991, the Secretary approved a plan for assessments that are ''more focused, concentrating on ES ampersand H management, ES ampersand H corrective actions, self-assessment programs, and root-cause related issues.'' In July 1991, the Secretary approved the initiation of ES ampersand H Progress Assessments, as a followup to the Tiger Team Assessments, and in the continuing effort to institutionalize the self-assessment process and line management accountability in the ES ampersand H areas. This manual documents the processes to be used to perform the ES ampersand H Progress Assessments. It was developed based upon the lessons learned from Tiger Team Assessments, the two pilot Progress Assessments, and Progress Assessments that have been completed. The manual will be updated periodically to reflect lessons learned or changes in policy

  16. Environment, Safety and Health Progress Assessment of the Hanford Site

    International Nuclear Information System (INIS)

    1992-05-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the Hanford Site, in Richland, Washington. The assessment, which was conducted from May 11 through May 22, 1992, included a selective-review of the ES ampersand H management systems and programs of the responsible DOE Headquarters Program Offices the DOE Richland Field Office, and the site contractors. The ES ampersand H Progress Assessments are part of the Secretary of Energy's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the Hanford Site ES ampersand H Progress Assessment is to provide the Secretary with an independent assessment of the adequacy and effectiveness of the DOE and contractor management structures, resources, and systems to address ES ampersand H problems and requirements. They are not intended to be comprehensive compliance assessments of ES ampersand H activities. The point of reference for assessing programs at the Hanford Site was, for the most part, the Tiger Team Assessment of the Hanford Site, which was conducted from May 21 through July 18, 1990. A summary of issues and progress in the areas of environment, safety and health, and management is included

  17. Space Nuclear Safety Program. Progress report, March 1984

    International Nuclear Information System (INIS)

    Zocher, R.W.; George, T.G.

    1985-08-01

    This technical monthly report covers studies related to the use of 238 PuO 2 in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos Laboratory. They are divided into: general-purpose heat source, lightweight radioisotope heater unit, and safety technology program. 43 figs., 2 tabs

  18. Environment, Safety and Health progress assessment of the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    1993-08-01

    The ES ampersand H Progress Assessments are part of the Department's continuous improvement process throughout DOE and its contractor organizations. The purpose of the INEL ES ampersand H Progress Assessment is to provide the Department with concise independent information on the following: (1) change in culture and attitude related to ES ampersand H activities; (2) progress and effectiveness of the ES ampersand H corrective actions resulting from previous Tiger Team Assessments; (3) adequacy and effectiveness of the ES ampersand H self-assessment programs of the DOE line organizations and the site management and operating contractor; and (4) effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES ampersand H problems. It is not intended that this Progress Assessment be a comprehensive compliance assessments of ES ampersand H activities. The points of reference for assessing programs at the INEL were, for the most part, the 1991 INEL Tiger Team Assessment, the INEL Corrective Action Plan, and recent appraisals and self-assessments of INEL. Horizontal and vertical reviews of the following programmatic areas were conducted: Management: Corrective action program; self-assessment; oversight; directives, policies, and procedures; human resources management; and planning, budgeting, and resource allocation. Environment: Air quality management, surface water management, groundwater protection, and environmental radiation. Safety and Health: Construction safety, worker safety and OSHA, maintenance, packaging and transportation, site/facility safety review, and industrial hygiene

  19. Nondestructive Evaluation Program: Progress in 1986

    International Nuclear Information System (INIS)

    1987-07-01

    The increasing cost of equipment for power generating plants and the potential increases in productivity and safety available through rapidly developing Nondestructive Evaluation (NDE) technology led EPRI to initiate a Nondestructive Evaluation Program in 1974. To date, the major focus has been on light water reactor inspection problems; however, increased application to other systems is now under way. This report presents a comprehensive review of the EPRI effort in the NDE area. Most of the report consists of contractor-supplied progress reports on each current project. An organizational plan of the program is presented in overview. In addition, organization from several viewpoints is presented, e.g., in-service inspection operators, R and D personnel, and utility representatives. The report summarizes significant progress made since the previous EPRI Special Report NP-4315-SR was issued in May 1986. Section 1 contains information about the program organization, and the sections that follow contain contractor-supplied progress reports of each current project. The progress reports are grouped by plant components - pipe, pressure vessel, steam generator and boiler tubes, and turbine. In addition, Part 6 is devoted to discussions of technology transfer

  20. Progress report projects in the field of nuclear safety sponsered by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1980-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work at the GRS, within the framework of general information of the progress in reactor safety research. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC and the OECD. (orig./HP) [de

  1. Using Contemporary Leadership Skills in Medication Safety Programs.

    Science.gov (United States)

    Hertig, John B; Hultgren, Kyle E; Weber, Robert J

    2016-04-01

    The discipline of studying medication errors and implementing medication safety programs in hospitals dates to the 1970s. These initial programs to prevent errors focused only on pharmacy operation changes - and not the broad medication use system. In the late 1990s, research showed that faulty systems, and not faulty people, are responsible for errors and require a multidisciplinary approach. The 2013 ASHP Statement on the Role of the Medication Safety Leader recommended that medication safety leaders be integrated team members rather than a single point of contact. Successful medication safety programs must employ a new approach - one that embraces the skills of all health care team members and positions many leaders to improve safety. This approach requires a new set of leadership skills based on contemporary management principles, including followership, team-building, tracking and assessing progress, storytelling and communication, and cultivating innovation, all of which promote transformational change. The application of these skills in developing or changing a medication safety program is reviewed in this article.

  2. 2013 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-12-01

    The 2013 Annual Progress Report summarizes fiscal year 2013 activities and accomplishments by projects funded by the DOE Hydrogen Program. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing; technology validation; safety, codes and standards; market transformation; and systems analysis.

  3. 2014 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2014-11-01

    The 2014 Annual Progress Report summarizes fiscal year 2014 activities and accomplishments by projects funded by the DOE Hydrogen Program. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing; technology validation; safety, codes and standards; market transformation; and systems analysis.

  4. 2011 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-11-01

    The 2011 Annual Progress Report summarizes fiscal year 2011 activities and accomplishments by projects funded by the DOE Hydrogen Program. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing; technology validation; safety, codes and standards; education; market transformation; and systems analysis.

  5. Quarterly report on the ferrocyanide safety program for the period ending December 31, 1994

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-01-01

    This is the fifteenth quarterly report on the progress of active addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0. 60 refs

  6. Quarterly report on the Ferrocyanide Safety Program for the period ending September 30, 1995

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-10-01

    This is the eighteenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0

  7. 2015 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-12-23

    The 2015 Annual Progress Report summarizes fiscal year 2015 activities and accomplishments by projects funded by the DOE Hydrogen and Fuel Cells Program. It covers the program areas of hydrogen production; hydrogen delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes and standards; systems analysis; and market transformation.

  8. Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1995

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-07-01

    This is the seventeenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six pans of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented

  9. Waste isolation safety assessment program. Summary of FY-77 progress

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Greenborg, J.; Stottlemyre, J.A.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.

    1977-11-01

    Objective is to provide long-term safety information for the National Waste Terminal Storage Program. Work in FY 77 supported the development of the generic assessment method (release scenario analysis, release consequence analysis) and of the generic data base (waste form release rate data, radionuclide geochemical interaction data)

  10. Fusion Safety Program annual report, fiscal year 1984

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.

    1985-06-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1984. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. A report section titled ''Activities at the INEL'' includes progress reports on the tritium implantation experiment, tritium blanket permeation, volatilization of reactor alloys, plasma disruptions, a comparative blanket safety assessment, transient code development, and a discussion of the INEL's participation in the Tokamak Fusion Core Experiment (TFCX) design study. The report section titled ''Outside Contracts'' includes progress reports on tritium conversion by the Oak Ridge National Laboratory (ORNL), lithium-lead reactions by the Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by MIT, tritium retention by the University of Virginia, and activation product release by GA Technologies. A list of publications produced during the year and brief descriptions of activities planned for FY-1985 are also included

  11. 2016 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2017-03-09

    The 2016 Annual Progress Report summarizes fiscal year 2016 activities and accomplishments by projects funded by the DOE Hydrogen and Fuel Cells Program. It covers the program areas of hydrogen production; hydrogen delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes and standards; systems analysis; market transformation; and Small Business Innovation Research projects.

  12. Organic Tanks Safety Program: Advanced organic analysis FY 1996 progress report

    International Nuclear Information System (INIS)

    1996-09-01

    Major focus during the first part of FY96 was to evaluate using organic functional group concentrations to screen for energetics. Fourier transform infrared and Raman spectroscopy would be useful screening tools for determining C-H and COO- organic content in tank wastes analyzed in a hot cell. These techniques would be used for identifying tanks of potential safety concern that may require further analysis. Samples from Tanks 241-C-106 and -C-204 were analyzed; the major organic in C-106 was B2EHPA and in C-204 was TBP. Analyses of simulated wastes were also performed for the Waste Aging Studies Task; organics formed as a result of degradation were identified, and the original starting components were monitored quantitatively. Sample analysis is not routine and required considerable methods adaptation and optimization. Several techniques have been evaluated for directly analyzing chelator and chelator fragments in tank wastes: matrix-assisted laser desorption/ionization time-of-flight mass spectrometry and liquid chromatography with ultraviolet detection using Cu complexation. Although not directly funded by the Tanks Safety Program, the success of these techniques have implications for both the Flammable Gas and Organic Tanks Safety Programs

  13. Progress and safety aspects in process heat utilization from nuclear systems

    International Nuclear Information System (INIS)

    Barnert, H.

    1995-01-01

    Report about the Status and the Progress in the Various Programs and Projects in the Federal Republic of Germany in Process Heat Utilization from the High Temperature Reactor and on Recent Changes of the Atomic Law in the Federal Republic of Germany with Big Influence on the Safety of Nuclear Energy Technology. (author)

  14. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology. Progress report. Reported period: July 1 to December 31, 1984

    International Nuclear Information System (INIS)

    1985-05-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRS 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./HP) [de

  15. Integral Fast Reactor Program annual progress report, FY 1994

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

    1994-12-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R ampersand D

  16. US Department of Energy Environment, Safety and Health Progress Assessment of the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety, and Health (ES&H) Progress Assessment of the Nevada Test Site (NTS), Nye County, Nevada. The assessment, which was conducted from July 20 through August 4, 1992, included a selective review of the ES&H management systems and progress of the responsible DOE Headquarters Program Offices; the DOE Nevada Field Office (NV); and the site contractors. The ES&H Progress Assessments are part of the Secretary of Energy`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. This report presents a summary of issues and progress in the areas of environment, safety and health, and management.

  17. US Department of Energy Environment, Safety and Health Progress Assessment of the Nevada Test Site

    International Nuclear Information System (INIS)

    1992-08-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) Progress Assessment of the Nevada Test Site (NTS), Nye County, Nevada. The assessment, which was conducted from July 20 through August 4, 1992, included a selective review of the ES ampersand H management systems and progress of the responsible DOE Headquarters Program Offices; the DOE Nevada Field Office (NV); and the site contractors. The ES ampersand H Progress Assessments are part of the Secretary of Energy's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. This report presents a summary of issues and progress in the areas of environment, safety and health, and management

  18. Integral Fast Reactor Program. Annual progress report, FY 1992

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

  19. Status report of the US Department of Energy's International Nuclear Safety Program

    International Nuclear Information System (INIS)

    1994-12-01

    The US Department of Energy (DOE) implements the US Government's International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program's activities that have been completed as of September 1994 and discusses those activities currently in progress

  20. Safety research programs sponsored by Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Weiss, A.J.; Azarm, A.; Baum, J.W.

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988

  1. Integral Fast Reactor Program annual progress report, FY 1991

    International Nuclear Information System (INIS)

    1992-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  2. Integral Fast Reactor Program. Annual progress report, FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1994-10-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D.

  3. Integral Fast Reactor Program. Annual progress report, FY 1993

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1994-10-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D

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

    Energy Technology Data Exchange (ETDEWEB)

    Levin, A.E.

    1995-09-01

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

  5. The progress and issues of national nuclear and radiation safety supervision and MIS

    International Nuclear Information System (INIS)

    Zhou Kefei; Sun Guochen; Jiang Guang; Li Jingxi; Zhang Lin

    2009-01-01

    The article briefly describes the pre-planning construction of 'National Nuclear and Radiation Safety Supervision and Management Information System', Including the overall frame of the system and the main issues found in the work which affect and confine the progress of the program. Some recommendations are put forward. (authors)

  6. Highway Safety Program Manual: Volume 3: Motorcycle Safety.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…

  7. Progress of nuclear safety research, (1)

    International Nuclear Information System (INIS)

    Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

    1981-01-01

    The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

  8. Fusion Safety Program annual report, fiscal year 1983

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.

    1984-07-01

    The Fusion Safety Program major activities for Fiscal Year 1983 are summarized in this report. The program was initiated in FY 1979, with the Idaho National Engineering Laboratory (INEL) designated lead laboratory, and EG and G Idaho, inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., activities at the INEL includes progress reports and portions of papers on the tritium implantation experiment, tritium control systems, tritium release from solid breeding blankets, plasma disruptions, risk assessment, transient code development, data base development, and a discussion of participation in the blanket comparison and selection study. The section outside contracts includes progress reports and portions of papers on lithium-lead reactions by Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by the University of California at Los Angeles (UCLA) and MIT, tritium retention by the University of Virginia, and effects of plasma disruptions by MIT. A list of publications and planned fiscal year 1984 activities are also included

  9. Progress of nuclear safety research, (2)

    International Nuclear Information System (INIS)

    Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

    1981-01-01

    The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

  10. Assessing progress in the development of safety culture

    International Nuclear Information System (INIS)

    Rotaru, I.; Ghita, S.; Biro, L.

    2002-01-01

    This paper is focussed on the organizational culture and learning processes required for the implementation of all aspects of safety culture. There is no prescriptive formula for improving safety culture. However, some common characteristics and practices are emerging that can be adopted by organizations in order to make progress. The paper refers to some approaches that have been successful in a number of countries. The experience of the international nuclear industry in the development and improvement of safety culture could be extended and found useful in other nuclear activities, irrespective of scale. The examples given of specific practice cover a wide range of activities including analysis of events, the regulatory approach on safety culture, employee participation and safety performance measures. Many of these practices may be relevant to smaller organizations and could contribute to improving safety culture, whatever the size of the organization. The most effective approach is to pursue a range of practices that can be mutually supportive in the development of a progressive safety culture, supported by professional standards, organizational and management commitment. Some guidance is also given on the assessment of safety culture and on the detection of a weakening safety culture. Few suggestions for accelerating the safety culture development and improvement process are also provided. (author)

  11. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    Energy Technology Data Exchange (ETDEWEB)

    GARVIN, L. J.; JENSEN, M. A.

    2004-04-13

    This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

  12. Assessing progress in the development of safety culture

    International Nuclear Information System (INIS)

    Rotaru, Ioan; Ghita, Sorin

    1999-01-01

    The concept of safety culture was introduced by the International Nuclear Safety Advisory Group (INSAG) in the Summary Report on the Post-Accident Meeting on the Chernobyl Accident in 1986. The concept was further expanded in the 1988 INSAG-3 report, Basic Safety Principles for Nuclear Power Plants, and again in 1991 in the INSAG-4 report. Recognizing the increasing role that safety culture is expected to play in nuclear installations worldwide, the Convention on Nuclear Safety states the Contracting Parties' desire 'to promote an effective nuclear safety culture'. The concept of safety culture is defined in INSAG-4 as follows: Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Safety culture is also an amalgamation of values, standards, morals and norms of acceptable behaviour. These are aimed at maintaining a self disciplined approach to the enhancement of safety beyond legislative and regulatory requirements. Therefore, the safety culture has to be inherent in the thoughts and actions of all the individuals at every level in an organization. The leadership provided by top management is crucial. Safety culture applies to conventional and personal safety as well as nuclear safety. All safety consideration are affected by common points of beliefs, attitudes, behaviour, and cultural differences, closely linked to a shared system of values and standards. The paper poses questions and tries to find answers relative to issues like: - how to assess progress; - specific organizational indicators of a progressive safety culture; - detection of incipient weaknesses in safety culture (organizational issues, employee issues, technology issues); - revitalizing a weakened safety culture; - overall assesment of safety culture; - general evaluation model. In conclusion, there is no consistent and

  13. Environment, safety and Health Progress Assessment of the Rocky Flats Plant

    International Nuclear Information System (INIS)

    1993-05-01

    This report documents the result of the US Department of Energy's (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the DOE Rocky Flats Plant (RFP) in Golden, Colorado. The assessment, which was conducted during the period of May 17 through May 28, 1993, included a selective review of the ES ampersand H management systems and programs of the responsible DOE Headquarters Program Offices (Defense Programs (DP) and Environmental Restoration and Waste Management (EM)), the DOE Rocky Flats Office (RFO), and the site contractor, EG ampersand G Rocky Flats, Inc. (EG ampersand G). Despite the near constant state of flux under which RFP has been required to operate, the Progress Assessment Team has concluded that significant progress has been made in correcting the deficiencies identified in the 1989 Assessment and in responding responsibly to regulations, and DOE directives and guidance that have been issued since that time. The Team concluded that the improvements have been concentrated in the activities associated with plutonium facilities and in regulatory driven programs. Much remains to be done with respect to implementing on a sitewide basis those management systems that anchor an organization's pursuit of continuous ES ampersand H improvement. Furthermore the Team concluded that the pace of improvement has been constrained by a combination of factors that have limited the site's ability to manage change in the pursuit of sitewide ES ampersand H excellence

  14. Safety performance indicators program

    International Nuclear Information System (INIS)

    Vidal, Patricia G.

    2004-01-01

    In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

  15. A summary of the program and progress to 1984 December of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1986-08-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fifth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1984 are described in this report. 74 refs

  16. Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

    Energy Technology Data Exchange (ETDEWEB)

    Blakely, D [Alberta Environment, Edmonton, AB (Canada)

    2009-07-01

    Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

  17. Environment, safety and health progress assessment of the Fernald Environmental Management Project (FEMP)

    International Nuclear Information System (INIS)

    1991-11-01

    This report documents the results of the Environment, Safety, and Health (ES ampersand H) Progress Assessment of the Fernald Environmental Management Project (FEMP), Fernald, Ohio, conducted from October 15 through October 25, 1991. The Secretary of Energy directed that small, focused, ES ampersand H Progress Assessments be performed as part of the continuing effort to institutionalize line management accountability and the self-assessment process in the areas of ES ampersand H. The FEMP assessment is the pilot assessment for this new program. The objectives for the FEMP ES ampersand H Progress Assessment were to assess: (1) how the FEMP has progressed since the 1989 Tiger Assessment; (2) how effectively the FEMP has corrected specific deficiencies and associated root causes identified by that team; and (3) whether the current organization, resources, and systems are sufficient to proactively manage ES ampersand H issues

  18. Environment, safety and health progress assessment of the Fernald Environmental Management Project (FEMP)

    Energy Technology Data Exchange (ETDEWEB)

    1991-11-01

    This report documents the results of the Environment, Safety, and Health (ES&H) Progress Assessment of the Fernald Environmental Management Project (FEMP), Fernald, Ohio, conducted from October 15 through October 25, 1991. The Secretary of Energy directed that small, focused, ES&H Progress Assessments be performed as part of the continuing effort to institutionalize line management accountability and the self-assessment process in the areas of ES&H. The FEMP assessment is the pilot assessment for this new program. The objectives for the FEMP ES&H Progress Assessment were to assess: (1) how the FEMP has progressed since the 1989 Tiger Assessment; (2) how effectively the FEMP has corrected specific deficiencies and associated root causes identified by that team; and (3) whether the current organization, resources, and systems are sufficient to proactively manage ES&H issues.

  19. Annual progress report 1981

    International Nuclear Information System (INIS)

    1982-01-01

    This annual progress report of the CEA Protection and Nuclear Safety Institut outlines a brief description of the progress made in each section of the Institut. Research activities of the Protection department include, radiation effects on man, radioecology and environment radioprotection techniques. Research activities of the Nuclear Safety department include, reactor safety analysis, fuel cycle facilities safety analysis, safety research programs. The third section deals with nuclear material security including security of facilities, security of nuclear material transport and monitoring of nuclear material management [fr

  20. Liquefied Gaseous Fuels Safety and Environmental Control Assessment Program: second status report

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    The Assistant Secretary for Environment has responsibility for identifying, characterizing, and ameliorating the environmental, health, and safety issues and public concerns associated with commercial operation of specific energy systems. The need for developing a safety and environmental control assessment for liquefied gaseous fuels was identified by the Environmental and Safety Engineering Division as a result of discussions with various governmental, industry, and academic persons having expertise with respect to the particular materials involved: liquefied natural gas, liquefied petroleum gas, hydrogen, and anhydrous ammonia. This document is arranged in three volumes and reports on progress in the Liquefied Gaseous Fuels (LGF) Safety and Environmental Control Assessment Program made in Fiscal Year (FY)-1979 and early FY-1980. Volume 1 (Executive Summary) describes the background, purpose and organization of the LGF Program and contains summaries of the 25 reports presented in Volumes 2 and 3. Annotated bibliographies on Liquefied Natural Gas (LNG) Safety and Environmental Control Research and on Fire Safety and Hazards of Liquefied Petroleum Gas (LPG) are included in Volume 1.

  1. Status and progress of the RERTR program

    International Nuclear Information System (INIS)

    Travelli, A.

    1996-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1996 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1995 in collaboration with its many international partners. Significant progress has been made during the past year in each of the three areas that the delegates to last year's RERTR meeting chose to address, in their letter to President Clinton, as requiring special attention. (1) In the area of U.S. acceptance of spent fuel from foreign research reactors, a second shipment of 99 urgent-relief spent fuel elements was completed. The Final Environmental Impact Statement was published in February 1996, and the Record of Decision was published in May 1996. The first shipments under the Record of Decision, containing 280 spent fuel elements, were received at the Savannah River Site in September 1996. (2) In the area of advanced fuel development, adequate funding and guidance were received by the RERTR program in March 1996. Fuel development activities are now in progress, including procurement of equipment, screening of candidate materials, and preparations for the production of a first series of microplates. The first irradiations are planned to begin in the Advanced Test Reactor. in Idaho, during April 1997. (3) In the area of conversion of DOE research reactors, the RERTR program has been tasked by the Department of Energy to assess the feasibility of converting to LEU fuel each of the DOE research reactors which currently use HEU fuel. A preliminary assessment will be presented at this meeting. Significant progress has been made by the Russian RERTR program, which aims to develop and demonstrate within the next five years the technical means needed to convert Russian-supplied research reactors to LEU fuels. The study of an alternative LEU core for the FRM-II design has been extended to address, with excellent results

  2. Health and Safety Research Division progress report, October 1, 1988--March 31, 1990

    International Nuclear Information System (INIS)

    1990-09-01

    The Health and Safety Research Division (HASRD) of the Oak Ridge National Laboratory (ORNL) continues to maintain an outstanding program of basic and applied research displaying a high level of creativity and achievement as documented by awards, publications, professional service, and successful completion of variety of projects. Our focus is on human health and the scientific basis for measurement and assessment of health-related impacts of energy technologies. It is our custom to publish a division progress report every 18 months that summarizes our programmatic progress and other measures of achievement over the reporting period. Since it is not feasible to summarize in detail all of our work over the period covered by this report (October 1, 1988, to March 30, 1990), we intend this document to point the way to the expensive open literature that documents our findings. During the reporting period the Division continued to maintain strong programs in its traditional areas of R ampersand D, but also achieved noteworthy progress in other areas. Much of the Division's work on site characterization, development of new field instruments, compilation of data bases, and methodology development fits into this initiative. Other new work in tunneling microscopy in support of DOE's Human Genome Program and the comprehensive R ampersand D work related to surface-enhanced Raman spectroscopy have attained new and exciting results. These examples of our progress and numerous other activities are highlighted in this report

  3. Health and Safety Research Division progress report, October 1, 1988--March 31, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-01

    The Health and Safety Research Division (HASRD) of the Oak Ridge National Laboratory (ORNL) continues to maintain an outstanding program of basic and applied research displaying a high level of creativity and achievement as documented by awards, publications, professional service, and successful completion of variety of projects. Our focus is on human health and the scientific basis for measurement and assessment of health-related impacts of energy technologies. It is our custom to publish a division progress report every 18 months that summarizes our programmatic progress and other measures of achievement over the reporting period. Since it is not feasible to summarize in detail all of our work over the period covered by this report (October 1, 1988, to March 30, 1990), we intend this document to point the way to the expensive open literature that documents our findings. During the reporting period the Division continued to maintain strong programs in its traditional areas of R D, but also achieved noteworthy progress in other areas. Much of the Division's work on site characterization, development of new field instruments, compilation of data bases, and methodology development fits into this initiative. Other new work in tunneling microscopy in support of DOE's Human Genome Program and the comprehensive R D work related to surface-enhanced Raman spectroscopy have attained new and exciting results. These examples of our progress and numerous other activities are highlighted in this report.

  4. High-temperature gas-cooled reactor safety studies. Progress report for January 1, 1974--June 30, 1975

    International Nuclear Information System (INIS)

    Cole, T.E.; Sanders, J.P.; Kasten, P.R.

    1977-07-01

    Progress is reported in the following areas: systems and safety analysis; fission product technology; primary coolant technology; seismic and vibration technology; confinement components; primary system materials technology; safety instrumentation; loss of flow accident analysis using HEATUP code; use of coupled-conduction-convection model for core thermal analysis; development of multichannel conduction-convection program HEXEREI; cooling system performance after shutdown; core auxiliary cooling system performance; development of FLODIS code; air ingress into primary systems following DBDA; performance of PCRV thermal barrier cover plates; temperature limits for fuel particle coating failure; tritium distribution and release in HTGR; energy release to PCRV during DBDA; and mathematical models for HTGR reactor safety studies

  5. Health, Safety, and Environment Division: Annual progress report 1987

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.A. (comp.)

    1988-04-01

    The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help develop better occupational health and safety practices.

  6. Health, Safety, and Environment Division: Annual progress report 1987

    International Nuclear Information System (INIS)

    Rosenthal, M.A.

    1988-04-01

    The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help develop better occupational health and safety practices

  7. Elements of a nuclear criticality safety program

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1995-01-01

    Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance

  8. LMFBR aerosol release and transport program. Quarterly progress report, July-September 1981

    International Nuclear Information System (INIS)

    Kress, T.S.; Tobias, M.L.

    1982-01-01

    This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Office of Nuclear Regulatory Research, Division of Accident Evaluation of the Nuclear Regulatory Commission for the period July-September 1981. Topics discussed include (1) preparations for under-sodium tests at the Fast Aerosol Simulant Test Facility, (2) progress in interpretation of Oak Ridge National Laboratory-Sandia Laboratory normalization test results, (3) U 3 O 8 in steam (light-water reactor accident) aerosol experiments conducted in the Nuclear Safety Power Plant, (4) experiments on B 2 O 3 and SiO 2 aerosols at the Containment Research Installation-II Facility, (5) fuel-melting tests in small-scale experimental facilities for the core-melt aerosol program, (6) analytical comparison of simple adiabatic nonlinear and linear analytical models of bubble oscillation phenomena with experimental data

  9. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The

  10. 10 CFR 70.62 - Safety program and integrated safety analysis.

    Science.gov (United States)

    2010-01-01

    ...; (iv) Potential accident sequences caused by process deviations or other events internal to the... have experience in nuclear criticality safety, radiation safety, fire safety, and chemical process... this safety program; namely, process safety information, integrated safety analysis, and management...

  11. A Laboratory Safety Program at Delaware.

    Science.gov (United States)

    Whitmyre, George; Sandler, Stanley I.

    1986-01-01

    Describes a laboratory safety program at the University of Delaware. Includes a history of the program's development, along with standard safety training and inspections now being implemented. Outlines a two-day laboratory safety course given to all graduate students and staff in chemical engineering. (TW)

  12. Progress report: nuclear safety and radiation protection in France in 2005

    International Nuclear Information System (INIS)

    2007-01-01

    The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

  13. Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

    International Nuclear Information System (INIS)

    Berven, B.A.

    1993-09-01

    This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration

  14. Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berven, B.A.

    1993-09-01

    This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration.

  15. Environment, Safety and Health Progress Assessment of the Argonne Illinois Site

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This report documents the results of the US Department of Energy (DOE) Environment, Safety and Health (ES&H) Progress Assessment of the Argonne Illinois Site (AIS), near Chicago, Illinois, conducted from October 25 through November 9, 1993. During the Progress Assessment, activities included a selective review of the ES&H management systems and programs with principal focus on the DOE Office of Energy Research (ER); CH, which includes the Argonne Area Office; the University of Chicago; and the contractor`s organization responsible for operation of Argonne National Laboratory (ANL). The ES&H Progress Assessments are part of DOE`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the AIS ES&H Progress Assessment was to provide the Secretary of Energy, senior DOE managers, and contractor management with concise independent information on the following: change in culture and attitude related to ES&H activities; progress and effectiveness of the ES&H corrective actions resulting from the previous Tiger Team Assessment; adequacy and effectiveness of the ES&H self-assessment process of the DOE line organizations, the site management, and the operating contractor; and effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES&H problems and new ES&H initiatives.

  16. Environment, Safety and Health Progress Assessment of the Argonne Illinois Site

    International Nuclear Information System (INIS)

    1993-11-01

    This report documents the results of the US Department of Energy (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the Argonne Illinois Site (AIS), near Chicago, Illinois, conducted from October 25 through November 9, 1993. During the Progress Assessment, activities included a selective review of the ES ampersand H management systems and programs with principal focus on the DOE Office of Energy Research (ER); CH, which includes the Argonne Area Office; the University of Chicago; and the contractor's organization responsible for operation of Argonne National Laboratory (ANL). The ES ampersand H Progress Assessments are part of DOE's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the AIS ES ampersand H Progress Assessment was to provide the Secretary of Energy, senior DOE managers, and contractor management with concise independent information on the following: change in culture and attitude related to ES ampersand H activities; progress and effectiveness of the ES ampersand H corrective actions resulting from the previous Tiger Team Assessment; adequacy and effectiveness of the ES ampersand H self-assessment process of the DOE line organizations, the site management, and the operating contractor; and effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES ampersand H problems and new ES ampersand H initiatives

  17. Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

    Energy Technology Data Exchange (ETDEWEB)

    Blakely, D. [Alberta Environment, Edmonton, AB (Canada)

    2009-07-01

    Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

  18. 77 FR 70409 - System Safety Program

    Science.gov (United States)

    2012-11-26

    ...-0060, Notice No. 2] 2130-AC31 System Safety Program AGENCY: Federal Railroad Administration (FRA... rulemaking (NPRM) published on September 7, 2012, FRA proposed regulations to require commuter and intercity passenger railroads to develop and implement a system safety program (SSP) to improve the safety of their...

  19. University Safety Culture: A Work-in-Progress?

    Science.gov (United States)

    Lyons, Michael

    2016-01-01

    Safety management systems in Australian higher education organisations are under-researched. Limited workplace safety information can be found in the various reports on university human resources benchmarking programs, and typically they show only descriptive statistics. With the commencement of new consultation-focused regulations applying to…

  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. Aviation Safety/Automation Program Conference

    Science.gov (United States)

    Morello, Samuel A. (Compiler)

    1990-01-01

    The Aviation Safety/Automation Program Conference - 1989 was sponsored by the NASA Langley Research Center on 11 to 12 October 1989. The conference, held at the Sheraton Beach Inn and Conference Center, Virginia Beach, Virginia, was chaired by Samuel A. Morello. The primary objective of the conference was to ensure effective communication and technology transfer by providing a forum for technical interchange of current operational problems and program results to date. The Aviation Safety/Automation Program has as its primary goal to improve the safety of the national airspace system through the development and integration of human-centered automation technologies for aircraft crews and air traffic controllers.

  2. Progress of nuclear safety research - 2005

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

    2006-03-01

    The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

  3. AEC controlled area safety program

    Energy Technology Data Exchange (ETDEWEB)

    Hendricks, D W [Nevada Operations Office, Atomic Energy Commission, Las Vegas, NV (United States)

    1969-07-01

    The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)

  4. AEC controlled area safety program

    International Nuclear Information System (INIS)

    Hendricks, D.W.

    1969-01-01

    The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)

  5. Fusion safety program plan

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.; Herring, J.S.

    1980-09-01

    The program plan consists of research that has been divided into 13 different areas. These areas focus on the radioactive inventories that are expected in fusion reactors, the energy sources potentially available to release a portion of these inventories, and analysis and design techniques to assess and ensure that the safety risks associated with operation of magnetic fusion facilities are acceptably low. The document presents both long-term program requirements that must be fulfilled as part of the commercialization of fusion power and a five-year plan for each of the 13 different program areas. Also presented is a general discussion of magnetic fusion reactor safety, a method for establishing priorities in the program, and specific priority ratings for each task in the five-year plan

  6. Annual report on reactor safety research projects. Reporting period 2011. Progress report

    International Nuclear Information System (INIS)

    2011-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  7. Annual report on reactor safety research projects. Reporting period 2014. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  8. Annual report on reactor safety research projects. Reporting period 2013. Progress report

    International Nuclear Information System (INIS)

    2013-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  9. Annual report on reactor safety research projects. Reporting period 2015. Progress report

    International Nuclear Information System (INIS)

    2015-01-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft tor Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are ·' prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. it has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  10. Solar lease grant program. Technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    Progress on a lease program for the installation of a solar water heater with no installation charge is reported. Information on the announcement of the program, the selection of participants, the contractural agreement, progress on installation of equipment, monitoring, and evaluation is summarized. The status of the budget concerned with the program is announced. Forms used for applications for the program and an announcement from Resource Alternatives for Cilco customers are presented.

  11. Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

  12. Implementation of a Radiological Safety Coach program

    Energy Technology Data Exchange (ETDEWEB)

    Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

    1998-02-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

  13. Implementation of a Radiological Safety Coach program

    International Nuclear Information System (INIS)

    Konzen, K.K.

    1998-01-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets

  14. 1985. Annual progress report

    International Nuclear Information System (INIS)

    1986-01-01

    This annual progress report of the CEA Protection and Nuclear Safety Institut outlines a description of the progress made in each sections of the Institut Research activities of the different departments include: reactor safety analysis, fuel cycle facilities analysis; and associated safety research programs (criticality, sites, transport ...), radioecology and environmental radioprotection techniques; data acquisition on radioactive waste storage sites; radiation effects on man, studies on radioprotection techniques; nuclear material security including security of facilities, security of nuclear material transport, and monitoring of nuclear material management; nuclear facility decommissioning; and finally the public information [fr

  15. Public Health Service Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    McBride, J R [Southwestern Radiological Health Laboratory, Las Vegas, NV (United States)

    1969-07-01

    Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

  16. Public Health Service Safety Program

    International Nuclear Information System (INIS)

    McBride, J.R.

    1969-01-01

    Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

  17. General-purpose heat source project and space nuclear safety and fuels program. Progress report

    International Nuclear Information System (INIS)

    Maraman, W.J.

    1979-12-01

    This formal monthly report covers the studies related to the use of 238 PuO 2 in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are general-purpose heat source development and space nuclear safety and fuels. Most of the studies discussed hear are of a continuing nature. Results and conclusions described may change as the work continues

  18. A web-based tool for the Comprehensive Unit-based Safety Program (CUSP).

    Science.gov (United States)

    Pronovost, Peter J; King, Jay; Holzmueller, Christine G; Sawyer, Melinda; Bivens, Shauna; Michael, Michelle; Haig, Kathy; Paine, Lori; Moore, Dana; Miller, Marlene

    2006-03-01

    An organization's ability to change is driven by its culture, which in turn has a significant impact on safety. The six-step Comprehensive Unit-Based Safety Program (CUSP) is intended to improve local culture and safety. A Web-based project management tool for CUSP was developed and then pilot tested at two hospitals. HOW ECUSP WORKS: Once a patient safety concern is identified (step 3), a unit-level interdisciplinary safety committee determines issue criticality and starts up the projects (step 4), which are managed using project management tools within eCUSP (step 5). On a project's completion, the results are disseminated through a shared story (step 6). OSF St. Joseph's Medical Center-The Medical Birthing Center (Bloomington, Illinois), identified 11 safety issues, implemented 11 projects, and created 9 shared stories--including one for its Armband Project. The Johns Hopkins Hospital (Baltimore) Medical Progressive Care (MPC4) Unit identified 5 safety issues and implemented 4 ongoing projects, including the intravenous (IV) Tubing Compliance Project. The eCUSP tool's success depends on an organizational commitment to creating a culture of safety.

  19. Nuclear reactor safety. Quarterly progress report, October 1--December 31, 1977

    International Nuclear Information System (INIS)

    Jackson, J.F.; Stevenson, M.G.

    1978-02-01

    Progress in reactor safety research is summarized. LWR studies include TRAC code development for thermal-hydraulic analysis of accidents, containment systems evaluation, and safety experiments. LMFBR studies include SIMMER code development and applications, modeling of core disruptive accidents, and safety test facilities studies. HTGR safety studies cover fission product release and transport, structural evaluation, phenomena modeling, systems analysis, and accident delineation. GCFR studies are focussed on core disruptive testing

  20. Environmental and Occupational Safety Division annual progress report for 1984

    International Nuclear Information System (INIS)

    1985-11-01

    Over 950 radiation workers were monitored at ORNL for both internal and external exposure to ionizing radiation and radioactive materials in 1984, and no employee exceeded 50% of the applicable DOE dose limit. No internal exposure exceeded 10% of the maximum permissible organ burden, as determined by in-vivo gamma spectrometry. Dose readings from 5000 TLDs and 136,000 pocket meters were determined, and more than 5800 calibrations were performed on these devices. Approximately 82,000 radioassays were performed; among these were 1500 urinalyses and 3000 radiochemical analyses. Over 3000 calibrations were performed for approximately 2000 portable and fixed survey instruments. Response teams were identified in support of the Radiological Assistance Program (RAP). Documentation, procedures, and equipment for the RAP vehicle were upgraded. A long-range environmental plan was issued early in the year and again in June 1984 to document the scope and justification for each project. The DEM is developing an environmental information system for managing DOE-ORO and ORNL environmental data. Five hundred eighty-four waste disposal requests containing 5769 items were handled by the Hazardous Materials Control Group during 1984. The Office of Operational Safety made significant progress in the completion of Safety Analysis Reports for existing facilities. The Radiation and Safety Surveys Department is becoming increasingly involved in work resulting in facility improvement, repair, or upgrade as well as decontamination and decommissioning of older facilities

  1. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1985-10-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (research coordination department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./PW) [de

  2. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1989-06-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB Forschungsbetreuung (Research Coordination Department) at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  3. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1984-09-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRS 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./HP) [de

  4. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1988-10-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB Forschungsbetreuung (research coordination department) at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  5. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1989-11-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB Forschungsbetreuung (Research Coordination Department) at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  6. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology

    International Nuclear Information System (INIS)

    1993-09-01

    Each progress report presents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  7. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1988-06-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB Forschungsbetreuung (research coordination department) at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  8. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology

    International Nuclear Information System (INIS)

    1992-09-01

    Each progress report presents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communitites) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  9. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology

    International Nuclear Information System (INIS)

    1993-03-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977-1980 of the BMFT. Another table uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP) [de

  10. NASA Aviation Safety Program Systems Analysis/Program Assessment Metrics Review

    Science.gov (United States)

    Louis, Garrick E.; Anderson, Katherine; Ahmad, Tisan; Bouabid, Ali; Siriwardana, Maya; Guilbaud, Patrick

    2003-01-01

    The goal of this project is to evaluate the metrics and processes used by NASA's Aviation Safety Program in assessing technologies that contribute to NASA's aviation safety goals. There were three objectives for reaching this goal. First, NASA's main objectives for aviation safety were documented and their consistency was checked against the main objectives of the Aviation Safety Program. Next, the metrics used for technology investment by the Program Assessment function of AvSP were evaluated. Finally, other metrics that could be used by the Program Assessment Team (PAT) were identified and evaluated. This investigation revealed that the objectives are in fact consistent across organizational levels at NASA and with the FAA. Some of the major issues discussed in this study which should be further investigated, are the removal of the Cost and Return-on-Investment metrics, the lack of the metrics to measure the balance of investment and technology, the interdependencies between some of the metric risk driver categories, and the conflict between 'fatal accident rate' and 'accident rate' in the language of the Aviation Safety goal as stated in different sources.

  11. Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

    International Nuclear Information System (INIS)

    Chung, Dae Wook

    2011-01-01

    Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

  12. Pressure Safety Program Implementation at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

    2013-01-01

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply

  13. United States program for the safety assessment of geologic disposal of commercial radioactive wastes

    International Nuclear Information System (INIS)

    Claiborne, H.C.

    1977-01-01

    The safe disposal of commercial radioactive wastes in deep geologic formations is the goal of the National Waste Terminal Storage (NWTS) Program. A comprehensive safety assessment program has been established which will proceed on a schedule consistent with the start-up of two waste repositories in late 1985. Safety assessment begins with selection of a disposal site; that is, all geologic and hydrologic factors must indicate long-term stability of the formation and prospective isolation of wastes from circulating around waters for hundreds of thousands of years. The long-term stability of each site must be demonstrated by sophisticated rock mechanics analyses. To help provide answers on the mechanism and consequences of an unlikely breach in the integrity of the repository, a Waste Isolation Safety Assessment Program (WISAP) is being sponsored at the Battelle Pacific Northwest Laboratories. Methods and data necessary to characterize the safety of generic geological waste disposal concepts, which are to be applied in the assessment of specific sties, will be developed. Other long-term safety-related studies that complement WISAP are in progress, for example, borehole plugging, salt dissolutioning, and salt transport in vertical boreholes. Requirements for licensing are in the process of being formulated by the NRC

  14. National Ignition Facility Project Site Safety Program

    International Nuclear Information System (INIS)

    Dun, C

    2003-01-01

    This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

  15. Clear progress in nuclear safety worldwide: Convention on nuclear safety concludes

    International Nuclear Information System (INIS)

    2002-01-01

    It has been concluded that a significant progress has been observed in a number of key areas, such as strengthened legislation, regulatory independence, the availability of financial resources, enhanced emergency preparedness and safety improvements at nuclear power plants built to earlier standards. The objective of the Convention is to achieve and maintain a high level of nuclear safety worldwide. During the two week Review Meeting, parties engaged in a 'peer review' process in which the National Reports from individual States were collectively examined and discussed, with written replies provided to all the questions raised. Clear improvement was noted in the quality of the National Reports, the number of questions and the openness and quality of discussion and answers. The Contracting Parties praised the IAEA's various safety review missions and services, which they use widely to help enhance the effectiveness of their national safety arrangements. Forty-six contracting parties participated at the Review Meeting with over 400 delegates attending, including many heads and senior officers from regulatory bodies and experts from industry. To date, the Convention has been signed by sixty-five States and ratified by fifty-four, representing 428 of the 448 nuclear power reactors worldwide

  16. The RERTR [Reduced Enrichment Research and Test Reactor] Program: Progress and plans

    International Nuclear Information System (INIS)

    Travelli, A.

    1987-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results, and new developments which occurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U 3 Si 2 -Al and U 3 Si-Al fuels, was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U 3 Si 2 -Al fuel at 4.8 g U/cm 3 was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40% average burnup. Good progress was made in the area of LEU usage for the production of fission 99 Mo, and in the coordination of safety evaluations related to LEU conversions of US university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U 3 Si-Al with 19.75% enrichment and U 3 Si 2 -Al with 45% enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR Program

  17. Fusion safety program Annual report, Fiscal year 1995

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

    1995-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

  18. Gap Analysis Approach for Construction Safety Program Improvement

    Directory of Open Access Journals (Sweden)

    Thanet Aksorn

    2007-06-01

    Full Text Available To improve construction site safety, emphasis has been placed on the implementation of safety programs. In order to successfully gain from safety programs, factors that affect their improvement need to be studied. Sixteen critical success factors of safety programs were identified from safety literature, and these were validated by safety experts. This study was undertaken by surveying 70 respondents from medium- and large-scale construction projects. It explored the importance and the actual status of critical success factors (CSFs. Gap analysis was used to examine the differences between the importance of these CSFs and their actual status. This study found that the most critical problems characterized by the largest gaps were management support, appropriate supervision, sufficient resource allocation, teamwork, and effective enforcement. Raising these priority factors to satisfactory levels would lead to successful safety programs, thereby minimizing accidents.

  19. Health, safety and environmental research program

    International Nuclear Information System (INIS)

    Dinner, P.J.

    1983-01-01

    This report outlines the Health, Safety and Environmental Research Program being undertaken by the CFFTP. The Program objectives, relationship to other CFFTP programs, implementation plans and expected outputs are stated. Opportunities to build upon the knowledge and experience gained in safely managing tritium in the CANDU program, by addressing generic questions pertinent to tritium safety for fusion facilities, are identified. These opportunities exist across a broad spectrum of issues covering the anticipated behaviour of tritium in fusion facilities, the surrounding environment and in man

  20. Seismic safety margins research program overview

    International Nuclear Information System (INIS)

    Tokarz, F.J.; Smith, P.D.

    1978-01-01

    A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I

  1. Nuclear Criticality Safety Department Qualification Program

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

  2. National HTGR safety program

    International Nuclear Information System (INIS)

    Davis, D.E.; Kelley, A.P. Jr.

    1982-01-01

    This paper presents an overview of the National HTGR Program in the US with emphasis on the safety and licensing strategy being pursued. This strategy centers upon the development of an integrated approach to organizing and classifying the functions needed to produce safe and economical nuclear power production. At the highest level, four plant goals are defined - Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness. The HTGR features which support the attainment of each goal are described and finally a brief summary is provided of the current status of the principal safety development program supporting the validation of the four plant goals

  3. Spent Fuel and Waste Management Technology Development Program. Annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Bryant, J.W.

    1994-01-01

    This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

  4. Effective safety training program design

    International Nuclear Information System (INIS)

    Chilton, D.A.; Lombardo, G.J.; Pater, R.F.

    1991-01-01

    Changes in the oil industry require new strategies to reduce costs and retain valuable employees. Training is a potentially powerful tool for changing the culture of an organization, resulting in improved safety awareness, lower-risk behaviors and ultimately, statistical improvements. Too often, safety training falters, especially when applied to pervasive, long-standing problems. Stepping, Handling and Lifting injuries (SHL) more commonly known as back injuries and slips, trips and falls have plagued mankind throughout the ages. They are also a major problem throughout the petroleum industry. Although not as widely publicized as other immediately-fatal accidents, injuries from stepping, materials handling, and lifting are among the leading causes of employee suffering, lost time and diminished productivity throughout the industry. Traditional approaches have not turned the tide of these widespread injuries. a systematic safety training program, developed by Anadrill Schlumberger with the input of new training technology, has the potential to simultaneously reduce costs, preserve employee safety, and increase morale. This paper: reviews the components of an example safety training program, and illustrates how a systematic approach to safety training can make a positive impact on Stepping, Handling and Lifting injuries

  5. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    International Nuclear Information System (INIS)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T

  6. The Department of Energy nuclear criticality safety program

    International Nuclear Information System (INIS)

    Felty, J.R.

    2004-01-01

    This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

  7. DOE Defense Program (DP) safety programs. Final report, Task 003

    International Nuclear Information System (INIS)

    1998-01-01

    The overall objective of the work on Task 003 of Subcontract 9-X52-W7423-1 was to provide LANL with support to the DOE Defense Program (DP) Safety Programs. The effort included the identification of appropriate safety requirements, the refinement of a DP-specific Safety Analysis Report (SAR) Format and Content Guide (FCG) and Comprehensive Review Plan (CRP), incorporation of graded approach instructions into the guidance, and the development of a safety analysis methodologies document. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective is provided here

  8. IAEA Operational Safety Team (OSART) Reviews Progress at Fessenheim Nuclear Power Plant, France

    International Nuclear Information System (INIS)

    2011-01-01

    . A systematic three-year training course revision program is in place now which ensures that the latest operating experience is used for learning purposes; The plant has reached satisfactory progress in eliminating industrial safety hazards. Actions include installation of protective screens over hot pipes or equipment, installation of guards on rotating equipment and elimination of tripping hazards particularly due to loose extension cords; and Insufficient progress has been made on the recommendation to have a person on the site at all times who is authorized to initiate an appropriate on-site response plan promptly and without consultation. It is noted that the practice at Fessenheim NPP is the same as the practice applied at other EDF plants and it is agreed by the French regulatory body ASN. The team delivered a draft of its findings to Fessenheim management in the form of 'Technical Notes' for factual comments. These notes, along with any comments from Fessenheim NPP and the French nuclear regulatory authority, will be reviewed at IAEA headquarters. The final report will be submitted to the Government of France within three months. The IAEA conducts approximately six OSART follow-up missions each year and this was the 102nd follow-up mission conducted to date. (IAEA)

  9. Technological progress, safety, and the guardian role of inspection

    Energy Technology Data Exchange (ETDEWEB)

    Critchley, O H

    1981-08-01

    Technological innovation is accompanied by unforeseen human consequences as well as benefits, and progress has produced a public awareness of the potential for hazards that has led to efficient safety-inspection procedures. Because no safety procedure is foolproof, the public learns to tolerate certain levels of risk from technology if it concludes that the benefits are worthwhile. The perception of values often transcends simple cost/benefit analysis. Safety technology and regulation developed during the past 50 years has benefited from earlier disastrous accidents enough to give the nuclear power industry an unprecedented safety record. Efforts to understand and anticipate human error have refined the role of inspection without achieving absolute reliability. Well-directed inspections that accept human fallibility will achieve more than design and organizational improvements. 42 references. (DCK)

  10. Safety program considerations for space nuclear reactor systems

    International Nuclear Information System (INIS)

    Cropp, L.O.

    1984-08-01

    This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given

  11. Annual technical progress report: reactor safety, Government fiscal year 1978

    International Nuclear Information System (INIS)

    1978-01-01

    Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis

  12. Fusion Safety Program annual report, fiscal year 1994

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1995-03-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities

  13. USNRC HTGR safety research program overview

    International Nuclear Information System (INIS)

    Foulds, R.B.

    1982-01-01

    An overview is given of current activities and planned research efforts of the US Nuclear Regulatory Commission (NRC) HTGR Safety Program. On-going research at Brookhaven National Laboratory, Oak Ridge National Laboratory, Los Alamos National Laboratory, and Pacific Northwest Laboratory are outlined. Tables include: HTGR Safety Issues, Program Tasks, HTGR Computer Code Library, and Milestones for Long Range Research Plan

  14. Space Nuclear Safety Program. Progress report, November 1983

    International Nuclear Information System (INIS)

    Bronisz, S.E.

    1984-06-01

    This technical monthly report covers studies related to the use of 238 PuO 2 in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Topics discussed include: safety-verification impact tests; explosion test; fragment test; leaking fueled clads; effects of fresh water and seawater or PuO 2 pellets; and impact tests of 5 watt radioisotope thermoelectric generator

  15. ATLAS program for advanced thermal-hydraulic safety research

    International Nuclear Information System (INIS)

    Song, Chul-Hwa; Choi, Ki-Yong; Kang, Kyoung-Ho

    2015-01-01

    Highlights: • Major achievements of the ATLAS program are highlighted in conjunction with both developing advanced light water reactor technologies and enhancing the nuclear safety. • The ATLAS data was shown to be useful for the development and licensing of new reactors and safety analysis codes, and also for nuclear safety enhancement through domestic and international cooperative programs. • A future plan for the ATLAS testing is introduced, covering recently emerging safety issues and some generic thermal-hydraulic concerns. - Abstract: This paper highlights the major achievements of the ATLAS program, which is an integral effect test program for both developing advanced light water reactor technologies and contributing to enhancing nuclear safety. The ATLAS program is closely related with the development of the APR1400 and APR"+ reactors, and the SPACE code, which is a best-estimate system-scale code for a safety analysis of nuclear reactors. The multiple roles of ATLAS testing are emphasized in very close conjunction with the development, licensing, and commercial deployment of these reactors and their safety analysis codes. The role of ATLAS for nuclear safety enhancement is also introduced by taking some examples of its contributions to voluntarily lead to multi-body cooperative programs such as domestic and international standard problems. Finally, a future plan for the utilization of ATLAS testing is introduced, which aims at tackling recently emerging safety issues such as a prolonged station blackout accident and medium-size break LOCA, and some generic thermal-hydraulic concerns as to how to figure out multi-dimensional phenomena and the scaling issue.

  16. Implementation of radiation safety program in a medical institution

    International Nuclear Information System (INIS)

    Palanca, Elena D.

    1999-01-01

    A medical institution that utilizes radiation for the diagnosis and treatment of diseases of malignancies develops and implements a radiation safety program to keep occupational exposures of radiation workers and exposures of non-radiation workers and the public to the achievable and a more achievable minimum, to optimize the use of radiation, and to prevent misadministration. The hospital radiation safety program is established by a core medical radiation committee composed of trained radiation safety officers and head of authorized users of radioactive materials and radiation machines from the different departments. The radiation safety program sets up procedural guidelines of the safe use of radioactive material and of radiation equipment. It offers regular training to radiation workers and radiation safety awareness courses to hospital staff. The program has a comprehensive radiation safety information system or radsis that circularizes the radiation safety program in the hospital. The radsis keeps the drafted and updated records of safety guides and policies, radioactive material and equipment inventory, personnel dosimetry reports, administrative, regulatory and licensing activity document, laboratory procedures, emergency procedures, quality assurance and quality control program process, physics and dosimetry procedures and reports, personnel and hospital staff training program. The medical radiation protection committee is tasked to oversee the actual implementation of the radiation safety guidelines in the different radiation facilities in the hospital, to review personnel exposures, incident reports and ALARA actions, operating procedures, facility inspections and audit reports, to evaluate the existing radiation safety procedures, to make necessary changes to these procedures, and make modifications of course content of the training program. The effective implementation of the radiation safety program provides increased confidence that the physician and

  17. The radiation safety self-assessment program of Ontario Hydro

    International Nuclear Information System (INIS)

    Armitage, G.; Chase, W.J.

    1987-01-01

    Ontario Hydro has developed a self-assessment program to ensure that high quality in its radiation safety program is maintained. The self-assessment program has three major components: routine ongoing assessment, accident/incident investigation, and detailed assessments of particular radiation safety subsystems or of the total radiation safety program. The operation of each of these components is described

  18. Reactor safety research programs. Quarterly progress report, October 1--December 31, 1977

    International Nuclear Information System (INIS)

    Romano, A.J.

    1978-01-01

    HTGR safety evaluation included studies on fission product release; materials, chemistry, and instrumentation; structural evaluation; and analytical safety evaluation. LMFBR safety evaluation included studies on accident sequences, technical coordination of structural integrity, and SSC code development and validation. LWR safety studies included thermal/hydraulic accident analysis, THOR code development, and stress corrosion cracking of PWR steam generator tubing

  19. Nuclear safety training program (NSTP) for dismantling

    International Nuclear Information System (INIS)

    Cretskens, Pieter; Lenie, Koen; Mulier, Guido

    2014-01-01

    European Control Services (GDF Suez) has developed and is still developing specific training programs for the dismantling and decontamination of nuclear installations. The main topic in these programs is nuclear safety culture. We therefore do not focus on technical training but on developing the right human behavior to work in a 'safety culture' environment. The vision and techniques behind these programs have already been tested in different environments: for example the dismantling of the BN MOX Plant in Dessel (Belgium), Nuclear Safety Culture Training for Electrabel NPP Doel..., but also in the non-nuclear industry. The expertise to do so was found in combining the know-how of the Training and the Nuclear Department of ECS. In training, ECS is one of the main providers of education in risky tasks, like elevation and manipulation of charges, working in confined spaces... but it does also develop training on demand to improve safety in a certain topic. Radiation Protection is the core business in the Nuclear Department with a presence on most of the nuclear sites in Belgium. Combining these two domains in a nuclear safety training program, NSTP, is an important stage in a dismantling project due to specific contamination, technical and other risks. It increases the level of safety and leads to a harmonization of different working cultures. The modular training program makes it possible to evaluate constantly as well as in group or individually. (authors)

  20. The 1988 progress report of the Nuclear Safety and Protection Institut

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The 1988 progress report of the Nuclear Safety and Protection Institut (CEA, France). The Institute's fields of action involve: The activities and technical safety of the nuclear power plants, the environmental and human radiation protection which includes technical, health and medical aspects, the nuclear materials compatibility and control and the accident intervention actions. The 1988 Institute activities are characterized by the continuity of the previous technical safety directives, by the improvement of the nuclear risk communication and of the international cooperation [fr

  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. Gas-cooled fast reactor safety - and overview and status of the U.S. program

    International Nuclear Information System (INIS)

    Torri, A.; Buttemer, D.R.

    1981-01-01

    In the revised GCFR Safety Program Plan a quantitative risk limit line has been adopted to establish requirements for the safety related functions and systems. The risk limit line is derived from an interpretation of NRC established licensing requirements, including those for LMFBR's. Multiple barriers to the progression of accident sequences are defined in the form of six Lines of Protection (LOPs). LOPs-1 to 3 are dedicated to accident prevention and represent the normal operating systems, the dedicated safety systems and the inherent design features, respectively. LOPs-4 to 6 are dedicated to the mitigation of core melt accident consequences and include in-vessel accident containment, secondary containment integrity and radiological attenuation, respectively. Cumulative frequency limits and consequence limits are established for each LOP. Design features associated with each LOP are described and the results of supporting safety analyses are summarized. (author)

  3. Canadian hydrogen safety program

    International Nuclear Information System (INIS)

    MacIntyre, I.; Tchouvelev, A.V.; Hay, D.R.; Wong, J.; Grant, J.; Benard, P.

    2007-01-01

    The Canadian hydrogen safety program (CHSP) is a project initiative of the Codes and Standards Working Group of the Canadian transportation fuel cell alliance (CTFCA) that represents industry, academia, government, and regulators. The Program rationale, structure and contents contribute to acceptance of the products, services and systems of the Canadian Hydrogen Industry into the Canadian hydrogen stakeholder community. It facilitates trade through fair insurance policies and rates, effective and efficient regulatory approval procedures and accommodation of the interests of the general public. The Program integrates a consistent quantitative risk assessment methodology with experimental (destructive and non-destructive) failure rates and consequence-of-release data for key hydrogen components and systems into risk assessment of commercial application scenarios. Its current and past six projects include Intelligent Virtual Hydrogen Filling Station (IVHFS), Hydrogen clearance distances, comparative quantitative risk comparison of hydrogen and compressed natural gas (CNG) refuelling options; computational fluid dynamics (CFD) modeling validation, calibration and enhancement; enhancement of frequency and probability analysis, and Consequence analysis of key component failures of hydrogen systems; and fuel cell oxidant outlet hydrogen sensor project. The Program projects are tightly linked with the content of the International Energy Agency (IEA) Task 19 Hydrogen Safety. (author)

  4. Ranking EU progress on road safety : 11th road safety Performance Index (PIN) report.

    NARCIS (Netherlands)

    Adminaite, D. Jost, G. Stipdonk, H. & Ward, H.

    2017-01-01

    In 2010, the European Union renewed its commitment to improve road safety by setting a target of reducing road deaths by 50% by 2020, compared to 2010 levels. This target followed an earlier target set in 2001 to halve road deaths by 2010. Since 2014, progress has virtually ground to a halt. 2016

  5. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    International Nuclear Information System (INIS)

    1987-05-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions

  6. Occupational Safety and Health Programs in Career Education.

    Science.gov (United States)

    DiCarlo, Robert D.; And Others

    This resource guide was developed in response to the Occupational Safety and Health Act of 1970 and is intended to assist teachers in implementing courses in occupational safety and health as part of a career education program. The material is a synthesis of films, programed instruction, slides and narration, case studies, safety pamphlets,…

  7. Sandia Laboratories environment and safety programs

    International Nuclear Information System (INIS)

    Zak, B.D.; McGrath, P.E.; Trauth, C.A. Jr.

    1975-01-01

    Sandia, one of ERDA's largest laboratories, is primarily known for its extensive work in the nuclear weapons field. In recent years, however, Sandia's role has expanded to embrace sizeable programs in the energy, resource recovery, and the environment and safety fields. In this latter area, Sandia has programs which address nuclear, fossil fuel, and general environment and safety issues. Here we survey ongoing activities and describe in more detail aa few projects of particular interest. These range from a study of the impact of sealed disposal of radioactive wastes, through reactor safety and fossil fuel plume chemistry, to investigations of the composition and dynamics of the stratosphere

  8. OSHA Training Programs. Module SH-48. Safety and Health.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This student module on OSHA (Occupational Safety and Health Act) training programs is one of 50 modules concerned with job safety and health. This module provides a list of OSHA training requirements and describes OSHA training programs and other safety organizations' programs. Following the introduction, 11 objectives (each keyed to a page in the…

  9. Fusion safety program annual report fiscal year 1997

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2)

  10. Fusion safety program annual report fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C. [and others

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2).

  11. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology

    International Nuclear Information System (INIS)

    1991-12-01

    Each progress report presents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progreess in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communitites) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./HP) [de

  12. Fusion Safety Program Annual Report, Fiscal Year 1996

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1996-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1996. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. The objective is to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, chemical reactions and activation product release, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Work done for ITER this year has focused on developing the needed information for the Non- Site- Specific Safety Report (NSSR-1). A final area of activity described is development of the new DOE Technical Standards for Safety of Magnetic Fusion Facilities

  13. 78 FR 43091 - Technical Operations Safety Action Program (T-SAP) and Air Traffic Safety Action Program (ATSAP)

    Science.gov (United States)

    2013-07-19

    ... Administration 14 CFR Part 193 [Docket No.: FAA-2013-0375] Technical Operations Safety Action Program (T-SAP) and... Disclosure. SUMMARY: The FAA is proposing that safety information provided to it under the T-SAP, established... to the FAA under the T-SAP and ATSAP, so the FAA can learn about and address aviation safety hazards...

  14. 75 FR 15484 - Railroad Safety Technology Program Grant Program

    Science.gov (United States)

    2010-03-29

    ... governments for projects that have a public benefit of improved railroad safety and efficiency. The program... State and local governments for projects * * * that have a public benefit of improved safety and network... minimum 20 percent grantee cost share (cash or in-kind) match requirement. DATES: FRA will begin accepting...

  15. Waste resources utilization program. Progress report, period ending 30 June 1975

    International Nuclear Information System (INIS)

    1975-08-01

    Initial progress on the Waste Resources Utilization Program, a joint effort sponsored by ERDA and EPA under the terms of Interagency Agreement E(29-2)-3536/EPA-IAG-D5-0675 is reported. This program has as its objective the use of 134 Cs/ 137 Cs (a potential nuclear reactor ''waste resource'') as a gamma radiation source, coupled with modest heating, to treat sewage sludge (another ''waste resource'') to rid it of pathogenic organisms so that it may be safely used as a fertilizer or a feed supplement for ruminant animals. The potential exists for using at least 50 percent of the by-product cesium from future reactor fuel-rod reprocessing in this one application alone. Activities dealing with research on many aspects of the problem such as pathogen reduction, physical and chemical effects, cost benefit analysis, safety and security, and systems engineering are reported. (U.S.)

  16. Research program on regulatory safety research

    International Nuclear Information System (INIS)

    Mailaender, R.

    2010-02-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning regulatory nuclear safety research, as co-ordinated by the Swiss Nuclear Safety Inspectorate ENSI. Work carried out in various areas is reviewed, including that done on reactor safety, radiation protection and waste disposal as well as human aspects, organisation and safety culture. Work done concerning materials, pressure vessel integrity, transient analysis, the analysis of serious accidents in light-water reactors, fuel and material behaviour, melt cooling and concrete interaction is presented. OECD data bank topics are discussed. Transport and waste disposal research at the Mont Terri rock laboratory is looked at. Requirements placed on the personnel employed in nuclear power stations are examined and national and international co-operation is reviewed

  17. High-heat tank safety issue resolution program plan

    International Nuclear Information System (INIS)

    Wang, O.S.

    1993-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank (SST) 241-C-106. This program plan also outlines the logic for selecting approaches and tasks to mitigate and resolve the high-heat safety issue. The identified safety issue for high-heat tank 241-C-106 involves the potential release of nuclear waste to the environment as the result of heat-induced structural damage to the tank's concrete, if forced cooling is interrupted for extended periods. Currently, forced ventilation with added water to promote thermal conductivity and evaporation cooling is used to cool the waste. At this time, the only viable solution identified to resolve this safety issue is the removal of heat generating waste in the tank. This solution is being aggressively pursued as the permanent solution to this safety issue and also to support the present waste retrieval plan. Tank 241-C-106 has been selected as the first SST for retrieval. The program plan has three parts. The first part establishes program objectives and defines safety issues, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. Selected tasks and best-estimate schedules are also summarized in the program plan

  18. Status and progress of the RERTR program in the year 2002

    International Nuclear Information System (INIS)

    Travelli, Armando

    2002-01-01

    conversion of all HEU research reactors supplied by the United States and Russia during the next ten years, with high priority given to reactors in the United States and Russia. This effort will address, in addition to the fuel development and qualification, the analyses and performance/economic/safety evaluations needed to implement the conversions. In combination with this over-arching goal, the RERTR program plans to achieve at the earliest possible date two other major goals: 1) Qualification of LEU U-Mo dispersion fuels with uranium densities of 6 g/cm 3 and 7 g/cm 3 , so that reactors currently using or planning to use LEU silicide fuel can then rely on a fuel that is acceptable to COGEMA for reprocessing; and 2) Elimination of all obstacles to the utilization of LEU in targets for isotope production, so that this important function can be performed without the need for weapons-grade materials. To better concentrate on these primary goals, and in consideration of the excellent progress made by the French fuel development program, the RERTR program has decided to forgo parallel qualification of LEU U-Mo dispersion fuel with uranium density of 8-9 g/cm 3 . Only a concerted effort from all of us, working together as we have for many years, will ensure that these goals can be achieved. We intend to promote the efficiency and safety of research reactors while, at the same time, eliminating the traffic in weapons-grade uranium and, with it, the possibility that some of this material might fall in the wrong hands. In today's environment, few causes can be more deserving of our joint efforts. (author)

  19. Human genome program report. Part 1, overview and progress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    This report contains Part 1 of a two-part report to reflect research and progress in the U.S. Department of Energy Human Genome Program from 1994 through 1996, with specified updates made just before publication. Part 1 consists of the program overview and report on progress.

  20. IRSN research programs concerning reactor safety

    International Nuclear Information System (INIS)

    Bardelay, J.

    2005-01-01

    This paper is made up of 3 parts. The first part briefly presents the missions of IRSN (French research institute on nuclear safety), the second part reviews the research works currently led by IRSN in the following fields : -) the assessment of safety computer codes, -) thermohydraulics, -) reactor ageing, -) reactivity accidents, -) loss of coolant, -) reactor pool dewatering, -) core meltdown, -) vapor explosion, and -) fission product release. In the third part, IRSN is shown to give a major importance to experimental programs led on research or test reactors for collecting valid data because of the complexity of the physical processes that are involved. IRSN plans to develop a research program concerning the safety of high or very high temperature reactors. (A.C.)

  1. A Computer Program for Assessing Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of)

    2014-10-15

    Through several accidents of NPP including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, a lack of safety culture was pointed out as one of the root cause of these accidents. Due to its latent influences on safety performance, safety culture has become an important issue in safety researches. Most of the researches describe how to evaluate the state of the safety culture of the organization. However, they did not include a possibility that the accident occurs due to the lack of safety culture. Because of that, a methodology for evaluating the impact of the safety culture on NPP's safety is required. In this study, the methodology for assessing safety culture impact is suggested and a computer program is developed for its application. SCII model which is the new methodology for assessing safety culture impact quantitatively by using PSA model. The computer program is developed for its application. This program visualizes the SCIs and the SCIIs. It might contribute to comparing the level of the safety culture among NPPs as well as improving the management safety of NPP.

  2. Nuclear criticality safety program at the Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

    1994-01-01

    The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

  3. Recent progress in safety-related applications of reactor noise analysis

    International Nuclear Information System (INIS)

    Hirota, Jitsuya; Shinohara, Yoshikuni; Saito, Keiichi

    1982-01-01

    Recent progress in safety-related applications of reactor noise analysis is reviewed, mainly referring to various papers presented at the Third Specialists' Meeting on Reactor Noise (SMORN-III) held in Tokyo in 1981. Advances in application of autoregressive model, coherence analysis and pattern recognition technique are significant since SMORN-II in 1977. Development of reactor diagnosis systems based on noise analysis is in progress. Practical experiences in the safety-related applications to power plants are being accumulated. Advances in quantitative monitoring of vibration of internal structures in PWR and diagnosis of core stability and control system characteristics in BWR are notable. Acoustic methods are also improved to detect sodium boiling in LMFBR. The Reactor Noise Analysis Benchmark Test performed by Japan in connection with SMORN-III is successful so that it is possible to proceed to the second stage of the benchmark test. (author)

  4. Space nuclear safety program: Progress report, April-June 1987

    Energy Technology Data Exchange (ETDEWEB)

    George, T.G. (comp.)

    1988-07-01

    This quarterly report describes studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems, carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed are ongoing; the results and conclusions described may change as the work progresses.

  5. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

  6. Research notes : are safety corridors really safe? Evaluation of the corridor safety improvement program.

    Science.gov (United States)

    1998-08-26

    High accident frequencies on Oregons highway corridors are of concern to the Oregon Department of Transportation (ODOT). : ODOT adopted the Corridor Safety Improvement Program as part of an overall program of safety improvements using federal and ...

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

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1979-09-01

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

  8. Management of a comprehensive radiation safety program in a major American University and affiliated academic medical center

    International Nuclear Information System (INIS)

    Yoshizumi, T.T.; Reiman, R.E.; Vylet, V.; Clapp, J.R.; Thomann, W.R.; Lyles, K.W.

    2000-01-01

    Duke University, which operates under eight radiation licenses issued by the State of North Carolina, consists of a leading medical center including extensive inpatient and outpatient facilities, a medical school, biomedical research labs, and an academic campus including two major accelerator facilities. The Nuclear Medicine and Radiation Oncology departments handle over 40,000 diagnostic and therapeutic procedures annually, including approximately 160 radioiodine therapeutic cases. In biomedical research labs, about 300 professors are authorized to use radioactive materials. Over 2,000 radiation workers are identified on campus. Over the past two years, we have transformed the existing radiation safety program into a more responsive and more accountable one. Simultaneously, the institutional 'culture' changed, and the Radiation Safety Division came to be viewed as a helpful ally by investigators. The purpose of this paper is to present our experiences that have made this transformation possible. Our initiatives included; (a) defining short-term and long-term goals; (b) establishing a definitive chain of authority; (c) obtaining an external review by a consultant Health Physicist; (d) improving existing radiation safety programs; (e) reorganizing the Radiation Safety Division, with creation of multidisciplinary professional staff positions; (f) implementing campus-wide radiation safety training, (g) increasing technician positions; (h) establishing monthly medical center radiation safety executive meeting. As a result progress made at the Divisional level includes; (a) culture change by recruiting professionals with academic credentials and recent college graduates; (b) implementing weekly staff meetings and monthly quality assurance meetings; (c) achieving academic prominence by publishing and presenting papers in national meetings; (d) senior staff achieving faculty appointments with academic departments; (e) senior staff participating in graduate student

  9. Division of Waste Management programs. Progress report, July-December 1978

    International Nuclear Information System (INIS)

    Lerch, R.E.; Allen, C.R.; Richardson, G.L.

    1979-07-01

    This is the eleventh progress report on Division of Waste Management programs. The report describes progress in the second half of 1978 on the following programs: intermediate-level waste solidification, chemical processing of combustible solid waste, and application of acid digestion to commercial wastes. The latter two programs were combined in October 1978 into a single program, acid digestion of combustible wastes

  10. AEC sets five year nuclear safety research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The research by the government for the establishment of means of judging the adequacy of safety measures incorporated in nuclear facilities, including setting safety standards and collecting documents of general criteria, and the research by the industry on safety measures and the promotion of safety-related technique are stated in the five year program for 1976-80 reported by subcommittees, Atomic Energy Commission (AEC). Four considerations on the research items incorporated in the program are 1) technical programs relating to the safety of nuclear facilities and the necessary criteria, 2) priority of the relevant items decided according to their impact on circumstances, urgency, the defence-indepth concept and so on, 3) consideration of all relevant data and documents collected, and research subjects necessary to quantify safety measurement, and 4) consideration of technological actualization, the capability of each research body, the budget and the time schedule. In addition, seven major themes decided on the basis of these points are 1) reactivity-initiated accident, 2) LOCA, 3) fuel behavior, 4) structural safety, 5) radioactive release, 6) statistical method of safety evaluation, and 7) seismic characteristics. The committee has deliberated the appropriate division of researches between the government and the industry. A set of tables showing the nuclear safety research plan for 1976-80 are attached. (Iwakiri, K.)

  11. Space Nuclear Safety Program: Progress report, January-March 1987

    Energy Technology Data Exchange (ETDEWEB)

    Lewin, R. (ed.); George, T.G. (comp.)

    1988-07-01

    This quarterly report describes studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems, which were carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed are ongoing; the results and conclusions described may change as the work progresses.

  12. Space nuclear safety program: Progress report, July--September 1987

    Energy Technology Data Exchange (ETDEWEB)

    George, T.G. (comp.)

    1989-02-01

    This quarterly report describes studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems, carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. The studies discussed are ongoing; the results and conclusions described may change as the work progresses. 20 figs., 4 tabs.

  13. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

  14. Directory of Academic Programs in Occupational Safety and Health.

    Science.gov (United States)

    Weis, William J., III; And Others

    This booklet describes academic program offerings in American colleges and universities in the area of occupational safety and health. Programs are divided into five major categories, corresponding to each of the core disciplines: (1) occupational safety and health/industrial hygiene, (2) occupational safety, (3) industrial hygiene, (4)…

  15. OPG waterways public safety program

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, T [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

    2009-07-01

    Ontario Power Generation (OPG) has 64 hydroelectric generating stations, 241 dams, and 109 dams in Ontario's registry with the International Commission on Large Dams (ICOLD). In 1986, it launched a formal dam safety program. This presentation addressed the importance of public safety around dams. The safety measures are timely because of increasing public interaction around dams; the public's unawareness of hazards; public interest in extreme sports; easier access by recreational vehicles; the perceived right of public to access sites; and the remote operation of hydroelectric stations. The presentation outlined the OPG managed system approach, with particular reference to governance; principles; standards and procedures; and aspects of implementation. Specific guidelines and governing documents for public safety around dams were identified, including guidelines for public safety of waterways; booms and buoys; audible warning devices and lights; public safety signage; fencing and barricades; and risk assessment for public safety around waterways. The presentation concluded with a discussion of audits and management reviews to determine if safety objectives and targets have been met. figs.

  16. General-purpose heat source project and space nuclear safety fuels program. Progress report, February 1980

    International Nuclear Information System (INIS)

    Maraman, W.J.

    1980-05-01

    This formal monthly report covers the studies related to the use of 238 PuO 2 in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are: General-Purpose Heat Source Development and Space Nuclear Safety and Fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work

  17. The RERTR [Reduced Enrichment Research and Test Reactor] program: A progress report

    International Nuclear Information System (INIS)

    Travelli, A.

    1986-11-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1985, the activities, results, and new developments which occurred in 1986 are reviewed. The second miniplate series, concentrating on U 3 Si 2 -Al and U 3 Si-Al fuels, was expanded and its irradiation continued. Postirradiation examinations of several of these miniplates and of six previously irradiated U 3 Si 2 -Al full-size elements were completed with excellent results. The whole-core ORR demonstration with U 3 Si 2 -Al fuel at 4.8 g U/cm 3 is well under way and due for completion before the end of 1987. DOE removed an important barrier to conversions by announcing that the new LEU fuels will be accepted for reprocessing. New DOE prices for enrichment and reprocessing services were calculated to have minimal effect on HEU reactors, and to reduce by about 8 to 10% the total fuel cycle costs of LEU reactors. New program activities include preliminary feasibility studies of LEU use in DOE reactors, evaluation of the feasibility to use LEU targets for the production of fission-product 99 Mo, and responsibility for coordinating safety evaluations related to LEU conversions of US university reactors, as required by NRC. Achievement of the final program goals is projected for 1990. This progress could not have been achieved without close international cooperation, whose continuation and intensification are essential to the achievement of the ultimate goals of the RERTR Program

  18. Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Labour. Period: 1 January - 30 June 2003

    International Nuclear Information System (INIS)

    2003-01-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers. (orig.) [de

  19. Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Labour. Period: 1 July - 31 December 2003

    International Nuclear Information System (INIS)

    2004-01-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers. (orig.) [de

  20. Fundamentals of a patient safety program

    International Nuclear Information System (INIS)

    Frush, Karen S.

    2008-01-01

    Thousands of people are injured or die from medical errors and adverse events each year, despite being cared for by hard-working, intelligent and well-intended health care professionals, working in the highly complex and high-risk environment of the American health care system. Patient safety leaders have described a need for health care organizations to make error prevention a major strategic objective while at the same time recognizing the importance of transforming the traditional health care culture. In response, comprehensive patient safety programs have been developed with the aim of reducing medical errors and adverse events and acting as a catalyst in the development of a culture of safety. Components of these programs are described, with an emphasis on strategies to improve pediatric patient safety. Physicians, as leaders of the health care team, have a unique opportunity to foster the culture and commitment required to address the underlying systems causes of medical error and harm. (orig.)

  1. Fusion Safety Program annual report, fiscal year 1992

    International Nuclear Information System (INIS)

    Holland, D.F.; Cadwallader, L.C.; Herring, J.S.; Longhurst, G.R.; McCarthy, K.A.; Merrill, B.J.; Piet, S.J.

    1993-01-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1992. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG ampersand G Idaho, Inc. is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations including the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory, the Massachusetts Institute of Technology, and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving beryllium, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment failure rate data base, and computer code development for reactor transients. Also included in the report is a summary of the safety and environmental studies performed by the INEL for the Tokamak Physics Experiments and the Tokamak Fusion Test Reactor, the safety analysis for the International Thermonuclear Experimental Reactor design, and the technical support for the ARIES commercial reactor design study

  2. Does a Rehabilitation Program of Aerobic and Progressive Resisted Exercises Influence HIV-Induced Distal Neuropathic Pain?

    Science.gov (United States)

    Maharaj, Sonill S; Yakasai, Abdulsalam M

    2018-05-01

    Distal symmetrical polyneuropathy is a common neurological sequela after HIV, which leads to neuropathic pain and functional limitations. Rehabilitation programs with exercises are used to augment pharmacological therapy to relieve pain but appropriate and effective exercises are unknown. This study explored the safety and effect of moderate-intensity aerobic exercises and progressive resisted exercises for HIV-induced distal symmetrical polyneuropathy neuropathic pain. A randomized pretest, posttest of 12 wks of aerobic exercise or progressive resisted exercise compared with a control. Outcome measures were assessed using the subjective periphery neuropathy, brief peripheral neuropathy screening, and numeric pain rating scale. Pain was assessed at baseline, 6 and 12 wks. Data between groups were compared using Kruskal-Wallis, Mann-Whitney U test, and within-groups Friedman and Wilcoxon signed rank tests. There were 136 participants (mean [SD] age = 36.79 [8.23] yrs) and the exercise groups completed the protocols without any adverse effects. Pain scores within and between aerobic exercise and progressive resisted exercise groups showed significant improvement (P 0.05). This study supports a rehabilitation program of moderate-intensity aerobic exercise and progressive resisted exercise being safe and effective for reducing neuropathic pain and is beneficial with analgesics for HIV-induced distal symmetrical polyneuropathy.

  3. 49 CFR 659.19 - System safety program plan: contents.

    Science.gov (United States)

    2010-10-01

    ... implementation of the system safety program. (j) A description of the process used by the rail transit agency to... the rail transit agency to manage safety issues. (d) The process used to control changes to the system... hazard management program. (n) A description of the process used for facilities and equipment safety...

  4. The U.S. RERTR program status and progress

    International Nuclear Information System (INIS)

    Travelli, A.

    1998-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program since its inception in 1978 is described. A brief summary of the results which the RERTR Program had achieved by the end of 1996 in collaboration with its many international partners is followed by a detailed review of the major events, findings, and activities of 1997. Significant progress has been made during the past year. In the area of U.S. acceptance of spent fuel from foreign research reactors, several shipments have taken place and additional are being planned. Intense fuel development activities are in progress, including procurement of equipment, screening of candidate materials, and production of microplates. Irradiation of the first series of microplates began in August 1997 in the Advanced Test Reactor, in Idaho. Progress has been made in the Russian RERTR program, which aims to develop and demonstrate within five years the technical means needed to convert Russian-supplied research reactors to LEU fuels. The study of an alternative LEU core for the FRM-II design has been extended to address, with favorable results, controversial performance issues which were raised at last year's meeting. Progress was also made on several aspects of producing molybdenum-99 from fission targets utilizing LEU instead of HEU. Various types of targets and processes are being pursued, with FDA approval of an LEU process projected to occur within two years. The feasibility of LEU Fuel conversion for three important DOE research reactors (BMRR, HFBR, and HFIR) has been evaluated by the RERTR program. In spite of the many momentous events which have occurred during the intervening years, and the excellent progress achieved, the most important challenges that the RERTR program faces today are not very different in type from those that were faced during the first RERTR meeting. Now, as then, the most important task is to develop new LEU fuels satisfying requirements which cannot be satisfied by any

  5. The U.S. RERTR Program. Status and progress

    International Nuclear Information System (INIS)

    Travelli, A.

    1997-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program since its inception in 1978 is described. A brief summary of the results which the RERTR Program had achieved by the end of 1996 in collaboration with its many international partners is followed by a detailed review of the major events, findings, and activities of 1997. Significant progress has been made during the past year. In the area of U.S. acceptance of spent fuel from foreign research reactors, several shipments have taken place and additional are being planned. Intense fuel development activities are in progress, including procurement of equipment, screening of candidate materials, and production of microplates. Irradiation of the first series of microplates began in August 1997 in the Advanced Test Reactor, in Idaho. Progress has been made in the Russian RERTR program, which aims to develop and demonstrate within five years the technical means needed to convert Russian-supplied research reactors to LEU fuels. The study of an alternative LEU core for the FRM-II design has been extended to address, with favorable results, controversial performance issues which were raised at last year's meeting. Progress was also made on several aspects of producing molybdenum-99 from fission targets utilizing LEU instead of HEU. Various types of targets and processes are being pursued, with FDA approval of an LEU process projected to occur within two years. The feasibility of LEU fuel conversion for three important DOE research reactors (BMRR, HFBR, and HFIR) has been evaluated by the RERTR program. In spite of the many momentous events which have occurred during the intervening years, and the excellent progress achieved, the most important challenges that the RERTR program faces today are not very different in type from those that were faced during the first RERTR meeting. Now, as then, the most important task is to develop new LEU fuels satisfying requirements which cannot be satisfied by any

  6. Experimental research progress on passive safety systems of Chinese advanced PWR

    International Nuclear Information System (INIS)

    Xiao Zejun; Zhuo Wenbin; Zheng Hua; Chen Bingde; Zong Guifang; Jia Dounan

    2003-01-01

    TMI and Chernobyl accidents, having pronounced impact on nuclear industries, triggered the governments as well as interested institutions to devote much attention to the safety of nuclear power plant and public's requirements on nuclear power plant safety were also going to be stricter and stricter. It is obvious that safety level of an ordinary light water reactor is no longer satisfactory to these requirements. Recently, the safety authorities have recommended the implementation of passive system to improve the safety of nuclear reactors. Passive safety system is one of the main differences between Chinese advanced PWR and other conventional PWR. The working principle of passive safety system is to utilize the gravity, natural convection (natural circulation) and stored energy to implement the system's safety function. Reactors with passive safety systems are not only safer, but also more economical. The passive safety system of Chinese advanced PWR is composed of three independent systems, i.e. passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system. This paper is a summary of experimental research progress on passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system

  7. Status and progress of the RERTR Program

    International Nuclear Information System (INIS)

    Travelli, A.

    1996-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1996 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1995 in collaboration with its many international partners

  8. Status and progress of the RERTR Program

    International Nuclear Information System (INIS)

    Travelli, A.

    1993-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1993 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1992 in collaboration with its many international partners

  9. India's power program and its concern over environmental safety

    International Nuclear Information System (INIS)

    Prasad, G.E.; Mittra, J.

    2001-01-01

    India's need of electrical power is enormous and per capita consumption of power is to be increased at least by ten times to reach the level of world average. Thermal Power generation faces two fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India's self reliant, three stage, 'closed-fuel-cycle' nuclear power program is promising better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating necessary safety features in the design, operational safety through structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from nuclear power program. Based on latest technology, as available in case of nuclear power option, it is quite possible to meet high energy requirement with least impact on the environment.. (authors)

  10. Progress of the RERTR program in 1989

    International Nuclear Information System (INIS)

    Travelli, A.

    1991-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1988, the major events, findings, and activities of 1989 are reviewed. (orig.)

  11. Japan's international cooperation programs on seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    Sanada, Akira

    1997-01-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  12. Safety Test Program Summary SNAP 19 Pioneer Heat Source Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1971-07-01

    Sixteen heat source assemblies have been tested in support of the SNAP 19 Pioneer Safety Test Program. Seven were subjected to simulated reentry heating in various plasma arc facilities followed by impact on earth or granite. Six assemblies were tested under abort accident conditions of overpressure, shrapnel impact, and solid and liquid propellant fires. Three capsules were hot impacted under Transit capsule impact conditions to verify comparability of test results between the two similar capsule designs, thus utilizing both Pioneer and Transit Safety Test results to support the Safety Analysis Report for Pioneer. The tests have shown the fuel is contained under all nominal accident environments with the exception of minor capsule cracks under severe impact and solid fire environments. No catastrophic capsule failures occurred in this test which would release large quantities of fuel. In no test was fuel visible to the eye following impact or fire. Breached capsules were defined as those which exhibit thoria contamination on its surface following a test, or one which exhibited visible cracks in the post test metallographic analyses.

  13. Waste Tank Organic Safety Project organic concentration mechanisms task. FY 1994 progress report

    International Nuclear Information System (INIS)

    Gerber, M.A.

    1994-09-01

    The Pacific Northwest Laboratory (PNL), Waste Tank Organic Safety Project is conducting research to support Westinghouse Hanford Company's (WHC) Waste Tank Safety Program, sponsored by the U.S. Department of Energy's Tank Farm Project Office. The goal of PNL's program is to provide a scientific basis for analyzing organics in Hanford's underground storage tanks (USTs) and for determining whether they are at concentrations that pose a potentially unsafe condition. Part of this research is directed toward determining what organic concentrations are safe by conducting research on organic aging mechanisms and waste energetics to assess the conditions necessary to produce an uncontrolled energy release in tanks due to reactions between the organics and the nitrate and nitrate salts in the tank wastes. The objective of the Organic Concentration Mechanisms Task is to assess the degree of localized enrichment of organics to be expected in the USTs due to concentration mechanisms. This report describes the progress of research conducted in FY 1994 on two concentration mechanisms of interest to the tank safety project: (1) permeation of a separate organic liquid phase into the interstitial spaces of the tank solids during the draining of free liquid from the tanks; and (2) concentration of organics on the surfaces of the solids due to adsorption. Three experiments were conducted to investigate permeation of air and solvent into a sludge simulant that is representative of single-shell tank sludge. The permeation behavior of air and solvent into the sludge simulant can be explained by the properties of the fluid pairs (air/supernate and solvent supernate) and the sludge. One important fluid property is the interfacial tension between the supernate and either the solvent or air. In general, the greater the interfacial tension between two fluids, the more difficult it will be for the air or solvent to displace the supernate during dewatering of the sludge

  14. The NASA Aviation Safety Program: Overview

    Science.gov (United States)

    Shin, Jaiwon

    2000-01-01

    In 1997, the United States set a national goal to reduce the fatal accident rate for aviation by 80% within ten years based on the recommendations by the Presidential Commission on Aviation Safety and Security. Achieving this goal will require the combined efforts of government, industry, and academia in the areas of technology research and development, implementation, and operations. To respond to the national goal, the National Aeronautics and Space Administration (NASA) has developed a program that will focus resources over a five year period on performing research and developing technologies that will enable improvements in many areas of aviation safety. The NASA Aviation Safety Program (AvSP) is organized into six research areas: Aviation System Modeling and Monitoring, System Wide Accident Prevention, Single Aircraft Accident Prevention, Weather Accident Prevention, Accident Mitigation, and Synthetic Vision. Specific project areas include Turbulence Detection and Mitigation, Aviation Weather Information, Weather Information Communications, Propulsion Systems Health Management, Control Upset Management, Human Error Modeling, Maintenance Human Factors, Fire Prevention, and Synthetic Vision Systems for Commercial, Business, and General Aviation aircraft. Research will be performed at all four NASA aeronautics centers and will be closely coordinated with Federal Aviation Administration (FAA) and other government agencies, industry, academia, as well as the aviation user community. This paper provides an overview of the NASA Aviation Safety Program goals, structure, and integration with the rest of the aviation community.

  15. 2010 Annual Progress Report: DOE Hydrogen Program

    Energy Technology Data Exchange (ETDEWEB)

    2011-02-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  16. German Light-Water-Reactor Safety-Research Program

    International Nuclear Information System (INIS)

    Seipel, H.G.; Lummerzheim, D.; Rittig, D.

    1977-01-01

    The Light-Water-Reactor Safety-Research Program, which is part of the energy program of the Federal Republic of Germany, is presented in this article. The program, for which the Federal Minister of Research and Technology of the Federal Republic of Germany is responsible, is subdivided into the following four main problem areas, which in turn are subdivided into projects: (1) improvement of the operational safety and reliability of systems and components (projects: quality assurance, component safety); (2) analysis of the consequences of accidents (projects: emergency core cooling, containment, external impacts, pressure-vessel failure, core meltdown); (3) analysis of radiation exposure during operation, accident, and decommissioning (project: fission-product transport and radiation exposure); and (4) analysis of the risk created by the operation of nuclear power plants (project: risk and reliability). Various problems, which are included in the above-mentioned projects, are concurrently studied within the Heiss-Dampf Reaktor experiments

  17. 76 FR 74723 - New Car Assessment Program (NCAP); Safety Labeling

    Science.gov (United States)

    2011-12-01

    ... [Docket No. NHTSA 2010-0025] RIN 2127-AK51 New Car Assessment Program (NCAP); Safety Labeling AGENCY... NHTSA's regulation on vehicle labeling of safety rating information to reflect the enhanced NCAP ratings... Traffic Safety Administration under the enhanced NCAP testing and rating program. * * * * * (e) * * * (4...

  18. The Progressive Insurance Automotive X PRIZE Education Program

    Energy Technology Data Exchange (ETDEWEB)

    Robyn Ready

    2011-12-31

    The Progressive Insurance Automotive X PRIZE Education Program conducted education and outreach activities and used the competition's technical goals and vehicle demonstrations as a means of attracting students and the public to learn more about advanced vehicle technologies, energy efficiency, climate change, alternative fuels, and the science and math behind efficient vehicle development. The Progressive Insurance Automotive X PRIZE Education Program comprised three integrated components that were designed to educate the general public and create a multi-tiered initiative to engage students and showcase the 21st century skills students will need to compete in our global economy: teamwork, creativity, strong literacy, math and science skills, and innovative thinking. The elements included an Online Experience, a National Student Contest, and in person education events and activites. The project leveraged online connections, strategic partnerships, in-classroom, and beyond-the-classroom initiatives, as well as mainstream media. This education program supported by the U.S. Department of Energy (DOE) also funded the specification of vehicle telemetry and the full development and operation of an interactive online experience that allowed internet users to follow the Progressive Insurance Automotive X PRIZE vehicles as they performed in real-time during the Progressive Insurance Automotive X PRIZE competition events.

  19. Nordic Nuclear Safety Research. Presentation of the 1994 - 1997 program

    International Nuclear Information System (INIS)

    Bennerstedt, Torkel

    1998-01-01

    NKS (Nordic Nuclear Safety Research) has just concluded its fifth 4-year program (1994 - 1997). The following nine projects were performed: Strategy for reactor safety: Studies of preparatory work to minimize the risk of accidents; Prevention of severe reactor accidents: studies of recriticality, core melt progression and support systems to minimize releases; Safe disposal of radioactive waste: Waste characterization, Performance analyses and environmental impact statements for repositories; Marine radioecology: Improved assessment methods for effects of releases of radionuclides; Long ecological half-lives in semi-natural systems: Models for transfer of cesium from nature to man; Preparedness strategies and procedures: Mobile measurements, quality assurance and interventions; Emergency preparedness drills and exercises; Preplanning of early cleanup: Check-list for planners and decision makers for various environments and fallout situations; Overriding information issues: Risk communication, real-time exchange of information after an accident. Together with additional financial support from a number of ministries and companies in the nuclear power field, the total NKS budget for the period 1994 - 1997 was some USD 5 million, evenly distributed over the years. To this should be added contributions in kind by participating organizations, worth at least another USD 10 million, without which this program would not have been possible. The nine projects and some practical results (rather than scientific detail) are outlined in this paper. (EG)

  20. Progress report: nuclear safety and radiation protection in 2006

    International Nuclear Information System (INIS)

    2007-01-01

    For the French Nuclear Safety Authority (Asn), the year 2006 was marked by two important nuclear laws being passed, one of which brought about a major change in its status. The year was a relatively satisfactory one with regard to nuclear safety, although the picture was more contrasted concerning radiation protection: in this area, more particularly in the medical field, the overall impression of good progress is offset by the declaration of a number of radiotherapy accidents. Given the benefits expected from radiotherapy treatment by the patient suffering from cancer, the conditions in which this activity is carried out are a subject of major concern for Asn, in the light of the serious risks linked to patient over-exposure. ( some important points as follows: the law on transparency and security in the nuclear field, the law on sustainable management of radioactive materials and waste, Asn: an independent administrative authority, EPR reactor project safety, I.R.R.S.: an international audit of Asn in 2006, harmonization of nuclear safety, cancer radiotherapy, improved information of the public after the T.S.N. law, taking account of organisational and human factors). (N.C.)

  1. Safety guidance and inspection program for particle accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Do Whey [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Lee, Hee Seock; Yeo, In Whan [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)] (and others)

    2001-03-15

    The inspection program and the safety guidance were developed to enhance the radiation protection for the use of particle accelerators. First the classification of particle accelerators was conducted to develop the safety inspection protocol efficiently. The status of particle accelerators which were operated at the inside and outside of the country, and their safety programs were surveyed. The characteristics of radiation production was researched for each type of particle accelerators. Two research teams were launched for industrial and research accelerators and for medical accelerators, respectively. In each stages of a design, a fabrication, an installation, a commissioning, and normal operation of accelerators, those safety inspection protocols were developed. Because all protocols resulted from employing safety experts, doing the questionnaire, and direct facility surveys, it can be applicable to present safety problem directly. The detail improvement concepts were proposed to revise the domestic safety rule. This results might also be useful as a practical guidance for the radiation safety officer of an accelerator facility, and as the detail standard for the governmental inspection authorities.

  2. India's power programs and its concern over environmental safety

    International Nuclear Information System (INIS)

    Prasad, G.E.; Mittra, J.; Sarma, M.S.R.

    2000-01-01

    India's need for electrical power is enormous and per capita consumption of power is to be increased at least by 10 times to reach the level of the world average. Thermal power generation faces two-fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India 's self reliant, . three stage, 'closed-fuel-cycle' nuclear power program is promising a better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, the Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating' necessary safety features in the design, operational safety through a structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from the nuclear power program. Based on the latest technology, as available in case of the nuclear power option, it is quite possible to meet high energy requirements with least impact on the environment. (authors)

  3. DOE program for transportation R and D: a progress report

    International Nuclear Information System (INIS)

    Sisler, J.A.

    1978-01-01

    The Transportation Branch of the Division of Environmental Control Technology (ECT), US Department of Energy (DOE), is managing a research and development program oriented toward the environmental and safety aspects of the transportation of energy materials. This program was started under the US Energy Research and Development Administration (ERDA), and in October 1977 became one of the programs of the newly formed DOE. The objectives of the current R and D program include: (1) development of data and methodology for environment and safety (E and S) assessments including development of transportation environmental data, severe accident analysis and risk assessment; (2) confirmatory full-scale testing of package and vehicular systems to improve scale modeling and analytical techniques for transport system safety assessment; (3) development of an improved capability for assessing the dynamic performance of nuclear packaging under severe accident conditions; (4) evaluation and verification of existing transportation standards to assure adequate environmental controls; and (5) development of the needed information system tools such as films, booklets, and exhibits to permit the public and other interested parties to have access to the results of the R and D program. This paper summarizes the history of this program, describes the accomplishments, includes references to published reports, and discusses the current status of the environmental and safety R and D program as related to transportation of energy material. Comments are also included regarding the future direction of the program

  4. EPRI program in water reactor safety

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Gelhaus, F.; Gopalakrishnan, A.

    1975-01-01

    The basis for EPRI's water reactor safety program is twofold. First is compilation and development of fundamental background data necessary for quantified light-water reactor (LWR) safety assurance appraisals. Second is development of realistic and experimentally bench-marked analytical procedures. The results are expected either to confirm the safety margins in current operating parameters, and to identify overly conservative controls, or, in some cases, to provide a basis for improvements to further minimize uncertainties in expected performance. Achievement of these objectives requires the synthesis of related current and projected experimental-analytical projects toward establishment of an experimentally-based analysis for the assurance of safety for LWRs

  5. Safety in the Chemical Laboratory: Safety in the Chemistry Laboratories: A Specific Program.

    Science.gov (United States)

    Corkern, Walter H.; Munchausen, Linda L.

    1983-01-01

    Describes a safety program adopted by Southeastern Louisiana University. Students are given detailed instructions on laboratory safety during the first laboratory period and a test which must be completely correct before they are allowed to return to the laboratory. Test questions, list of safety rules, and a laboratory accident report form are…

  6. Progress report concerning safety research for nuclear reactor facilities

    International Nuclear Information System (INIS)

    1978-01-01

    Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

  7. HTGR safety research program

    International Nuclear Information System (INIS)

    Barsell, A.W.; Olsen, B.E.; Silady, F.A.

    1981-01-01

    An HTGR safety research program is being performed supporting and guided in priorities by the AIPA Probabilistic Risk Study. Analytical and experimental studies have been conducted in four general areas where modeling or data assumptions contribute to large uncertainties in the consequence assessments and thus, in the risk assessment for key core heat-up accident scenarios. Experimental data have been obtained on time-dependent release of fission products from the fuel particles, and plateout characteristics of condensible fission products in the primary circuit. Potential failure modes of primarily top head PCRV components as well as concrete degradation processes have been analyzed using a series of newly developed models and interlinked computer programs. Containment phenomena, including fission product deposition and potential flammability of liberated combustible gases have been studied analytically. Lastly, the behaviour of boron control material in the core and reactor subcriticality during core heatup have been examined analytically. Research in these areas has formed the basis for consequence updates in GA-A15000. Systematic derivation of future safety research priorities is also discussed. (author)

  8. Analysis of School Food Safety Programs Based on HACCP Principles

    Science.gov (United States)

    Roberts, Kevin R.; Sauer, Kevin; Sneed, Jeannie; Kwon, Junehee; Olds, David; Cole, Kerri; Shanklin, Carol

    2014-01-01

    Purpose/Objectives: The purpose of this study was to determine how school districts have implemented food safety programs based on HACCP principles. Specific objectives included: (1) Evaluate how schools are implementing components of food safety programs; and (2) Determine foodservice employees food-handling practices related to food safety.…

  9. AFCT/TFCT/ISFS Program. Technical progress report for the period October 1, 1977--December 31, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Hill, O.F. (comp.)

    1978-02-01

    This is the eighth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program, formerly the LWR Fuel Recycle Program. This program is designed to provide information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: Survey of Current Technology of Fuel Handling Techniques; Investigation of Air Cleaning Processes for Removing Tributyl Phosphate (TBP) from Off-Gas Streams; Study of Iodine Chemistry in Process Solutions; Electropolishing to Decontaminate Metallic Waste from Alternate and Thorium Converter Fuel Cycles; and U.S. Scale Transport, Dispersion and Removal Mode Comparison Safety Criticality Experiments. (11 figs., 7 tables)

  10. Development of a safety communication and recognition program for construction.

    Science.gov (United States)

    Sparer, Emily H; Herrick, Robert F; Dennerlein, Jack T

    2015-05-01

    Leading-indicator-based (e.g., hazard recognition) incentive programs provide an alternative to controversial lagging-indicator-based (e.g., injury rates) programs. We designed a leading-indicator-based safety communication and recognition program that incentivized safe working conditions. The program was piloted for two months on a commercial construction worksite and then redesigned using qualitative interview and focus group data from management and workers. We then ran the redesigned program for six months on the same worksite. Foremen received detailed weekly feedback from safety inspections, and posters displayed worksite and subcontractor safety scores. In the final program design, the whole site, not individual subcontractors, was the unit of analysis and recognition. This received high levels of acceptance from workers, who noted increased levels of site unity and team-building. This pilot program showed that construction workers value solidarity with others on site, demonstrating the importance of health and safety programs that engage all workers through a reliable and consistent communication infrastructure. © The Author(s) 2015 Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  11. Fusion Safety Program. Annual report, FY 1982

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1983-07-01

    The Fusion Safety Program major activities for Fiscal Year 1982 are summarized in this report. The program was started in FY-79, with the Idaho National Engineering Laboratory (INEL) designated as lead laboratory and EG and G Idaho, Inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., Activities at INEL includes major portions of papers dealing with ongoing work in tritium implantation experiments, tritium risk assessment, transient code development, heat transfer and fluid flow analysis, and high temperature oxidation and mobilization of structural material experiments. The section Outside Contracts includes studies of superconducting magnet safety conducted by Argonne National Laboratory, experiments concerning superconductor safety issues performed by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety and environmental studies by MIT, a summary of lithium safety experiments at Hanford Engineering Development Laboratory, and the results of tritium gas conversion to oxide experiments at Oak Ridge National Laboratory. A List of Publications and Proposed FY-83 Activities are also presented

  12. Division of Waste Management programs. Progress report, January-June 1979

    International Nuclear Information System (INIS)

    Lerch, R.E.; Allen, C.R.; Crippen, M.D.

    1980-10-01

    This is the twelfth progress report on Division of Waste Management programs being conducted at the Hanford Engineering Development Laboratory (HEDL) for the United States Department of Energy. The report describes progress in the first half of 1979 on the following programs: Acid Digestion of Combustible Wastes; and Chemical Treatment of Transuranic Contaminated Metals

  13. Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Technology. Period: 1 January - 30 June, 2002

    International Nuclear Information System (INIS)

    2002-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order to the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Managment Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.) [de

  14. Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Technology. Period: 1 July - 31 December 2001

    International Nuclear Information System (INIS)

    2002-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order to the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Managment Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.) [de

  15. 29 CFR 1960.12 - Dissemination of occupational safety and health program information.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Dissemination of occupational safety and health program... OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Administration § 1960.12 Dissemination of occupational safety and health program information. (a) Copies of the Act, Executive Order 12196, program...

  16. Safety Culture Perceptions in a Collegiate Aviation Program: A Systematic Assessment

    OpenAIRE

    Adjekum, Daniel Kwasi

    2014-01-01

    An assessment of the perceptions of respondents on the safety culture at an accredited Part 141 four year collegiate aviation program was conducted as part of the implementation of a safety management system (SMS). The Collegiate Aviation Program Safety Culture Assessment Survey (CAPSCAS), which was modified and revalidated from the existing Commercial Aviation Safety Survey (CASS), was used. Participants were drawn from flight students and certified flight instructors in the program. The sur...

  17. General-purpose heat source project and space nuclear safety and fuels program. Progress reportt, January 1980

    International Nuclear Information System (INIS)

    Maraman, W.J.

    1980-04-01

    This formal monthly report covers the studies related to the use of 238 PuO 2 in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are the general-purpose heat source development and space nuclear safety and fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work

  18. Effective radiological safety program for electron linear accelerators

    International Nuclear Information System (INIS)

    Swanson, W.P.

    1980-10-01

    An outline is presented of some of the main elements of an electron accelerator radiological safety program. The discussion includes types of accelerator facilities, types of radiations to be anticipated, activity induced in components, air and water, and production of toxic gases. Concepts of radiation shielding design are briefly discussed and organizational aspects are considered as an integral part of the overall safety program

  19. 41 CFR 128-1.8006 - Seismic Safety Program requirements.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Seismic Safety Program requirements. 128-1.8006 Section 128-1.8006 Public Contracts and Property Management Federal Property Management Regulations System (Continued) DEPARTMENT OF JUSTICE 1-INTRODUCTION 1.80-Seismic Safety Program...

  20. Fusion Safety Program annual report, Fiscal Year 1993

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1993-12-01

    This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG ampersand G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies

  1. Nuclear Safety Research Reactor (NSRR) program in JAERI

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, M; Hoshi, T; Ohnishi, N; Fujishiro, T; Inabe, T [Japan Atomic Energy Research Institute (Japan)

    1974-07-01

    An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power reactors so as to establish realistic safety criteria and to develop analytical models for prediction of fuel failures. We expect to contribute finally to the improvement of reactor design and fuel fabrication techniques based on these experimental results. The NSRR experiments will be performed in the large central experimental tube, which is one of the most excellent features of this reactor, using specially designed capsules or loops which can accommodate up to 49 BWR type test fuels. Many types of test fuels in various conditions will be examined by the NSRR program, such as BWR, PWR and FBR type fuels from the beginning of life to the end of life with and without simulated reactor internal structures. The experiments will be continued for more than 10 years divided into three phases. The first phase of the program will be devoted to the experiments pertaining to reactivity initiated accidents (RIA). In these experiments we will make use of the excellent pulsing capability of ACPR, which is expected to generate 100 MW-sec prompt energy release with 1.3 msec of minimum reactor period by 4.7 dollar reactivity insertion and to yield more than 280 cal/g-UO{sub 2} heat deposit even in an approximately 10% enriched BWR type test fuel. (280 cal/g-UO{sub 2} is believed enough heat deposit to cause fuel failure.) In general, heat flow behaviors from fuel meat to clad and from clad to coolant are very complex phenomena, but they are the key point in analyzing transient response of fuels. In the sudden heat transient conditions brought by pulsing, however, it will be possible to examine each phenomenon

  2. Nuclear Safety Research Reactor (NSRR) program in JAERI

    International Nuclear Information System (INIS)

    Ishikawa, M.; Hoshi, T.; Ohnishi, N.; Fujishiro, T.; Inabe, T.

    1974-01-01

    An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power reactors so as to establish realistic safety criteria and to develop analytical models for prediction of fuel failures. We expect to contribute finally to the improvement of reactor design and fuel fabrication techniques based on these experimental results. The NSRR experiments will be performed in the large central experimental tube, which is one of the most excellent features of this reactor, using specially designed capsules or loops which can accommodate up to 49 BWR type test fuels. Many types of test fuels in various conditions will be examined by the NSRR program, such as BWR, PWR and FBR type fuels from the beginning of life to the end of life with and without simulated reactor internal structures. The experiments will be continued for more than 10 years divided into three phases. The first phase of the program will be devoted to the experiments pertaining to reactivity initiated accidents (RIA). In these experiments we will make use of the excellent pulsing capability of ACPR, which is expected to generate 100 MW-sec prompt energy release with 1.3 msec of minimum reactor period by 4.7 dollar reactivity insertion and to yield more than 280 cal/g-UO 2 heat deposit even in an approximately 10% enriched BWR type test fuel. (280 cal/g-UO 2 is believed enough heat deposit to cause fuel failure.) In general, heat flow behaviors from fuel meat to clad and from clad to coolant are very complex phenomena, but they are the key point in analyzing transient response of fuels. In the sudden heat transient conditions brought by pulsing, however, it will be possible to examine each phenomenon separately

  3. Implementation of a patient safety program at a tertiary health system: A longitudinal analysis of interventions and serious safety events.

    Science.gov (United States)

    Cropper, Douglas P; Harb, Nidal H; Said, Patricia A; Lemke, Jon H; Shammas, Nicolas W

    2018-04-01

    We hypothesize that implementation of a safety program based on high reliability organization principles will reduce serious safety events (SSE). The safety program focused on 7 essential elements: (a) safety rounding, (b) safety oversight teams, (c) safety huddles, (d) safety coaches, (e) good catches/safety heroes, (f) safety education, and (g) red rule. An educational curriculum was implemented focusing on changing high-risk behaviors and implementing critical safety policies. All unusual occurrences were captured in the Midas system and investigated by risk specialists, the safety officer, and the chief medical officer. A multidepartmental committee evaluated these events, and a root cause analysis (RCA) was performed. Events were tabulated and serious safety event (SSE) recorded and plotted over time. Safety success stories (SSSs) were also evaluated over time. A steady drop in SSEs was seen over 9 years. Also a rise in SSSs was evident, reflecting on staff engagement in the program. The parallel change in SSEs, SSSs, and the implementation of various safety interventions highly suggest that the program was successful in achieving its goals. A safety program based on high-reliability organization principles and made a core value of the institution can have a significant positive impact on reducing SSEs. © 2018 American Society for Healthcare Risk Management of the American Hospital Association.

  4. MORT: a safety management program developed for ERDA

    International Nuclear Information System (INIS)

    1977-03-01

    ERDA's System Safety Development Center (SSDC) is located at the Idaho National Engineering Laboratory under the EG and G Idaho, Inc., contract administered by the Idaho Operations Office. The SSDC performs a variety of tasks for ERDA's Division of Safety, Standards, and Compliance, for the purpose of improvement and application of safety program elements. Primary among these tasks are development and demonstration of new methodologies, training, consultation, and technical writing. This information package (ERDA 77-38) is an example of the later task, aimed at communicating to a general audience the nature and purpose of major features of the Management Oversight and Risk Tree (MORT) program. The SSDC also originates a guideline series of monographs (the ERDA 76-45 series) for individuals who desire more specific explanations of the MORT program

  5. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  6. Nuclear criticality safety specialist training and qualification programs

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1993-01-01

    Since the beginning of the Nuclear Criticality Safety Division of the American Nuclear Society (ANS) in 1967, the nuclear criticality safety (NCS) community has sought to provide an exchange of information at a national level to facilitate the education and development of NCS specialists. In addition, individual criticality safety organizations within government contractor and licensed commercial nonreactor facilities have developed training and qualification programs for their NCS specialists. However, there has been substantial variability in the content and quality of these program requirements and personnel qualifications, at least as measured within the government contractor community. The purpose of this paper is to provide a brief, general history of staff training and to describe the current direction and focus of US DOE guidance for the content of training and qualification programs designed to develop NCS specialists

  7. 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

  8. Safety risk management of underground engineering in China: Progress, challenges and strategies

    Directory of Open Access Journals (Sweden)

    Qihu Qian

    2016-08-01

    Full Text Available Underground construction in China is featured by large scale, high speed, long construction period, complex operation and frustrating situations regarding project safety. Various accidents have been reported from time to time, resulting in serious social impact and huge economic loss. This paper presents the main progress in the safety risk management of underground engineering in China over the last decade, i.e. (1 establishment of laws and regulations for safety risk management of underground engineering, (2 implementation of the safety risk management plan, (3 establishment of decision support system for risk management and early-warning based on information technology, and (4 strengthening the study on safety risk management, prediction and prevention. Based on the analysis of the typical accidents in China in the last decade, the new challenges in the safety risk management for underground engineering are identified as follows: (1 control of unsafe human behaviors; (2 technological innovation in safety risk management; and (3 design of safety risk management regulations. Finally, the strategies for safety risk management of underground engineering in China are proposed in six aspects, i.e. the safety risk management system and policy, law, administration, economy, education and technology.

  9. Research projects into the safety of nuclear power plants. Period covered: 01. July - 31. December 2004. Progress report

    International Nuclear Information System (INIS)

    2004-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  10. Japan`s international cooperation programs on seismic safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

    1997-03-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  11. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology. Reported period: January 1 to June 30, 1993

    International Nuclear Information System (INIS)

    1993-01-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977 - 1980 of the BMFT. Another table of uses the same classification system as applied in the nuclear safety index of the CEC (Commision of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig.) [de

  12. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology. Reported period: January 1 to June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977 - 1980 of the BMFT. Another table of uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig.) [de

  13. Safety implications of standardized continuous quality improvement programs in community pharmacy.

    Science.gov (United States)

    Boyle, Todd A; Ho, Certina; Mackinnon, Neil J; Mahaffey, Thomas; Taylor, Jeffrey M

    2013-06-01

    Standardized continuous quality improvement (CQI) programs combine Web-based technologies and standardized improvement processes, tools, and expectations to enable quality-related events (QREs) occurring in individual pharmacies to be shared with pharmacies in other jurisdictions. Because standardized CQI programs are still new to community pharmacy, little is known about how they impact medication safety. This research identifies key aspects of medication safety that change as a result of implementing a standardized CQI program. Fifty-three community pharmacies in Nova Scotia, Canada, adopted the SafetyNET-Rx standardized CQI program in April 2010. The Institute for Safe Medication Practices (ISMP) Canada's Medication Safety Self-Assessment (MSSA) survey was administered to these pharmacies before and 1 year into their use of the SafetyNET-Rx program. The nonparametric Wilcoxon signed-rank test was used to explore where changes in patient safety occurred as a result of SafetyNETRx use. Significant improvements occurred with quality processes and risk management, staff competence, and education, and communication of drug orders and other information. Patient education, environmental factors, and the use of devices did not show statistically significant changes. As CQI programs are designed to share learning from QREs, it is reassuring to see that the largest improvements are related to quality processes, risk management, staff competence, and education.

  14. Progress of the RERTR program in 1999

    International Nuclear Information System (INIS)

    Travelli, A.

    1999-01-01

    This paper describes the progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners during 1999 and discusses planned activities for the coming year

  15. Safety and economic impacts of photo radar program.

    Science.gov (United States)

    Chen, Greg

    2005-12-01

    Unsafe speed is one of the major traffic safety challenges facing motorized nations. In 2003, unsafe speed contributed to 31 percent of all fatal collisions, causing a loss of 13,380 lives in the United States alone. The economic impact of speeding is tremendous. According to NHTSA, the cost of unsafe speed related collisions to the American society exceeds 40 billion US dollars per year. In response, automated photo radar speed enforcement programs have been implemented in many countries. This study assesses the economic impacts of a large-scale photo radar program in British Columbia. The knowledge generated from this study could inform policy makers and project managers in making informed decisions with regard to this highly effective and efficient, yet very controversial program. This study establishes speed and safety effects of photo radar programs by summarizing two physical impact investigations in British Columbia. It then conducts a cost-benefit analysis to assess the program's economic impacts. The cost-benefit analysis takes into account both societal and funding agency's perspectives. It includes a comprehensive account of major impacts. It uses willingness to pay principle to value human lives saved and injuries avoided. It incorporates an extended sensitivity analysis to quantify the robustness of base case conclusions. The study reveals an annual net benefit of approximately 114 million in year 2001 Canadian dollars to British Columbians. The study also finds a net annual saving of over 38 million Canadian dollars for the Insurance Corporation of British Columbia (ICBC) that funded the program. These results are robust under almost all alternative scenarios tested. The only circumstance under which the net benefit of the program turns negative is when the real safety effects were one standard deviation below the estimated values, which is possible but highly unlikely. Automated photo radar traffic safety enforcement can be an effective and efficient

  16. Developing an integrated dam safety program

    International Nuclear Information System (INIS)

    Nielsen, N. M.; Lampa, J.

    1996-01-01

    An effort has been made to demonstrate that dam safety is an integral part of asset management which, when properly done, ensures that all objectives relating to safety and compliance, profitability, stakeholders' expectations and customer satisfaction, are achieved. The means to achieving this integration of the dam safety program and the level of effort required for each core function have been identified using the risk management approach to pinpoint vulnerabilities, and subsequently to focus priorities. The process is considered appropriate for any combination of numbers, sizes and uses of dams, and is designed to prevent exposure to unacceptable risks. 5 refs., 1 tab

  17. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology. Reported period: July 1 to December 31, 1986. Progress report

    International Nuclear Information System (INIS)

    1987-05-01

    Investigations on the safety of light water reactors (LWR) being performed in the framework of the research program on reactor safety (RS-projects) are sponsored by the Federal Ministry for Research and Technology (BMFT). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The individual reports are classified according to the research program on the safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  18. Research and development program in reactor safety for NUCLEBRAS

    International Nuclear Information System (INIS)

    Pinheiro, R.B.; Resende Lobo, A.A. de; Horta, J.A.L.; Avelar Esteves, F. de; Lepecki, W.P.S.; Mohr, K.; Selvatici, E.

    1984-01-01

    With technical assistance from the IAEA, it was established recently an analytical and experimental Research and Development Program for NUCLEBRAS in the area of reactor safety. The main objectives of this program is to make possible, with low investments, the active participation of NUCLEBRAS in international PWR safety research. The analytical and experimental activities of the program are described with some detail, and the main results achieved up to now are presented. (Author) [pt

  19. The Nordic safety program on accident consequence assessment

    International Nuclear Information System (INIS)

    Tveten, U.

    1988-01-01

    One important part of Nordic cooperation is partially funded by the Nordic Council of Ministers, namely the work performed within the Nordic Safety Program (often referred to as the NKA projects). NKA is the Nordic abbreviation of the Nordic Liaison Committee on Atomic Energy. One program area in the present four-year period is concerned with problems related to reactor accident consequence assessment, and contains almost twenty projects covering a wide range of subjects. The author is program coordinator for this program area. The program will be completed in 1989. The program was strongly influenced by Chernobyl, and a number of new projects were included in the program in 1986. Involved in the program are these Nordic institutions: Riso National Laboratory (Denmark). Technical Research Centre of Finland. Finnish Centre for Radiation and Nuclear Safety. Finnish Meteorological Institute. Institute for Energy Technology (Norway). Agricultural University of Norway. Meteorological Institute of Norway. Studsvik Energiteknik AB (Sweden). National Defence Research Laboratory (Sweden)

  20. Systems Analysis of NASA Aviation Safety Program: Final Report

    Science.gov (United States)

    Jones, Sharon M.; Reveley, Mary S.; Withrow, Colleen A.; Evans, Joni K.; Barr, Lawrence; Leone, Karen

    2013-01-01

    A three-month study (February to April 2010) of the NASA Aviation Safety (AvSafe) program was conducted. This study comprised three components: (1) a statistical analysis of currently available civilian subsonic aircraft data from the National Transportation Safety Board (NTSB), the Federal Aviation Administration (FAA), and the Aviation Safety Information Analysis and Sharing (ASIAS) system to identify any significant or overlooked aviation safety issues; (2) a high-level qualitative identification of future safety risks, with an assessment of the potential impact of the NASA AvSafe research on the National Airspace System (NAS) based on these risks; and (3) a detailed, top-down analysis of the NASA AvSafe program using an established and peer-reviewed systems analysis methodology. The statistical analysis identified the top aviation "tall poles" based on NTSB accident and FAA incident data from 1997 to 2006. A separate examination of medical helicopter accidents in the United States was also conducted. Multiple external sources were used to develop a compilation of ten "tall poles" in future safety issues/risks. The top-down analysis of the AvSafe was conducted by using a modification of the Gibson methodology. Of the 17 challenging safety issues that were identified, 11 were directly addressed by the AvSafe program research portfolio.

  1. Management of radioactive material safety programs at medical facilities. Final report

    International Nuclear Information System (INIS)

    Camper, L.W.; Schlueter, J.; Woods, S.

    1997-05-01

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution's executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC's reporting and notification requirements are discussed, and a general description is given of how NRC's licensing, inspection and enforcement programs work

  2. 29 CFR 1960.80 - Secretary's evaluations of agency occupational safety and health programs.

    Science.gov (United States)

    2010-07-01

    ... EMPLOYEE OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Evaluation of Federal Occupational Safety and Health Programs § 1960.80 Secretary's evaluations of agency occupational safety and health... evaluating an agency's occupational safety and health program. To accomplish this, the Secretary shall...

  3. Fusion Safety Program annual report: Fiscal year 1987

    International Nuclear Information System (INIS)

    Holland, D.F.; Herring, J.S.; Longhurst, G.R.; Lyon, R.E.; Merrill, B.J.; Piet, S.J.

    1988-02-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1987. The Idaho National Engineering Laboratory (INEL) is the designated lead laboraotry and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. Activities are conducted at the INEL and in participating laboratories including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment methodology, computer codes development for reactor transients, and fusion waste management. Also included in the report is a summary of the safety and environmental analysis and conventional facilities design performed by INEL for the Compact Ignition Tokamak design project, the safety analysis and documentation performed for the Tokamak Ignition/Burn Experimental Reactor design, and the technical support provided to the Environmental Safety and Economics Committee (ESECOM). 42 refs., 17 figs., 4 tabs

  4. High-heat tank safety issue resolution program plan. Revision 2

    International Nuclear Information System (INIS)

    Wang, O.S.

    1994-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank 241-C-106. The heat source of approximately 110,000 Btu/hr is the radioactive decay of the stored waste material (primarily 90 Sr) inadvertently transferred into the tank in the later 1960s. Currently, forced ventilation, with added water to promote thermal conductivity and evaporation cooling, is used for heat removal. The method is very effective and economical. At this time, the only viable solution identified to permanently resolve this safety issue is the removal of heat-generating waste in the tank. This solution is being aggressively pursued as the only remediation method to this safety issue, and tank 241-C-106 has been selected as the first single-shell tank for retrieval. The current cooling method and other alternatives are addressed in this program as means to mitigate this safety issue before retrieval. This program plan has three parts. The first part establishes program objectives and defines safety issue, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and other alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. A table of best-estimate schedules for the key tasks is also included in this program plan

  5. 29 CFR 1960.79 - Self-evaluations of occupational safety and health programs.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Self-evaluations of occupational safety and health programs. 1960.79 Section 1960.79 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH... AND HEALTH PROGRAMS AND RELATED MATTERS Evaluation of Federal Occupational Safety and Health Programs...

  6. A program approach for site safety at oil spills

    International Nuclear Information System (INIS)

    Whipple, F.L.; Glenn, S.P.; Ocken, J.J.; Ott, G.L.

    1993-01-01

    When OSHA developed the hazardous waste operations (Hazwoper) regulations (29 CFR 1910.120) members of the response community envisioned a separation of oil and open-quotes hazmatclose quotes response operations. Organizations that deal with oil spills have had difficulty applying Hazwoper regulations to oil spill operations. This hinders meaningful implementation of the standard for their personnel. We should approach oil spills with the same degree of caution that is applied to hazmat response. Training frequently does not address the safety of oil spill response operations. Site-specific safety and health plans often are neglected or omitted. Certain oils expose workers to carcinogens, as well as chronic and acute hazards. Significant physical hazards are most important. In responding to oil spills, the hazards must be addressed. It is the authors' contention that a need exists for safety program at oil spill sites. Gone are the days of labor pool hires cleaning up spills in jeans and sneakers. The key to meaningful programs for oil spills requires application of controls focused on relevant safety risks rather than minimal chemical exposure hazards. Working with concerned reviewers from other agencies and organizations, the authors have developed a general safety and health program for oil spill response. It is intended to serve as the basis for organizations to customize their own written safety and health program (required by OSHA). It also provides a separate generic site safety plan for emergency phase oil spill operations (check-list) and long term post-emergency phase operations

  7. Integrated program of using of Probabilistic Safety Analysis in Spain

    International Nuclear Information System (INIS)

    1998-01-01

    Since 25 June 1986, when the CSN (Nuclear Safety Conseil) approve the Integrated Program of Probabilistic Safety Analysis, this program has articulated the main activities of CSN. This document summarize the activities developed during these years and reviews the Integrated programme

  8. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF's management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES ampersand H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES ampersand H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES ampersand H support organizations and administrative groups, and describes their interactions with the NIF Program

  9. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF`s management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES&H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES&H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES&H support organizations and administrative groups, and describes their interactions with the NIF Program.

  10. Research projects into the safety of nuclear power plants. Period cover 01. January - 30. June 2017. Progress report

    International Nuclear Information System (INIS)

    2017-01-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to the topic areas of reactor safety research. The reports are arranged in sequence of their project numbers. Ilt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  11. Management of radioactive material safety programs at medical facilities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Camper, L.W.; Schlueter, J.; Woods, S. [and others

    1997-05-01

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

  12. Research program on regulatory safety research - Synthesis report 2008

    International Nuclear Information System (INIS)

    Mailaender, R

    2009-06-01

    This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2008 and the results obtained. The main points of the research program, which is co-ordinated by the Swiss Federal Nuclear Safety Inspectorate ENSI, are discussed. Topics covered concern reactor safety as well as human, organisational and safety aspects. Work done in several areas concerning reactor safety and materials as well as interactions in severe accidents in light-water reactors is described. Radiation protection, the transport and disposal of radioactive wastes and safety culture are also looked at. Finally, national and international co-operation is briefly looked at and work to be done in 2009 is reviewed. The report is completed with a list of research and development projects co-ordinated by ENSI

  13. Fast reactor test facilities in the US safety program

    International Nuclear Information System (INIS)

    Avery, R.; Dickerman, C.E.; Lennox, D.H.; Rose, D.

    1979-01-01

    The needs for safety information derivable from in-pile programs are reviewed, and the correlation made with existing and planned capability. In view of the current status of the U.S. breeder program, emphasis is given in the review to the impact of different fast breeder options on the required program and facilities. It is concluded that facility needs are somewhat independent of specific fast breeder concept, even though the relative emphasis on the various safety issues will differ. 8 refs

  14. MCNP Progress & Performance Improvements

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bull, Jeffrey S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-04-14

    Twenty-eight slides give information about the work of the US DOE/NNSA Nuclear Criticality Safety Program on MCNP6 under the following headings: MCNP6.1.1 Release, with ENDF/B-VII.1; Verification/Validation; User Support & Training; Performance Improvements; and Work in Progress. Whisper methodology will be incorporated into the code, and run speed should be increased.

  15. A reliability program approach to operational safety

    International Nuclear Information System (INIS)

    Mueller, C.J.; Bezella, W.A.

    1985-01-01

    A Reliability Program (RP) model based on proven reliability techniques is being formulated for potential application in the nuclear power industry. Methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed and a review of current nuclear risk-dominant issues conducted. The need for a reliability approach to address dependent system failures, operating and emergency procedures and human performance, and develop a plant-specific performance data base for safety decision making is demonstrated. Current research has concentrated on developing a Reliability Program approach for the operating phase of a nuclear plant's lifecycle. The approach incorporates performance monitoring and evaluation activities with dedicated tasks that integrate these activities with operation, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the Reliability Program. (orig./HP)

  16. Seismic safety margin assessment program (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    Suzuki, Kenichi; Iijima, Toru; Inagaki, Masakatsu; Taoka, Hideto; Hidaka, Shinjiro

    2011-01-01

    Seismic capacity test data, analysis method and evaluation code provided by Seismic Safety Margin Assessment Program have been utilized for the support of seismic back-check evaluation of existing plants. The summary of the program in 2010 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. Many seismic capacity tests of various snubbers were conducted and quantitative seismic capacities were evaluated. One of the emergency diesel generator partial-model seismic capacity tests was conducted and quantitative seismic capacity was evaluated. Some of the analytical evaluations of piping-system seismic capacities were conducted. 2. Analysis method for minute evaluation of component seismic response. The difference of seismic response of large components such as primary containment vessel and reactor pressure vessel when they were coupled with 3-dimensional FEM building model or 1-dimensional lumped mass building model, was quantitatively evaluated. 3. Evaluation code for quantitative evaluation of seismic safety margin of systems, structures and components. As the example, quantitative evaluation of seismic safety margin of systems, structures and components were conducted for the reference plant. (author)

  17. Reactor technology. Progress report, January--March 1978

    International Nuclear Information System (INIS)

    Warren, J.L.

    1978-07-01

    Progress is reported in eight program areas. The nuclear Space Electric Power Supply Program examined safety questions in the aftermath of the COSMOS 954 incident, examined the use of thermoelectric converters, examined the neutronic effectiveness of various reflecting materials, examined ways of connecting heat pipes to one another, studied the consequences of the failure of one heat pipe in the reactor core, and did conceptual design work on heat radiators for various power supplies. The Heat Pipe Program reported progress in the design of ceramic heat pipes, new application of heat pipes to solar collectors, and final performance tests of two pipes for HEDL applications. Under the Nuclear Process Heat Program, work continues on computer codes to model a pebble bed high-temperature gas-cooled reactor, adaptation of a set of German reactor calculation codes to use on U.S. computers, and a parametric study of a certain resonance integral required in reactor studies. Under the Nonproliferation Alternative Sources Assessment Program LASL has undertaken an evaluation of a study of gaseous core reactors by Southern Science Applications, Inc. Independently LASL has developed a proposal for a comprehensive study of gaseous uranium-fueled reactor technology. The Plasma Core Reactor Program has concentrated on restacking the beryllium reflector and redesigning the nuclear control system. The status of and experiments on four critical assemblies, SKUA, Godiva IV, Big Ten, and Flattop, are reported. The Nuclear Criticality Safety Program carried out several tasks including conducting a course, doing several annual safety reviews and evaluating the safety of two Nevada test devices. During the quarter one of the groups involved in reactor technology has acquired responsibility for the operation of a Cockroft-Walton accelerator. The present report contains information on the use of machine and improvements being made in its operation

  18. Correlation between safety climate and contractor safety assessment programs in construction.

    Science.gov (United States)

    Sparer, Emily H; Murphy, Lauren A; Taylor, Kathryn M; Dennerlein, Jack T

    2013-12-01

    Contractor safety assessment programs (CSAPs) measure safety performance by integrating multiple data sources together; however, the relationship between these measures of safety performance and safety climate within the construction industry is unknown. Four hundred and one construction workers employed by 68 companies on 26 sites and 11 safety managers employed by 11 companies completed brief surveys containing a nine-item safety climate scale developed for the construction industry. CSAP scores from ConstructSecure, Inc., an online CSAP database, classified these 68 companies as high or low scorers, with the median score of the sample population as the threshold. Spearman rank correlations evaluated the association between the CSAP score and the safety climate score at the individual level, as well as with various grouping methodologies. In addition, Spearman correlations evaluated the comparison between manager-assessed safety climate and worker-assessed safety climate. There were no statistically significant differences between safety climate scores reported by workers in the high and low CSAP groups. There were, at best, weak correlations between workers' safety climate scores and the company CSAP scores, with marginal statistical significance with two groupings of the data. There were also no significant differences between the manager-assessed safety climate and the worker-assessed safety climate scores. A CSAP safety performance score does not appear to capture safety climate, as measured in this study. The nature of safety climate in construction is complex, which may be reflective of the challenges in measuring safety climate within this industry. Am. J. Ind. Med. 56:1463-1472, 2013. © 2013 Wiley Periodicals, Inc. © 2013 Wiley Periodicals, Inc.

  19. Light-water-reactor safety program. Quarterly progress report, April--June 1977

    International Nuclear Information System (INIS)

    Sachs, R.G.; Kyger, J.A.

    1977-01-01

    The report summarizes work performed on the following water-reactor-safety problems: (1) loss-of-coolant accident research in heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies

  20. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Education, Science, Research and Technology. Reported period: January 1 to June 30, 1995

    International Nuclear Information System (INIS)

    1995-01-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Research Management Division at the GRS within the framework of general informations of progress in reactor safety research. The individual reports are classified according to projects of the reactor safety research program. Another table uses the same classification system as applied in the nuclear safety index of the CEC (Commision of the European Communities), IAEA (International Atomic Energy Agency) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP) [de

  1. 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...

  2. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-06-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Forschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  3. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-11-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  4. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  5. Probabilistic studies for a safety assurance program

    International Nuclear Information System (INIS)

    Iyer, S.S.; Davis, J.F.

    1985-01-01

    The adequate supply of energy is always a matter of concern for any country. Nuclear power has played, and will continue to play an important role in supplying this energy. However, safety in nuclear power production is a fundamental prerequisite in fulfilling this role. This paper outlines a program to ensure safe operation of a nuclear power plant utilizing the Probabilistic Safety Studies

  6. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  7. Guidance for implementing an environmental, safety, and health-assurance program. Volume 15. A model plan for line organization environmental, safety, and health-assurance programs

    Energy Technology Data Exchange (ETDEWEB)

    Ellingson, A.C.; Trauth, C.A. Jr.

    1982-01-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This particular document presents a model operational-level ES and H Assurance Program that may be used as a guide by an operational-level organization in developing its own plan. The model presented here reflects the guidance given in the total series of 15 documents.

  8. Canadian Nuclear Safety Commission's intern program

    International Nuclear Information System (INIS)

    Gilmour, P.E.

    2002-01-01

    The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

  9. High-temperature gas-cooled reactor safety-reliability program plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-01

    The purpose of this document is to present a safety plan as part of an overall program plan for the design and development of the High Temperature Gas-Cooled Reactor (HTGR). This plan is intended to establish a logical framework for identifying the technology necessary to demonstrate that the requisite degree of public risk safety can be achieved economically. This plan provides a coherent system safety approach together with goals and success criterion as part of a unifying strategy for licensing a lead reactor plant in the near term. It is intended to provide guidance to program participants involved in producing a technology base for the HTGR that is fully responsive to safety consideration in the design, evaluation, licensing, public acceptance, and economic optimization of reactor systems.

  10. Area Safety Program for the tokamak fusion test reactor (TFTR)

    International Nuclear Information System (INIS)

    Rappe, G.M.

    1984-10-01

    Overall the Area Safety Program has proved to be a very successful operation. There is no doubt that a safety program organized through line management is the best way to involve all personnel. Naturally, when the program was first started, there was some criticism and a certain resistance on the part of a few individuals to fully participate. However, once the program was underway and it could be seen that it was working to everyone's advantage, this reluctance disappeared and a spirit of full cooperation is now enjoyed. It is very important that for this success to continue there must be a two way flow of information, both from the Area Safety Coordinators up through line management, and from senior management, with decisions and answers, back down through the management chain with the utmost dispatch. As with all programs, there is still room for improvement. This program has started a review cycle with a view to streamlining certain areas and possibly increasing its scope in others

  11. AFCT/TFCT/ISFS Program. Technical progress report for the period April 1, 1978--June 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Hill, O.F. (comp.)

    1978-08-01

    This is the tenth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program. This program provides information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: thorium resource price analyses; spent fuel receipt and storage; investigation of air cleaning processes for removing TBP from off-gas streams; study of iodine chemistry in process solutions, high-level waste treatment; electropolishing to decontaminate metallic waste from alternate and thorium converter fuel cycles; U.S. scale transport, dispersion and removal model comparison; safety criticality experiments; and criticality research in support of thorium fuel cycle.

  12. Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W B; Passiakos, M

    1980-06-01

    This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

  13. Lessons learned from the safety assistance program for soviet-designed reactors

    International Nuclear Information System (INIS)

    Steinberg, N.

    1999-01-01

    Two examples of nuclear power situation were compared in this conference paper - the situation in Lithuania and the situation in the Ukraine. Based on the examples mentioned, author conclude that the effectiveness of the Multi-National Safety Assistance Program for Soviet -Designed Reactors in a given recipient country does not depend, in practice, on engineering issues. The principal aspects that determine this effectiveness are: first, the level of safety culture in the country, beginning at the Governmental level but also at the level of the senior managers of nuclear power. The other important factor which contributes is the availability of a well-developed national program for upgrading NPP safety. The economical well-being of nuclear power and of the country as a whole also has a major effect on the effectiveness of the western technical assistance programs that are trying to upgrade reactor safety in a particular recipient country. And finally, international community should have well coordinated and well substantiated safety assistance program for specific country

  14. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  15. Determining Safety Inspection Thresholds for Employee Incentives Programs on Construction Sites.

    Science.gov (United States)

    Sparer, Emily; Dennerlein, Jack

    2013-01-01

    The goal of this project was to evaluate approaches of determining the numerical value of a safety inspection score that would activate a reward in an employee safety incentive program. Safety inspections are a reflection of the physical working conditions at a construction site and provide a safety score that can be used in incentive programs to reward workers. Yet it is unclear what level of safety should be used when implementing this kind of program. This study explored five ways of grouping safety inspection data collected during 19 months at Harvard University-owned construction projects. Each approach grouped the data by one of the following: owner, general contractor, project, trade, or subcontractor. The median value for each grouping provided the threshold score. These five approaches were then applied to data from a completed project in order to calculate the frequency and distribution of rewards in a monthly safety incentive program. The application of each approach was evaluated qualitatively for consistency, competitiveness, attainability, and fairness. The owner-specific approach resulted in a threshold score of 96.3% and met all of the qualitative evaluation goals. It had the most competitive reward distribution (only 1/3 of the project duration) yet it was also attainable. By treating all workers equally and maintaining the same value throughout the project duration, this approach was fair and consistent. The owner-based approach for threshold determination can be used by owners or general contractors when creating leading indicator incentives programs and by researchers in future studies on incentive program effectiveness.

  16. MedWatch, the FDA Safety Information and Adverse Event Reporting Program

    Science.gov (United States)

    ... Reporting Program MedWatch: The FDA Safety Information and Adverse Event Reporting Program Share Tweet Linkedin Pin it ... approved information that can help patients avoid serious adverse events. Potential Signals of Serious Risks/New Safety ...

  17. 78 FR 66987 - Railroad Safety Technology Program Grant Program

    Science.gov (United States)

    2013-11-07

    ... carriers, railroad suppliers, and State and local governments for projects that have a public benefit of... projects . . . that have a public benefit of improved safety and network efficiency.'' To be eligible for... million. This grant program has a maximum 80-percent Federal and minimum 20-percent grantee cost share...

  18. Water reactor safety research program. A description of current and planned research

    International Nuclear Information System (INIS)

    1978-07-01

    The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

  19. Development of nuclear safety issues program

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

    2006-12-15

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

  20. Development of nuclear safety issues program

    International Nuclear Information System (INIS)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

    2006-12-01

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

  1. Operational safety

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The PNL Safety, Standards and Compliance Program contributed to the development and issuance of safety policies, standards, and criteria; for projects in the nuclear and nonnuclear areas. During 1976 the major emphasis was on developing criteria, instruments and methods to assure that radiation exposure to occupational personnel and to people in the environs of nuclear-related facilities is maintained at the lowest level technically and economically practicable. Progress in 1976 is reported on the preparation of guidelines for radiation exposure; Pu dosimetry studies; the preparation of an environmental monitoring handbook; and emergency instrumentation preparedness

  2. Electronuclear's safety culture assessment and enhancement program

    International Nuclear Information System (INIS)

    Selvatici, E.; Diaz-Francisco, J.M.; Diniz de Souza, V.

    2002-01-01

    The present paper describes the Eletronuclear's safety culture assessment and enhancement program. The program was launched by the company's top management one year after the creation of Eletronuclear in 1997, from the merging of two companies with different organizational cultures, the design and engineering company Nuclen and the nuclear directorate of the Utility Furnas, Operator of the Angra1 NPP. The program consisted of an assessment performed internally in 1999 with the support and advice of the IAEA. This assessment, performed with the help of a survey, pooled about 80% of the company's employees. The overall result of the assessment was that a satisfactory level of safety culture existed; however, a number of points with a considerable margin for improvement were also identified. These points were mostly related with behavioural matters such as motivation, stress in the workplace, view of mistakes, handling of conflicts, and last but not least a view by a considerable number of employees that a conflict between safety and production might exist. An Action Plan was established by the company managers to tackle these weak points. This Plan was issued as company guideline by the company's Directorate. The subsequent step was to detail and implement the different actions of the Plan, which is the phase that we are at present. In the detailing of the Action Plan, special care was taken to sum up efforts, avoiding duplication of work or competition with already existing programs. In this process it was identified that the company had a considerable number of initiatives directly related to organizational and safety culture improvement, already operational. These initiatives have been integrated in the detailed Action Plan. A new assessment, for checking the effectiveness of the undertaken actions, is planned for 2003. (author)

  3. Semiannual progress report for the Idaho Geothermal Program, April 1-September 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Parker, J.T. (ed.)

    1982-01-01

    Modifications incorporated in the 5-MW Pilot Power Plant at Raft River Geothermal Test Site, system operational testing and maintenance activities at that plant, and the water treatment program's corrosion studies are summarized. Progress is reported on performance tests of the ORNL condenser and the direct-contact heat exchanger in the Prototype Power Plant. Production-injection tests associated with pump installation in monitor wells at Raft River are reported. Case studies conducted and publications prepared for the program of low-to moderate-temperature hydrothermal resource development are also reported. Monitoring activities and studies of the environmental program at Raft River are described and two new areas of research under the Environmental Support Injection Research Program: pressure monitoring, and dispersion studies. Progress of three successful proposers under the User-Coupled Confirmation Drilling Program is summarized. A program to encourage use of geothermal energy at Federal facilities was developed and initiated. Investigation of direct use of hydrothermal energy is reported. Progress is reported on the marketing Assistance Program, through which technical information and assistance are provided to potential users and developers of geothermal resources. Also reported is progress on DOE's Program Opportunity Notice (PON) Program demonstration projects and the Program Research and Development Announcement (PRDA) Program study projects.

  4. Applying health education theory to patient safety programs: three case studies.

    Science.gov (United States)

    Gilkey, Melissa B; Earp, Jo Anne L; French, Elizabeth A

    2008-04-01

    Program planning for patient safety is challenging because intervention-oriented surveillance data are not yet widely available to those working in this nascent field. Even so, health educators are uniquely positioned to contribute to patient safety intervention efforts because their theoretical training provides them with a guide for designing and implementing prevention programs. This article demonstrates the utility of applying health education concepts from three prominent patient safety campaigns, including the concepts of risk perception, community participation, and social marketing. The application of these theoretical concepts to patient safety programs suggests that health educators possess a knowledge base and skill set highly relevant to patient safety and that their perspective should be increasingly brought to bear on the design and evaluation of interventions that aim to protect patients from preventable medical error.

  5. Effect of generic issues program on improving safety

    International Nuclear Information System (INIS)

    Fard, M. R.; Kauffman, J. V.

    2010-01-01

    The U.S. Nuclear Regulatory Commission (NRC) identifies (by its assessment of plant operation) certain issues involving public health and safety, the common defense and security, or the environment that could affect multiple entities under NRC jurisdiction. The Generic Issues Program (GIP) addresses the resolution of these Generic Issues (GIs). The resolution of these issues may involve new or revised rules, new or revised guidance, or revised interpretation of rules or guidance that affect nuclear power plant licensees, nuclear material certificate holders, or holders of other regulatory approvals. U.S. NRC provides information related to the past and ongoing GIP activities to the general public by the use of three main resources, namely NUREG-0933, 'Resolution of Generic Safety Issues, ' Generic Issues Management Control System (GIMCS), and GIP public web page. GIP information resources provide information such as historical information on resolved GIs, current status of the open GIs, policy documents, program procedures, GIP annual and quarterly reports and the process to contact GIP and propose a GI This paper provides an overview of the GIP and several examples of safety improvements resulting from the resolution of GIs. In addition, the paper provides a brief discussion of a few recent GIs to illustrate how the program functions to improve safety. (authors)

  6. Enhanced surveillance program FY97 accomplishments. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    Mauzy, A. [ed.; Laake, B. [comp.

    1997-10-01

    This annual report is one volume of the Enhanced Surveillance Program (ESP) FY97 Accomplishments. The complete accomplishments report consists of 11 volumes. Volume 1 includes an ESP overview and a summary of selected unclassified FY97 program highlights. Volume 1 specifically targets a general audience, reflecting about half of the tasks conducted in FY97 and emphasizing key program accomplishments and contributions. The remaining volumes of the accomplishments report are classified, organized by program focus area, and present in technical detail the progress achieved in each of the 104 FY97 program tasks. Focus areas are as follows: pits; high explosives; organics; dynamics; diagnostics; systems; secondaries; nonnuclear materials; nonnuclear components; and Surveillance Test Program upgrades.

  7. Development and implementation of a hospital-based patient safety program

    International Nuclear Information System (INIS)

    Frush, Karen S.; Alton, Michael; Frush, Donald P.

    2006-01-01

    Evidence from numerous studies indicates that large numbers of patients are harmed by medical errors while receiving health-care services in the United States today. The 1999 Institute of Medicine report on medical errors recommended that hospitals and health-care agencies ''establish safety programs to act as a catalyst for the development of a culture of safety'' [1]. In this article, we describe one approach to successful implementation of a hospital-based patient safety program. Although our experience at Duke University Health System will be used as an example, the needs, principles, and solutions can apply to a variety of other health-care practices. Key components include the development of safety teams, provision of tools that teams can use to support an environment of safety, and ongoing program modification to meet patient and staff needs and respond to changing priorities. By moving patient safety to the forefront of all that we do as health-care providers, we can continue to improve our delivery of health care to children and adults alike. This improvement is fostered when we enhance the culture of safety, develop a constant awareness of the possibility of human and system errors in the delivery of care, and establish additional safeguards to intercept medical errors in order to prevent harm to patients. (orig.)

  8. 42 CFR 9.10 - Occupational Health and Safety Program (OHSP) and biosafety requirements.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Occupational Health and Safety Program (OHSP) and... SANCTUARY SYSTEM § 9.10 Occupational Health and Safety Program (OHSP) and biosafety requirements. (a) How are employee Occupational Health and Safety Program risks and concerns addressed? The sanctuary shall...

  9. FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2010 : [analysis brief].

    Science.gov (United States)

    2014-11-01

    Two of the Federal Motor Carrier Safety Administrations (FMCSAs) key safety programs are the Roadside Inspection and Traffic Enforcement programs. The Roadside Inspection program consists of roadside inspections performed by qualified safety in...

  10. Management Oversight and Risk Tree (MORT): a new system safety program

    International Nuclear Information System (INIS)

    Clark, J.L.

    Experiences of Aerojet Nuclear Company (ANC), in the development and implementation of a system safety program for ANC and for the Energy Research and Development Administration (ERDA) are discussed. Aerojet Nuclear is the prime operating contractor for ERDA, formerly AEC, at the Idaho National Engineering Laboratory. The ERDA sponsored ''MORT'' system safety program is described along with the process whereby formal system safety methods are incorporated into a stable organization. Specifically, a discussion is given of initial development of MORT; pilot program trials conducted at ANC; implementation methodology; and reaction of the ANC organization. (auth)

  11. Progress in the U.S. department of energy sponsored in-depth safety assessments of VVER and RBMK reactors

    International Nuclear Information System (INIS)

    Binder, J.L.; Petri, M.C.; Pasedag, W.F.

    2001-01-01

    Since the disastrous accident at Chernobyl Nuclear Power Plant Unit 4 in 1986, there has been international recognition of the safety concerns posed by the operation of 67 Soviet-designed commercial nuclear reactors. These reactors are operated in eight countries from the former Soviet Union and its former satellite states in Central and Eastern Europe. The majority of these plants are in the Russian Federation (30 units) and Ukraine (14 units). New plants are in various stages of construction. U.S. support to improve the safety of Soviet-designed reactors over the past decade has been intended to enhance operational safety, provide for risk-reduction measures, and enhance regulatory capability. The U.S. approach to improving the safety of Soviet-designed reactors has matured into a large multi-year program known as the Soviet-Designed Reactor Safety Program that is managed by the U.S. Department of Energy (US DOE). The mission of the program is to implement a self-sustaining nuclear safety improvement program that would lead to internationally accepted safety practices at the plants. Those practices would create a safety culture that would be reflected in the operation, regulation, and professional attitudes of the designers, operators, and regulators of the nuclear facilities. A key component of this larger program has been the Plant Safety Evaluation Program, which supports in-depth safety assessments of VVER and RBMK plants. (author)

  12. FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model FY 2012, [analysis brief].

    Science.gov (United States)

    2016-02-01

    Roadside Inspection and Traffic Enforcement are two of : the Federal Motor Carrier Safety Administrations : (FMCSAs) key safety programs. The Roadside : Inspection Program consists of roadside inspections : performed by qualified safety inspect...

  13. Radiation safety program in a high dose rate brachytherapy facility

    International Nuclear Information System (INIS)

    Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

    2001-01-01

    The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)

  14. FMCSA safety program effectiveness measurement : roadside intervention effectiveness model FY 2011 : [analysis brief].

    Science.gov (United States)

    2015-06-01

    Roadside Inspection and Traffic Enforcement are two of the Federal Motor Carrier Safety Administrations (FMCSAs) key safety programs. The Roadside Inspection program consists of roadside inspections performed by qualified safety inspectors. The...

  15. Occupational Safety and Health Program at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    L. M. Calderon

    1999-01-01

    The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment

  16. The effectiveness of a bicycle safety program for improving safety-related knowledge and behavior in young elementary students.

    Science.gov (United States)

    McLaughlin, Karen A; Glang, Ann

    2010-05-01

    The purpose of this study was to evaluate the "Bike Smart" program, an eHealth software program that teaches bicycle safety behaviors to young children. Participants were 206 elementary students in grades kindergarten to 3. A random control design was employed to evaluate the program, with students assigned to either the treatment condition (Bike Smart) or the control condition (a video on childhood safety). Outcome measures included computer-based knowledge items (safety rules, helmet placement, hazard discrimination) and a behavioral measure of helmet placement. Results demonstrated that regardless of gender, cohort, and grade the participants in the treatment group showed greater gains than control participants in both the computer-presented knowledge items (p > .01) and the observational helmet measure (p > .05). Findings suggest that the Bike Smart program can be a low cost, effective component of safety training packages that include both skills-based and experiential training.

  17. Findings From the National Machine Guarding Program-A Small Business Intervention: Machine Safety.

    Science.gov (United States)

    Parker, David L; Yamin, Samuel C; Xi, Min; Brosseau, Lisa M; Gordon, Robert; Most, Ivan G; Stanley, Rodney

    2016-09-01

    The purpose of this nationwide intervention was to improve machine safety in small metal fabrication businesses (3 to 150 employees). The failure to implement machine safety programs related to guarding and lockout/tagout (LOTO) are frequent causes of Occupational Safety and Health Administration (OSHA) citations and may result in serious traumatic injury. Insurance safety consultants conducted a standardized evaluation of machine guarding, safety programs, and LOTO. Businesses received a baseline evaluation, two intervention visits, and a 12-month follow-up evaluation. The intervention was completed by 160 businesses. Adding a safety committee was associated with a 10% point increase in business-level machine scores (P increase in LOTO program scores (P < 0.0001). Insurance safety consultants proved effective at disseminating a machine safety and LOTO intervention via management-employee safety committees.

  18. Buff book 1: status summary report, water reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    This Management Report, to provide information for monitoring and controlling the progress of LWR Safety Research Projects Associated with the Office of Nuclear Regulatory Research and other agencies and organizations engaged in nuclear safety research. It utilizes data pertaining to project schedules, cost, and status which have been integrated into a network-based management information system, The purpose of this publication is to provide a vehicle for review of the current status and overall progress of the safety Research Program from a managerial point of view

  19. Status and progress of the RERTR program in the year 2003

    International Nuclear Information System (INIS)

    Travelli, Armando

    2003-01-01

    One of the most important events affecting the RERTR program during the past year was the decision by the U.S. Department of Energy to request the U.S. Congress to significantly increase RERTR program funding. This decision was prompted, at least in part, by the terrible events of September 11, 2001, and by a high-level U.S./Russian Joint Expert Group recommendation to immediately accelerate RERTR program activities in both countries, with the goal of converting all the world's research reactors to low-enriched fuel at the earliest possible time, and including both Soviet-designed and United States-designed research reactors. The U.S. Congress is expected to approve this request very soon, and the RERTR program has prepared itself well for the intense activities that the 'Accelerated RERTR Program' will require. Promising results have been obtained in the development of a fabrication process for monolithic LEU U-Mo fuel. Most existing and future research reactors could be converted to LEU with this fuel, which has a uranium density between 15.4 and 16.4 g/cm 3 and yielded promising irradiation results in 2002. The most promising method hinges on producing the monolithic meat by cold-rolling a thin ingot produced by casting. The aluminum clad and the meat are bonded by friction stir welding and the cladding surface is finished by a light cold roll. This method can be applied to the production of miniplates and appears to be extendable to the production of full-size plates, possibly with intermediate anneals. Other methods planned for investigation include high temperature bonding and hot isostatic pressing. The progress achieved within the Russian RERTR program, both for the traditional tube-type elements and for the new 'universal' LEU U-Mo pin-type elements, promises to enable soon the conversion of many Russian-designed research and test reactors. Irradiation testing of both fuel types with LEU U-Mo dispersion fuels has begun. Detailed studies are in progress to

  20. Report on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1978-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power-plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of advanced reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT which will appear in the near future. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC and the OECD. (orig./HP) [de

  1. Reports on research projects sponsored by the Federal Minister for Research and Technology in the field of reactor safety

    International Nuclear Information System (INIS)

    1979-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC European Communities and the OECD. (orig./HP) [de

  2. The Impact of a Patient Safety Program on Medical Error Reporting

    Science.gov (United States)

    2005-05-01

    307 The Impact of a Patient Safety Program on Medical Error Reporting Donald R. Woolever Abstract Background: In response to the occurrence of...a sentinel event—a medical error with serious consequences—Eglin U.S. Air Force (USAF) Regional Hospital developed and implemented a patient safety...communication, teamwork, and reporting. Objective: To determine the impact of a patient safety program on patterns of medical error reporting. Methods: This

  3. Baseline Gas Turbine Development Program. Fourteenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F W; Wagner, C E

    1976-04-30

    Progress is reported for a Baseline Gas Turbine Development Program sponsored by the Heat Engine Systems Branch, Division of Transportation Energy Conservation (TEC) of the Energy Research and Development Administration (ERDA). Structurally, this program is made up of three parts: (1) documentation of the existing automotive gas turbine state-of-the-art; (2) conduction of an extensive component improvement program; and (3) utilization of the improvements in the design, and building of an Upgraded Engine capable of demonstrating program goals.

  4. Fusion reactor safety studies, FY 1977

    International Nuclear Information System (INIS)

    Darby, J.B. Jr.

    1978-04-01

    This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

  5. Space Power Program Semiannual Progress Report for period ending June 30, 1963

    Energy Technology Data Exchange (ETDEWEB)

    Miller, A. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    1963-10-11

    This is a report of progress on the Oak Ridge National Laboratory's research and development program on nuclear power plants for electrical power production in space vehicles. The work is carried out under AEG Reactor Experiments, Fuels, and Materials, and Reactor Component programs. Research and development work is under way on the stainless steel boiling-potassium reactor and the Medium Power Reactor Experiment, boiling alkali metal heat transfer, high-temperature and refractory alloys, fuel material, and space reactor shielding, particularly in connection with SNAP 2, 8, 10, and 50. Many of these OREL efforts are directed toward the development of a specific type of power plant, but they also furnish a significant contribution of scientific and engineering information needed in other programs on advanced SNAP systems. Progress on research and development directly related to the Medium Power Reactor Experiment (MPRE) is presented mostly in Part I of this report. Progress on the MPRE will, in the future, be reported on a quarterly basis. The form of the reporting will alternate from MPRE Quarterly Progress Reports to Space Power Semiannual Progress Reports.

  6. Commercial Crew Program Crew Safety Strategy

    Science.gov (United States)

    Vassberg, Nathan; Stover, Billy

    2015-01-01

    The purpose of this presentation is to explain to our international partners (ESA and JAXA) how NASA is implementing crew safety onto our commercial partners under the Commercial Crew Program. It will show them the overall strategy of 1) how crew safety boundaries have been established; 2) how Human Rating requirements have been flown down into programmatic requirements and over into contracts and partner requirements; 3) how CCP SMA has assessed CCP Certification and CoFR strategies against Shuttle baselines; 4) Discuss how Risk Based Assessment (RBA) and Shared Assurance is used to accomplish these strategies.

  7. 78 FR 14912 - International Aviation Safety Assessment (IASA) Program Change

    Science.gov (United States)

    2013-03-08

    ... Aviation Safety Assessment (IASA) Program Change AGENCY: Federal Aviation Administration (FAA), DOT. ACTION..., into the U.S., or codeshare with a U.S. air carrier, complies with international aviation safety... subject to that country's aviation safety oversight can serve the United States using its own aircraft or...

  8. Report on the research projects in the field of reactor safety sponsored by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1978-09-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F -Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work, The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC Communities and the OECD. (orig./HP) 891 HP [de

  9. Ferrocyanide Safety Program cyanide speciation studies. Final report

    International Nuclear Information System (INIS)

    Bryan, S.A.; Pool, K.H.; Bryan, S.L.

    1995-07-01

    This report summarizes Pacific Northwest Laboratory's fiscal year (FY) 1995 progress toward developing and implementing methods to identify and quantify cyanide species in ferrocyanide tank waste. This work was conducted for Westinghouse Hanfbrd Company's (WHC's) Ferrocyanide Safety Program. Currently, there are 18 high-level waste storage tanks at the US Department of Energy's Hanford Site that are on a Ferrocyanide Tank Watchlist because they contain an estimated 1000 g-moles or more of precipitated ferrocyanide. In the presence of oxidizing material such as sodium nitrate or nitrite, ferrocyanide can be made to react exothermally by heating it to high temperatures or by applying an electrical spark of sufficient energy (Cady 1993). However, fuel, oxidizers, and temperature are all important parameters. If fuel, oxidizers, or high temperatures (initiators) are not present in sufficient amounts, then a runaway or propagating reaction cannot occur. To bound the safety concern, methods are needed to definitively measure and quantitate ferrocyanide concentration present within the actual waste. The target analyte concentration for cyanide in waste is approximately 0.1 to 15 wt % (as cyanide) in the original undiluted sample. After dissolution of the original sample and appropriate dilutions, the concentration range of interest in the analytical solutions can vary between 0.001 to 0.1 wt % (as cyanide). In FY 1992, 1993, and 1994, two solution (wet) methods were developed based on Fourier transform infrared (FTIR) spectroscopy and ion chromatography (IC); these methods were chosen for further development activities. The results of these activities are described

  10. 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

  11. A progressive methodology for seismic safety evaluation of gravity dams

    International Nuclear Information System (INIS)

    Ghrib, F.; Leger, P.; Tinawi, R.; Lupien, R.; Veilleux, M.

    1995-01-01

    A progressive methodology for the seismic safety evaluation of existing concrete gravity dams was described. The methodology was based on five structural analysis levels with increasing complexity to represent inertia forces, dam-foundation and dam-interaction mechanisms, as well as concrete cracking. The five levels were (1) preliminary screening, (2) pseudo-static method, (3) pseudo-dynamic method, (4) linear time history analysis, and (5) non-linear history analysis. The first four levels of analysis were applied for the seismic safety evaluation of Paugan gravity dam (Quebec). Results showed that internal forces from pseudo-dynamic, response spectra and transient finite element analyses could be used to interpret the dynamic stability of dams from familiar strength-based criteria. However, as soon as the base was cracked, the seismically induced forces were modified, and level IV analyses proved more suitable to handle rationally these complexities. 8 refs., 7 figs., 1 tab

  12. Program of nuclear criticality safety experiment at JAERI

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Ohnishi, Nobuaki

    1983-11-01

    JAERI is promoting the nuclear criticality safety research program, in which a new facility for criticality safety experiments (Criticality Safety Experimental Facility : CSEF) is to be built for the experiments with solution fuel. One of the experimental researches is to measure, collect and evaluate the experimental data needed for evaluation of criticality safety of the nuclear fuel cycle facilities. Another research area is a study of the phenomena themselves which are incidental to postulated critical accidents. Investigation of the scale and characteristics of the influences caused by the accident is also included in this research. The result of the conceptual design of CSEF is summarized in this report. (author)

  13. Workplace safety and health programs, practices, and conditions in auto collision repair businesses.

    Science.gov (United States)

    Brosseau, L M; Bejan, A; Parker, D L; Skan, M; Xi, M

    2014-01-01

    This article describes the results of a pre-intervention safety assessment conducted in 49 auto collision repair businesses and owners' commitments to specific improvements. A 92-item standardized audit tool employed interviews, record reviews, and observations to assess safety and health programs, training, and workplace conditions. Owners were asked to improve at least one-third of incorrect, deficient, or missing (not in compliance with regulations or not meeting best practice) items, of which a majority were critical or highly important for ensuring workplace safety. Two-thirds of all items were present, with the highest fraction related to electrical safety, machine safety, and lockout/tagout. One-half of shops did not have written safety programs and had not conducted recent training. Many had deficiencies in respiratory protection programs and practices. Thirteen businesses with a current or past relationship with a safety consultant had a significantly higher fraction of correct items, in particular related to safety programs, up-to-date training, paint booth and mixing room conditions, electrical safety, and respiratory protection. Owners selected an average of 58% of recommended improvements; they were most likely to select items related to employee Right-to-Know training, emergency exits, fire extinguishers, and respiratory protection. They were least likely to say they would improve written safety programs, stop routine spraying outside the booth, or provide adequate fire protection for spray areas outside the booth. These baseline results suggest that it may be possible to bring about workplace improvements using targeted assistance from occupational health and safety professionals.

  14. Sanitation & Safety for Child Feeding Programs.

    Science.gov (United States)

    Florida State Dept. of Health and Rehabilitative Services, Tallahassee.

    In the interest of promoting good health, sanitation, and safety practices in the operation of child feeding programs, this bulletin discusses practices in personal grooming and wearing apparel; the purchasing, storage, handling, and serving of food; sanitizing equipment and utensils; procedures to follow in case of a food poisoning outbreak; some…

  15. Safety Critical Java for Robotics Programming

    DEFF Research Database (Denmark)

    Thomsen, Bent; Luckow, Kasper Søe; Bøgholm, Thomas

    2015-01-01

    This paper introduces Safety Critical Java (SCJ) and argues its readiness for robotics programming. We give an overview of the work done at Aalborg University and elsewhere on SCJl, some of its implementations in the form of the JOP, FijiVM and HVM and some of the tools, especially WCA, Teta...

  16. 2009 Annual Progress Report: DOE Hydrogen Program, November 2009 (Book)

    Energy Technology Data Exchange (ETDEWEB)

    2009-11-01

    This report summarizes the hydrogen and fuel cell R&D activities and accomplishments of the DOE Hydrogen Program for FY2009. It covers the program areas of hydrogen production and delivery; fuel cells; manufacturing; technology validation; safety, codes and standards; education; and systems analysis.

  17. Regulation of Tumor Progression by Programmed Necrosis

    Directory of Open Access Journals (Sweden)

    Su Yeon Lee

    2018-01-01

    Full Text Available Rapidly growing malignant tumors frequently encounter hypoxia and nutrient (e.g., glucose deprivation, which occurs because of insufficient blood supply. This results in necrotic cell death in the core region of solid tumors. Necrotic cells release their cellular cytoplasmic contents into the extracellular space, such as high mobility group box 1 (HMGB1, which is a nonhistone nuclear protein, but acts as a proinflammatory and tumor-promoting cytokine when released by necrotic cells. These released molecules recruit immune and inflammatory cells, which exert tumor-promoting activity by inducing angiogenesis, proliferation, and invasion. Development of a necrotic core in cancer patients is also associated with poor prognosis. Conventionally, necrosis has been thought of as an unregulated process, unlike programmed cell death processes like apoptosis and autophagy. Recently, necrosis has been recognized as a programmed cell death, encompassing processes such as oncosis, necroptosis, and others. Metabolic stress-induced necrosis and its regulatory mechanisms have been poorly investigated until recently. Snail and Dlx-2, EMT-inducing transcription factors, are responsible for metabolic stress-induced necrosis in tumors. Snail and Dlx-2 contribute to tumor progression by promoting necrosis and inducing EMT and oncogenic metabolism. Oncogenic metabolism has been shown to play a role(s in initiating necrosis. Here, we discuss the molecular mechanisms underlying metabolic stress-induced programmed necrosis that promote tumor progression and aggressiveness.

  18. NUMERICAL ANALYSIS AND EXPERIMENTAL INVESTIGATION OF DISK SPRING CONFIGURATIONS WITH REGARD TO LOAD CAPACITY OF SAFETY PROGRESSIVE GEARS

    Directory of Open Access Journals (Sweden)

    Paweł LONKWIC

    2016-09-01

    Full Text Available The paper investigates the effect of various disk spring package configurations on brake load of safety progressive gears. The numerical analysis is performed using the Abaqus/CAE software and the designed 3D models. The numerical results are then verified in experimental tests. The tests also examine the effect of lubrication on brake load of spring packages. In addition, the paper investigates the work conditions of safety progressive gears at emergency braking. The experimental results show agreement with the numerical results.

  19. National Machine Guarding Program: Part 2. Safety management in small metal fabrication enterprises.

    Science.gov (United States)

    Parker, David L; Yamin, Samuel C; Brosseau, Lisa M; Xi, Min; Gordon, Robert; Most, Ivan G; Stanley, Rodney

    2015-11-01

    Small manufacturing businesses often lack important safety programs. Many reasons have been set forth on why this has remained a persistent problem. The National Machine Guarding Program (NMGP) was a nationwide intervention conducted in partnership with two workers' compensation insurers. Insurance safety consultants collected baseline data in 221 business using a 33-question safety management audit. Audits were completed during an interview with the business owner or manager. Most measures of safety management improved with an increasing number of employees. This trend was particularly strong for lockout/tagout. However, size was only significant for businesses without a safety committee. Establishments with a safety committee scored higher (55% vs. 36%) on the safety management audit compared with those lacking a committee (P < 0.0001). Critical safety management programs were frequently absent. A safety committee appears to be a more important factor than business size in accounting for differences in outcome measures. © 2015 The Authors. American Journal of Industrial Medicine Published by Wiley Periodicals, Inc.

  20. Multidisciplinary training program to create new breed of radiation monitor: the health and safety technician

    International Nuclear Information System (INIS)

    Vance, W.F.

    1979-01-01

    A multidiscipline training program established to create a new monitor, theHealth and Safety Technician, is described. The training program includes instruction in fire safety, explosives safety, industrial hygiene, industrial safety, health physics, and general safety practices

  1. Environment Health & Safety Research Program. Organization and 1979-1980 Publications

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-01

    This document was prepared to assist readers in understanding the organization of Pacific Northwest Laboratory, and the organization and functions of the Environment, Health and Safety Research Program Office. Telephone numbers of the principal management staff are provided. Also included is a list of 1979 and 1980 publications reporting on work performed in the Environment, Health and Safety Research Program, as well as a list of papers submitted for publication.

  2. Fusion-Reactor-Safety Research Program. Annual report, Fiscal Year 1981

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1982-07-01

    The report contains four sections: Outside Contracts includes the continuation of the General Atomic Co. low-activation materials safety study, water-cooled transport activation products study by Pacific Northwest Laboratory (PNL), studies of superconducting magnet safety conducted by Argonne National Laboratory (ANL) coupled with a new experimental superconducting magnet study program by Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety methodology work by MIT, portions of papers on lithium safety studies conducted at Hanford Engineering Development Laboratory (HEDL), and a new program to study tritium gas conversion to tritiated water at Oak Ridge National Laboratory (ORNL). The section EG and G idaho, Inc., Activities at INEL includes adaptations of papers of ongoing work in transient code development, tritium systems risk assessment, heat transfer activities, and a summary of a workshop on safety in design. A List of Publications and Proposed FY-82 Activities are also presented

  3. NASA's aviation safety research and technology program

    Science.gov (United States)

    Fichtl, G. H.

    1977-01-01

    Aviation safety is challenged by the practical necessity of compromising inherent factors of design, environment, and operation. If accidents are to be avoided these factors must be controlled to a degree not often required by other transport modes. The operational problems which challenge safety seem to occur most often in the interfaces within and between the design, the environment, and operations where mismatches occur due to ignorance or lack of sufficient understanding of these interactions. Under this report the following topics are summarized: (1) The nature of operating problems, (2) NASA aviation safety research, (3) clear air turbulence characterization and prediction, (4) CAT detection, (5) Measurement of Atmospheric Turbulence (MAT) Program, (6) Lightning, (7) Thunderstorm gust fronts, (8) Aircraft ground operating problems, (9) Aircraft fire technology, (10) Crashworthiness research, (11) Aircraft wake vortex hazard research, and (12) Aviation safety reporting system.

  4. Reports on research projects in the field of reactor safety sponsored by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1978-09-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), der Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC Communities and the OECD. (orig./HP) 891 HP [de

  5. Reports on research projects in the field of reactor safety sponsored by the Federal Ministry for research and technology

    International Nuclear Information System (INIS)

    1979-09-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power-plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT in the near future. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC Communities and the OECD. (orig.) [de

  6. Progress of nuclear safety research. 2001

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-10-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

  7. An evaluation of an airline cabin safety education program for elementary school children.

    Science.gov (United States)

    Liao, Meng-Yuan

    2014-04-01

    The knowledge, attitude, and behavior intentions of elementary school students about airline cabin safety before and after they took a specially designed safety education course were examined. A safety education program was designed for school-age children based on the cabin safety briefings airlines given to their passengers, as well as on lessons learned from emergency evacuations. The course is presented in three modes: a lecture, a demonstration, and then a film. A two-step survey was used for this empirical study: an illustrated multiple-choice questionnaire before the program, and, upon completion, the same questionnaire to assess its effectiveness. Before the program, there were significant differences in knowledge and attitude based on school locations and the frequency that students had traveled by air. After the course, students showed significant improvement in safety knowledge, attitude, and their behavior intention toward safety. Demographic factors, such as gender and grade, also affected the effectiveness of safety education. The study also showed that having the instructor directly interact with students by lecturing is far more effective than presenting the information using only video media. A long-term evaluation, the effectiveness of the program, using TV or video accessible on the Internet to deliver a cabin safety program, and a control group to eliminate potential extraneous factors are suggested for future studies. Copyright © 2013 Elsevier Ltd. All rights reserved.

  8. Chronic beryllium disease prevention program; worker safety and health program. Final rule.

    Science.gov (United States)

    2006-02-09

    The Department of Energy (DOE) is today publishing a final rule to implement the statutory mandate of section 3173 of the Bob Stump National Defense Authorization Act (NDAA) for Fiscal Year 2003 to establish worker safety and health regulations to govern contractor activities at DOE sites. This program codifies and enhances the worker protection program in operation when the NDAA was enacted.

  9. Public safety and sour gas quarterly progress report October - December 2002

    Energy Technology Data Exchange (ETDEWEB)

    Sikora, V.; Lillo, H.; Craig, M.; Neilson, G.

    2003-01-01

    This third quarterly progress report for the business year 2002-2003 on the Alberta Energy and Utilities Board (EUB) Public Safety and Sour Gas initiative covers projects based on the 87 recommendations made by the Provincial Advisory Committee on Public Safety and Sour Gas (Advisory Committee) in December 2000. As of December 2002, work has been completed on 16 recommendations and is proceeding on 50 recommendations. This report includes several tables indicating the status of recommendations as either complete or ongoing. The recommendation categories include: (1) sour gas development, planning and approval, (2) sour gas operations, (3) emergency preparedness, and (4) information, communication and consultation. The report also summarizes the health effects and sour gas research. Recommendations completed as of December 2002 include: plant proliferation; pre-license review of critical well license applications; license application training/certification information requirement; increase sour gas inspections; increase inspections of new and noncompliant operators; implement 100 per cent inspection rate for critical wells near people; response to sour gas complaints; enhance EUB capability to monitor for complaint response/compliance; complaint/incident response program for Aboriginal communities; interim policy on ERP review and reduced EPZs; infrastructure and resources for Aboriginal community ERP; field staff in industry-landowner discussions; EUB involvement in mediation of application issues; and, timely and meaningful public consultation for First Nations and Metis. Alberta Health and Wellness is currently evaluating the health effects of H{sub 2}S and SO{sub 2} and the work is near completion. Other ongoing work includes the development of a draft protocol to address the involvement of regional health authorities (RHAs), the early involvement of RHAs and other local government bodies, and a process for communication between the EUB field staff and

  10. Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report

    International Nuclear Information System (INIS)

    1998-01-01

    This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV's) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG ampersand G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin). Sandia / Sandia Corporation (Lockheed-Martin)

  11. Evaluating the effectiveness of a logger safety training program.

    Science.gov (United States)

    Bell, Jennifer L; Grushecky, Shawn T

    2006-01-01

    Logger safety training programs are rarely, if ever, evaluated as to their effectiveness in reducing injuries. Workers' compensation claim rates were used to evaluate the effectiveness of a logger safety training program, the West Virginia Loggers' Safety Initiative (LSI). There was no claim rate decline detected in the majority (67%) of companies that participated in all 4 years of the LSI. Furthermore, their rate did not differ from the rest of the WV logging industry that did not participate in the LSI. Worker turnover was significantly related to claim rates; companies with higher turnover of employees had higher claim rates. Companies using feller bunchers to harvest trees at least part of the time had a significantly lower claim rate than companies not using them. Companies that had more inspections per year had lower claim rates. High injury rates persist even in companies that receive safety training; high employee turnover may affect the efficacy of training programs. The logging industry should be encouraged to facilitate the mechanization of logging tasks, to address barriers to employee retention, and to increase the number of in-the-field performance monitoring inspections. Impact on industry There are many states whose logger safety programs include only about 4-8 hours of safe work practices training. These states may look to West Virginia's expanded training program (the LSI) as a model for their own programs. However, the LSI training may not be reaching loggers due to the delay in administering training to new employees and high levels of employee turnover. Regardless of training status, loggers' claim rates decline significantly the longer they work for a company. It may be that high injury rates in the state of West Virginia would be best addressed by finding ways to encourage and facilitate companies to become more mechanized in their harvesting practices, and to increase employee tenure. Increasing the number of yearly performance inspections

  12. The RERTR program status and progress

    International Nuclear Information System (INIS)

    Travelli, A.

    2004-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1995 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 994 in collaboration with its many international partners. The revelation that Iraq was on the verge of developing a nuclear weapon at the time of the Gulf War, and that it was planning to do so by extracting HEU from the fuel of its research reactors, has given new impetus and urgency to the RERTR commitment of eliminating HEU use in research and test reactors worldwide. The Draft Environmental Impact Statement on the DOE policy for managing spent nuclear fuels from foreign research reactors was published on schedule. A Record of Decision is due in December 1995. After much legal debate, a first shipment of 153 urgent-relief elements took place, and another 151 elements became eligible for shipment. Development of advanced LEU research reactor fuels is scheduled to begin in October 1995, after DOE funding is received. Funding for equipment needed to begin this activity was provided by the US Department of State, and procurement of the equipment is in progress. The Russian RERTR program, which aims to develop and demonstrate within the next five years the technical means needed to convert Russian-supplied research reactors to LEU fuels, is now in operation. A Statement of Intent was signed by high US and Chinese officials, endorsing cooperative activities between the RERTR program and Chinese laboratories involved in similar activities. Joint studies of LEU technical feasibility were completed for the SAFARI-1 reactor in South Africa and for the ANS reactor in the US. The ANS project was later canceled for budgetary and nonproliferation reasons. A new study has been initiated for the FRM-II reactor in Germany. Significant progress was made on several aspects of producing 99 Mo from fission targets utilizing LEU instead of

  13. Trends in traffic fatalities in Mexico: examining progress on the decade of action for road safety 2011-2020.

    Science.gov (United States)

    Cervantes-Trejo, Arturo; Leenen, Iwin; Fabila-Carrasco, John Stewart; Rojas-Vargas, Roy

    2016-11-01

    We explore demographic, temporal and geographic patterns of 256,588 road traffic fatalities from 1998 to 2013 in Mexico, in context of UN´s decade of action for road safety 2010-2020 (DARS). Combined traffic mortality data and population counts were analyzed using mixed-effects logistic regression, distinguishing sex-age groups, vulnerable and protected road users, and municipal size. Rapid growth from 1998 to 2008 in traffic mortality rates has been reversed since 2009. Most deaths averted are among young male protected road users (reduction of 0.95 fatalities per 100,000 per year in males 12-49). In spite of a steady decrease over the full study period, mortality rates remain high in vulnerable road users over 50, with a high mortality rate of 26 per 100,000 males over 75 years in 2013. Progress on the reduction of deaths advances in Mexico, in line with DARS targets. National road safety efforts require strengthening. Initiatives should target vulnerable road users, specifically adults >50 years in urban areas. Strengthening of drink driving programs aimed at young drivers/occupants is promising.

  14. Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    This progress report is compiled from major contributions from three programs: (1) the Advanced Fuel Recycle Program at ORNL; (2) the Converter Fuel Reprocessing Program at Savannah River Laboratory; and (3) the reprocessing components of the HTGR Fuel Recycle Program, primarily at General Atomic and ORNL. The coverage is generally overview in nature; experimental details and data are limited.

  15. OPG - Waterways public safety program

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, Tony [Ontario Power Generation (Canada)

    2011-07-01

    Ontario Power Generation (OPG) operates 65 hydroelectric generating stations in Ontario and has 241 dams. Security around dams is an important matter to minimize exposure of the public to hazards and to prevent an uncontrolled release of water and also to be prepared in case of failure. The purpose of this presentation is to describe the waterways public safety program developed by OPG in association with the Ontario Waterpower Associattion, the Canadian Dam Association and the Ontario Ministry of Natural Resoruces. This program takes a managed system approach with continuous review to address specific and changing conditions of sites. Policies, accountability mechanisms and assessments are first planned, and then implemented, every day functioning is monitored, corrective actions are developed on the basis of issues and reports are compiled for planning of new improvements. This research program provided OPG with new methods for preventing accidents more efficiently.

  16. THE SCHOOL HEALTH AND SAFETY PROGRAM.

    Science.gov (United States)

    1963

    INVOLVING INDIVIDUALS AS WELL AS ORGANIZATIONS, THE PROGRAM AIMED AT THE OPTIMUM HEALTH OF ALL CHILDREN, AND IMPROVEMENT OF HEALTH AND SAFETY STANDARDS WITHIN THE COMMUNITY. EACH OF THE CHILDREN WAS URGED TO HAVE A SUCCESSFUL VACCINATION FOR SMALL POX, THE DPT SERIES AND BOOSTER, THE POLIO SERIES, AND CORRECTIONS OF ALL DENTAL DEFECTS AND…

  17. Squale: evaluation criteria of functioning safety

    International Nuclear Information System (INIS)

    Deswarte, Y.; Kaaniche, M.; Benoit, P.

    1998-05-01

    The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.)

  18. The USERDA transport R and D program for environment and safety

    International Nuclear Information System (INIS)

    Sisler, J.A.

    1976-01-01

    This paper describes the U.S. Energy Research and Development Administration's (ERDA) transportation environment and safety research and development program for energy fuels and wastes, including background, current activities, and future plans. It will serve as an overview and integrating factor for the several related technical papers to be presented at this meeting which will enlarge on the detail of specific projects. The transportation R and D program provides for the environmental and safety review of transport systems and procedures; standards development; and package, vehicle, and systems testing for nuclear materials transport. A primary output of the program is the collection, processing, and dissemination of transport environment and safety data, shipment statistics, and technical information. Special transport projects which do not easily fit elsewhere in ERDA are usually done as a part of this program. (author)

  19. Human resource development program for nuclear safety and security in Tokyo Institute of Technology

    International Nuclear Information System (INIS)

    Han, Chi Young; Sagara, Hiroshi; Nagasaka, Hideo

    2014-01-01

    The Academy for Global Nuclear Safety and Security Agent was established at Tokyo Institute of Technology in 2011, to develop global nuclear human resources in the field of 3S (Safety, Security, and Safeguards) as a Program for Leading Graduate Schools supported by MEXT (Ministry of Education, Culture, Sports, Science and Technology). New courses of nuclear safety and security were developed in addition to the existing nuclear engineering program; 1) Environmental Dynamics of Radioactive Nuclides; Numerical simulation of the environmental dispersion of radioactive materials released from hypothetical nuclear accidents and evaluation of the public exposure are performed, by using a computer-based emergency response system, to have students predict the environmental dispersion of radionuclides and radiological consequence by nuclear accidents. 2) Measurement of Environmental Radiation; Students acquire hands-on experiences measuring environmental radiation contamination caused by the nuclear accident in Fukushima with multiple types of radiation detectors. Environmental samples are collected and analyzed for isotope identification and its spatial distribution. 3) Simulation of Severe Nuclear Accidents; The evaluation results of Fukushima accident progression are discussed as well as typical sever accidents that threaten the integrity of reactor vessel. Students simulate BWR (Boiling Water Cooled Reactor) transients, design basis accidents, and severe accidents by using simulators. 4) Nuclear Security Training; Design of physical protection systems, its fundamental physics, and regulatory frameworks are covered and students gain the practical experiences by use of intrusion detection systems at JAEA (Japan Atomic Energy Agency), and by numerical simulation of hydro-dynamics of structure material and nuclear material criticality at the university. (author)

  20. Assessment of elementary school safety restraint programs.

    Science.gov (United States)

    1985-06-01

    The purpose of this research was to identify elementary school (K-6) safety belt : education programs in use in the United States, to review their development, and : to make administrative and impact assessments of their use in selected States. : Six...

  1. Waste Management Program. Technical progress report, Aporil-June 1983

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-02-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

  2. 77 FR 3784 - Recreational Boating Safety Projects, Programs and Activities Funded Under Provisions of the...

    Science.gov (United States)

    2012-01-25

    ... program which provides full marketing, media, public information, and program strategy support to the... Wear, Vessel Safety Check Program (VSC), Boating Safety Education Courses, Propeller Strike Avoidance, Carbon Monoxide Poisoning Awareness and Education, and other recreational boating safety issues on an as...

  3. Reports on the research projects in the field of nuclear safety sponsored by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1979-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The CRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT in the near future. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC Communities and the OECD.(orig./HP) [de

  4. Reports on the research projects in the field of nuclear safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1980-06-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-progress reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT, which will appear in the near future. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC and the OECD. (orig./HP) [de

  5. Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Corradini, M. L. [Univ. of Wisconsin, Madison, WI (United States); Peko, D. [US Dept. of Energy, Washington, DC (United States); Farmer, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Rempe, J. [Rempe and Associates LLC, Idaho Falls, ID (United States); Humrickhouse, P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); O' Brien, J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Robb, K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gauntt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Osborn, D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-06-01

    In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary

  6. Light Water Reactor Sustainability Program: Reactor Safety Technologies Pathway Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Corradini, M. L. [Univ. of Wisconsin, Madison, WI (United States)

    2015-06-01

    In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary

  7. Application of quality assurance program to safety related aging equipment or components

    International Nuclear Information System (INIS)

    Papaiya, N.C.

    1990-01-01

    This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements

  8. Clinton P. Anderson Meson Physics Facility and its operational safety program

    International Nuclear Information System (INIS)

    Putnam, T.M.

    1975-01-01

    The Clinton P. Anderson Meson Physics Facility (LAMPF) at the Los Alamos Scientific Laboratory consists of/ (1) a medium-energy, high-intensity linear proton accelerator; (2) experimental areas designed to support a multidisciplined program of research and practical applications; and (3) support facilities for accelerator operations and the experimental program. The high-intensity primary and secondary beams at LAMPF and the varied research program create many interesting and challenging problems for the Health Physics staff. A brief overview of LAMPF is presented, and the Operational Safety Program is discussed, with emphasis on the radiological safety and health physics aspects

  9. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  10. Thermonuclear generation program: risks and safety

    International Nuclear Information System (INIS)

    Goes, Alexandre Gromann de Araujo

    1999-01-01

    This work deals with the fundamental concepts of risk and safety related to nuclear power generation. In the first chapter, a general evaluation of the various systems for energy generation and their environmental impacts is made. Some definitions for safety and risk are suggested, based on the already existing regulatory processes and also on the current tendencies of risk management. Aspects regarding the safety culture are commented. The International Nuclear Event Scale (INES), a coherent and clear mechanism of communication between nuclear specialists and the general public, is analyzed. The second chapter examines the thermonuclear generation program in Brazil and the role of the National Nuclear Energy Commission. The third chapter presents national and international scenarios in terms of safety and risks, available policies and the main obstacles for future development of nuclear energy and nuclear engineering, and strategies are proposed. In the last chapter, comments about possible trends and recommendations related to practical risk management procedures, taking into account rational criteria for resources distribution and risk reduction are made, envisaging a closer integration between nuclear specialists and the society as a whole, thus decreasing the conflicts in a democratic decision-making process

  11. Progress of nuclear safety research-2004

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

    2005-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

  12. Work safety in the light of technological progress in mining. [Poland, accident and technology assessment for period 1950 to 1972

    Energy Technology Data Exchange (ETDEWEB)

    Stecko, R.

    1976-01-01

    This paper discusses positive and negative aspects of technological progress in black coal mining in Poland in the period from 1950 to 1972 on the basis of statistical data supplied by various institutions. Twenty three indexes characterizing both work safety and technological progress in underground coal mines are used. Equations of linear and non-linear even regression and equations of linear and non-linear multiple regression are derived on the basis of statistical records of 23 years. The equations are used to estimate indexes of work safety on the basis of technical progress indexes. It is suggested that from among 8 indexes characterizing work safety 4 are most useful and important: danger index, absenteeism index, frequency of underground fire index, and frequency of rock burst index. Analysis of the regression equation shows that technological progress in underground coal mines in Poland has caused a decrease in indexes describing: frequency of work accidents, frequency of underground fires, frequency of rock burst, and danger of underground work; and an increase in indexes characterizing: seriousness of work accidents, and absenteeism caused by work accidents. (84 refs.)

  13. Prioritization of R and D programs on probabilistic reactor safety

    International Nuclear Information System (INIS)

    Husseiny, A.A.

    1982-01-01

    An interactive computer code based on the multiattribute utility theory has been developed with graphic capabilities to use in selection of probabilistic reactor safety RandD programs. Utility values and proper graphic representation are made through lottery games on the computer terminal. The code is applied to prioritize a set of RandD programs on LWR safety based on attributes including regulatory issues, institutional issues and operation problems. The methodology is described here in detail with its applications. Some of the input includes statistical distributions and subjective judgments on institutional issues. The flexibility of the approach provides a tool for decision makers whether on individual or group level to assess LWR safety priorities and continuously update their strategies

  14. Waste Management Program. Technical progress report, July-December, 1984

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement

  15. Home safe home: Evaluation of a childhood home safety program.

    Science.gov (United States)

    Stewart, Tanya Charyk; Clark, Andrew; Gilliland, Jason; Miller, Michael R; Edwards, Jane; Haidar, Tania; Batey, Brandon; Vogt, Kelly N; Parry, Neil G; Fraser, Douglas D; Merritt, Neil

    2016-09-01

    The London Health Sciences Centre Home Safety Program (HSP) provides safety devices, education, a safety video, and home safety checklist to all first-time parents for the reduction of childhood home injuries. The objective of this study was to evaluate the HSP for the prevention of home injuries in children up to 2 years of age. A program evaluation was performed with follow-up survey, along with an interrupted time series analysis of emergency department (ED) visits for home injuries 5 years before (2007-2013) and 2 years after (2013-2015) implementation. Spatial analysis of ED visits was undertaken to assess differences in home injury rates by dissemination areas controlling differences in socioeconomic status (i.e., income, education, and lone-parent status) at the neighborhood level. A total of 3,458 first-time parents participated in the HSP (a 74% compliance rate). Of these, 20% (n = 696) of parents responded to our questionnaire, with 94% reporting the program to be useful (median, 6; interquartile range, 2 on a 7-point Likert scale) and 81% learning new strategies for preventing home injuries. The median age of the respondent's babies were 12 months (interquartile range, 1). The home safety check list was used by 87% of respondents to identify hazards in their home, with 95% taking action to minimize the risk. The time series analysis demonstrated a significant decline in ED visits for home injuries in toddlers younger than2 years of age after HSP implementation. The declines in ED visits for home injuries remained significant over and above each socioeconomic status covariate. Removing hazards, supervision, and installing safety devices are key facilitators in the reduction of home injuries. Parents found the HSP useful to identify hazards, learn new strategies, build confidence, and provide safety products. Initial finding suggests that the program is effective in reducing home injuries in children up to 2 years of age. Therapeutic/care management study

  16. 2016 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    Satyapal, Sunita [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2017-02-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  17. 2015 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    Popovich, Neil

    2015-12-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  18. 2012 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    2012-12-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  19. National machine guarding program: Part 2. Safety management in small metal fabrication enterprises

    Science.gov (United States)

    Yamin, Samuel C.; Brosseau, Lisa M.; Xi, Min; Gordon, Robert; Most, Ivan G.; Stanley, Rodney

    2015-01-01

    Background Small manufacturing businesses often lack important safety programs. Many reasons have been set forth on why this has remained a persistent problem. Methods The National Machine Guarding Program (NMGP) was a nationwide intervention conducted in partnership with two workers' compensation insurers. Insurance safety consultants collected baseline data in 221 business using a 33‐question safety management audit. Audits were completed during an interview with the business owner or manager. Results Most measures of safety management improved with an increasing number of employees. This trend was particularly strong for lockout/tagout. However, size was only significant for businesses without a safety committee. Establishments with a safety committee scored higher (55% vs. 36%) on the safety management audit compared with those lacking a committee (P management programs were frequently absent. A safety committee appears to be a more important factor than business size in accounting for differences in outcome measures. Am. J. Ind. Med. 58:1184–1193, 2015. © 2015 The Authors. American Journal of Industrial Medicine Published by Wiley Periodicals, Inc. PMID:26345591

  20. Annual progress report 1980

    International Nuclear Information System (INIS)

    1981-01-01

    The technical support activities of the IPSN to competent administrations in 1980 has been marked: namely by the authorizations of divergence for 9 units EdF-PWR of 900 MW, the authorization project of creation and extension of reprocessing plant of COGEMA at the Hague UP 2 -800 and the authorization of starting up of the third unit of production of the EURODIF enrichment plant at Tricastin. On the other hand, IPSN has participated at the elaboration of a certain number of legislative and regulation texts relative to the control of nuclear matter, to radioprotection standards and to criteria of safety. For the safety of breeder, the test made at CABRI pile, in the international research program has given confirmation of the validity of theoretical models used in accidents calculations, hypothetical accidents which has allowed to reactualize safety criteria which have to be used for the development of this type of reactor. In worker radioprotection the results obtained in laboratory on the effect of radon, the progress made in personal dosimetry and the action of radioprotection undertaken in uranium mines constitutes a coherent effort. The deep drilling in granit (1000 m) and the experimental associated program which has finished the indispensable scientific data for the future policy in matter of storage of radioactives wastes. IPSN has contributed to progress made in the rules of exploitation of reactors, in the definition of wastes containment -specially at the output of reprocessing plant- in handling machines in hazardeous areas and in the study of environment [fr

  1. General aviation crash safety program at Langley Research Center

    Science.gov (United States)

    Thomson, R. G.

    1976-01-01

    The purpose of the crash safety program is to support development of the technology to define and demonstrate new structural concepts for improved crash safety and occupant survivability in general aviation aircraft. The program involves three basic areas of research: full-scale crash simulation testing, nonlinear structural analyses necessary to predict failure modes and collapse mechanisms of the vehicle, and evaluation of energy absorption concepts for specific component design. Both analytical and experimental methods are being used to develop expertise in these areas. Analyses include both simplified procedures for estimating energy absorption capabilities and more complex computer programs for analysis of general airframe response. Full-scale tests of typical structures as well as tests on structural components are being used to verify the analyses and to demonstrate improved design concepts.

  2. An Overview of the NASA Aviation Safety Program (AVSP) Systemwide Accident Prevention (SWAP) Human Performance Modeling (HPM) Element

    Science.gov (United States)

    Foyle, David C.; Goodman, Allen; Hooley, Becky L.

    2003-01-01

    An overview is provided of the Human Performance Modeling (HPM) element within the NASA Aviation Safety Program (AvSP). Two separate model development tracks for performance modeling of real-world aviation environments are described: the first focuses on the advancement of cognitive modeling tools for system design, while the second centers on a prescriptive engineering model of activity tracking for error detection and analysis. A progressive implementation strategy for both tracks is discussed in which increasingly more complex, safety-relevant applications are undertaken to extend the state-of-the-art, as well as to reveal potential human-system vulnerabilities in the aviation domain. Of particular interest is the ability to predict the precursors to error and to assess potential mitigation strategies associated with the operational use of future flight deck technologies.

  3. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

    2002-11-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

  4. Safety culture. Keys for sustaining progress

    International Nuclear Information System (INIS)

    Barraclough, I.; Carnino, A.

    1998-01-01

    Principles of nuclear safety are now well known and being put into practice around the world, leading to a degree of international harmonization in safety standards. Continued improvement in levels of safety requires the development of a comprehensive 'safety culture' at all levels of an organization, with visible and consistent leadership from senior management. This article reviews the main elements required for establishing and sustaining a good safety culture at nuclear installations that involves staff at all levels

  5. Light-water-reactor safety research program. Quarterly progress report, July--September 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Progress is summarized in the following research and development areas: (1) loss-of-coolant accident research; heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; and (3) mechanical properties of Zircaloy containing oxygen. Also included is an appendix on Kinetics of Fission Gas and Volatile Fission-product Behavior under Transient Conditions in LWR Fuel

  6. Construction safety program for the National Ignition Facility, Appendix B

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety.

  7. Construction safety program for the National Ignition Facility, Appendix B

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety

  8. Progress of nuclear safety research. 2003

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

    2004-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001, and the integrity evaluation of cracked core shroud of BWRs of the Tokyo Electric Power Company performed for assistance to the Nuclear Safety Commission in reviewing the evaluation reports by the licensees. (author)

  9. 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

  10. Nuclear reactor safety program in US department of energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1988-01-01

    The US Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and implement DOE orders. Teams of experts in the Department, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The Application of artificial intelligence technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs

  11. Prioritization of tasks in the draft LWR safety technology program plan. Final report

    International Nuclear Information System (INIS)

    Lim, E.Y.; Miller, W.J.; Parkinson, W.J.; Ritzman, R.L.; vonHerrmann, J.L.; Wood, P.J.

    1980-05-01

    The purpose of this report is to describe both the approach taken and the results produced in the SAI effort to prioritize the tasks in the Sandia draft LWR Safety Technology Program Plan. This work used the description of important safety issues developed in the Reactor Safety Study (2) to quantify the effect of safety improvements resulting from a research and development program on the risk from nuclear power plants. Costs of implementation of these safety improvements were also estimated to allow a presentation of the final results in a value (i.e., risk reduction) vs. impact (i.e., implementation costs) matrix

  12. F-35 Joint Strike Fighter: Preliminary Observations on Program Progress

    Science.gov (United States)

    2016-03-23

    current fighter aircraft. The cost of extending the lives of current fighter aircraft and acquiring other major weapon systems, while continuing to... Norway . Ongoing Manufacturing and Reliability Progress Continue Page 12 GAO-16-489T rework, and repair costs have remained steady over...Program Progress Why GAO Did This Study With estimated acquisition costs of nearly $400 billion, the F-35 Joint Strike Fighter—also known as the

  13. Fusion Safety Program annual report, fiscal year 1985

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-02-01

    The Fusion Safety Program (FSP) has supported magnetic fusion technology for seven years, and this is the seventh annual report issued by the FSP. Program focus is identification of the magnitude and distribution of radioactive inventories in fusion reactors, and research and analysis of postulated accident scenarios that could cause the release of a portion of these inventories. Research results are used to develop improved designs that can reduce the probability and magnitude of such releases and thus improve the overall safety of fusion reactors. During FY-1985, research activities continued and participation continued on the Ignition Systems Project (ISP). This report presents the significant results of EGandG Idaho, Inc., activities and those from outside contracts, and includes a list of publications produced during the year, and activities planned for FY-1986

  14. Waste Management Program. Technical progress report, October-December 1982

    International Nuclear Information System (INIS)

    1983-07-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities

  15. Fusion Safety Program annual report: Fiscal year 1986

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-06-01

    This report summarizes the Fusion Safety Program's (FSP) major activities in fiscal year 1986. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and EG and G Idaho, Inc., is the prime contractor for FSP, which was initiated in 1979. Activities are conducted at the INEL and in participating facilities, including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in this report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruption, risk assessment methodology, and computer code development for reactor transients. Contributions to the Technical Planning Activity (TPA) and the ''white paper'' study by the Environmental, Safety,and Economics Committee (ESECOM) are summarized. The report also includes a summary of the safety and environmental analysis and documentation performed by the INEL for the Compact Ignition Tokamak (CIT) design project

  16. Training and qualification program for nuclear criticality safety technical staff. Revision 1

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1997-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

  17. Nuclear Safety Culture Assessment for a Newcomer Country: Case Study of Jordan

    International Nuclear Information System (INIS)

    Khasawneh, Khalid; Park, Yun Woon

    2016-01-01

    For countries initiating or considering to start their nuclear power programs; developing a successful safety culture is of a great challenge, owing to lack of experience and the sensitive nature of the nuclear industry in general. The Jordanian case was chosen since Jordan is in the early stages of its nuclear program and the establishment of an effective safety culture is crucial to guarantee the safe operation of its future nuclear facilities. It also should be noted that Fukushima accident has adversely affected the progress of the Jordanian nuclear program driven by the negative public opinion. The government shifts the policies toward enhancing the nuclear safety by enforcing the communication between the engaged parties and openness and transparency with public. In the wake of Fukushima accident the Jordanian government reassured the appropriate siting criteria and siting review, the leadership and the organizations commitment to nuclear safety by adopting advanced reactor technology, the consideration of modern operator accident mitigation strategies and the increased and close cooperation with IAEA and adherence to evolving international safety standards. The progress in the Jordanian nuclear power project in order to satisfy the IAEA requirements was quantified and ranked. A good progress was shown in some aspects, for example in the multicultural and multi-national elements and the establishment of an independent and effective regulatory body. However, some elements, concerning the understanding of the safety culture, management system of the regulatory body and the cultural assessment was not satisfied and an urgent need to focus on and enhance those aspects are required by the Jordanian government. Some elements, for example the leadership, communication and competence, have partial fulfillment of the IAEA requirements. However enhancing those aspects is required in the short and the mid-term in order to guarantee a well-established nuclear power

  18. Nuclear Safety Culture Assessment for a Newcomer Country: Case Study of Jordan

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Khalid; Park, Yun Woon [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    For countries initiating or considering to start their nuclear power programs; developing a successful safety culture is of a great challenge, owing to lack of experience and the sensitive nature of the nuclear industry in general. The Jordanian case was chosen since Jordan is in the early stages of its nuclear program and the establishment of an effective safety culture is crucial to guarantee the safe operation of its future nuclear facilities. It also should be noted that Fukushima accident has adversely affected the progress of the Jordanian nuclear program driven by the negative public opinion. The government shifts the policies toward enhancing the nuclear safety by enforcing the communication between the engaged parties and openness and transparency with public. In the wake of Fukushima accident the Jordanian government reassured the appropriate siting criteria and siting review, the leadership and the organizations commitment to nuclear safety by adopting advanced reactor technology, the consideration of modern operator accident mitigation strategies and the increased and close cooperation with IAEA and adherence to evolving international safety standards. The progress in the Jordanian nuclear power project in order to satisfy the IAEA requirements was quantified and ranked. A good progress was shown in some aspects, for example in the multicultural and multi-national elements and the establishment of an independent and effective regulatory body. However, some elements, concerning the understanding of the safety culture, management system of the regulatory body and the cultural assessment was not satisfied and an urgent need to focus on and enhance those aspects are required by the Jordanian government. Some elements, for example the leadership, communication and competence, have partial fulfillment of the IAEA requirements. However enhancing those aspects is required in the short and the mid-term in order to guarantee a well-established nuclear power

  19. Safety analysis report upgrade program at the Plutonium Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pan, P.Y.

    1993-01-01

    Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements

  20. ERC Safety and Hygiene Programs functional organization structure and mission statement

    International Nuclear Information System (INIS)

    Coleman, S.R.

    2000-01-01

    This document provides a description of the functions, structure, commitments, and goals of the Environmental Restoration Contractor Safety and Hygiene Program. The current structure of the ERC Safety and Hygiene organization is described herein

  1. European passive plant program preliminary safety analyses to support system design

    International Nuclear Information System (INIS)

    Saiu, Gianfranco; Barucca, Luciana; King, K.J.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In the Phase 1 of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) was completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. Incorporation of the EUR has been a key design requirement for the EP1000 form the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. The present paper describes the EP1000 approach to safety analysis and, in particular, to the Design Extension Conditions that, according to the EUR, represent the preferred method for giving consideration to the Complex Sequences and Severe Accidents at the design stage without including them in the design bases conditions. Preliminary results of some DEC analyses and an overview of the probabilistic safety assessment (PSA) are also presented. (author)

  2. Control of doses delivered to patients in medical imagery. Progress report of the program of actions recommended by the ASN. January 2015

    International Nuclear Information System (INIS)

    2015-01-01

    This report proposes an overview and an assessment of the various actions recommended by the ASN (the French Nuclear Safety Authority) for a better management of doses delivered to patients in the case of medical imagery. It indicates and discusses the progress noticed: actions which have been already performed, actions which are currently in progress, and actions which are still to be launched. These actions concern various aspects: the practice quality and safety (quality and safety management), the organisation, human resources and training, equipment and installation safety, radio-vigilance practices, relationships with patients, knowledge of practices and of exposures of patients and workers. Some highlights are outlined: some persistent lacks in human resources, some encouraging initiatives in the field of training, some progresses in the field of practice quality and safety, and some limited results regarding equipment (notably MRI) and installation safety

  3. Food Safety Program in Asian Countries.

    Science.gov (United States)

    Yamaguchi, Ryuji; Hwang, Lucy Sun

    2015-01-01

    By using the ILSI network in Asia, we are holding a session focused on food safety programs in several Asian areas. In view of the external environment, it is expected to impact the global food system in the near future, including the rapid increase in food demand and in public health services due to population growth, as well as the threats to biosecurity and food safety due to the rapid globalization of the food trade. Facilitating effective information sharing holds promise for the activation of the food industry. At this session, Prof. Hwang shares the current situation of Food Safety and Sanitation Regulations in Taiwan. Dr. Liu provides a talk on the role of risk assessment in food regulatory control focused on aluminum-containing food additives in China. After the JECFA evaluation of aluminum-containing food additives in 2011, each country has carried out risk assessment based on dietary intake surveys. Ms. Chan reports on the activities of a working group on Food Standards Harmonization in ASEAN. She also explains that the ILSI Southeast Asia Region has actively supported the various ASEAN Working Groups in utilizing science to harmonize food standards. Prof. Park provides current research activities in Korea focused on the effect of climate change on food safety. Climate change is generally seen as having a negative impact on food security, particularly in developing countries. We use these four presentations as a springboard to vigorous discussion on issues related to Food Safety in Asia.

  4. Progress of IRSN R&D on ITER Safety Assessment

    Science.gov (United States)

    Van Dorsselaere, J. P.; Perrault, D.; Barrachin, M.; Bentaib, A.; Gensdarmes, F.; Haeck, W.; Pouvreau, S.; Salat, E.; Seropian, C.; Vendel, J.

    2012-08-01

    The French "Institut de Radioprotection et de Sûreté Nucléaire" (IRSN), in support to the French "Autorité de Sûreté Nucléaire", is analysing the safety of ITER fusion installation on the basis of the ITER operator's safety file. IRSN set up a multi-year R&D program in 2007 to support this safety assessment process. Priority has been given to four technical issues and the main outcomes of the work done in 2010 and 2011 are summarized in this paper: for simulation of accident scenarios in the vacuum vessel, adaptation of the ASTEC system code; for risk of explosion of gas-dust mixtures in the vacuum vessel, adaptation of the TONUS-CFD code for gas distribution, development of DUST code for dust transport, and preparation of IRSN experiments on gas inerting, dust mobilization, and hydrogen-dust mixtures explosion; for evaluation of the efficiency of the detritiation systems, thermo-chemical calculations of tritium speciation during transport in the gas phase and preparation of future experiments to evaluate the most influent factors on detritiation; for material neutron activation, adaptation of the VESTA Monte Carlo depletion code. The first results of these tasks have been used in 2011 for the analysis of the ITER safety file. In the near future, this R&D global programme may be reoriented to account for the feedback of the latter analysis or for new knowledge.

  5. 14 CFR 91.25 - Aviation Safety Reporting Program: Prohibition against use of reports for enforcement purposes.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Aviation Safety Reporting Program... GENERAL OPERATING AND FLIGHT RULES General § 91.25 Aviation Safety Reporting Program: Prohibition against... to the National Aeronautics and Space Administration under the Aviation Safety Reporting Program (or...

  6. Overview of a radiation safety program in a district style medical environment

    International Nuclear Information System (INIS)

    Wilson, G.

    2006-01-01

    This paper provides an overview of the eight components of a radiation safety program in a large health care facility spread out over several campuses in a large geographic area in Nova Scotia. The main focus is based on those areas that are regulated by the Canadian Nuclear Safety Commission and generally encompass nuclear medicine and radiation therapy operations. X-ray operations are regulated provincially, but the general operational principles of an effective radiation safety program can be applied in all these areas. The main components covered include the set up of an organizational structure that operates separately from individual departments, general items expected from reports to corporate management or regulators, and some examples of the front-line expectations for those in individual departments. The review is not all encompassing, but should give organizations some insight of the magnitude of a radiation safety program in a district style environment. (author)

  7. National machine guarding program: Part 2. Safety management in small metal fabrication enterprises

    OpenAIRE

    Parker, David L.; Yamin, Samuel C.; Brosseau, Lisa M.; Xi, Min; Gordon, Robert; Most, Ivan G.; Stanley, Rodney

    2015-01-01

    Background Small manufacturing businesses often lack important safety programs. Many reasons have been set forth on why this has remained a persistent problem. Methods The National Machine Guarding Program (NMGP) was a nationwide intervention conducted in partnership with two workers' compensation insurers. Insurance safety consultants collected baseline data in 221 business using a 33?question safety management audit. Audits were completed during an interview with the business owner or manag...

  8. The Role Of Quality Assurance Program For Safety Operation Of Nuclear Installations

    International Nuclear Information System (INIS)

    Harjanto, N.T.; Purwadi, K.P.; Boru, D.S.; Farida; Suharni

    2000-01-01

    Nuclear installations expose potential hazard of radiation, therefore in their construction, operation and maintenance, it is necessary to consider safety aspect, in which the safety requirements which has been determined must be met. One of the requirements that is absolutely needed is quality assurance, which covers arrangement of quality assurance program, organization and administration of the implementation of quality assurance, and supervision. Quality Assurance program is a guideline containing quality policies and basic determination on the realization of activities that effect the quality of equipment's and items used in the operation of nuclear installations in order that the operation of nuclear installation can run safety and in accordance with their design aims and operation limits. Quality Assurance Program includes document control, design control, supply control, control of equipment s and items, operation/process control, inspection and control of equipment test, and control of nonconformance and corrections. General system of nuclear installation operation is equipped with safety and supporting systems. These systems must apply the quality assurance program that cover control of activities in the systems. In the implementation of the quality assurance program, it is necessary to establish procedures, work guidelines/instructions, and quality recording that constitutes documents of quality system 2 nd , 3 th , and 4 th level after the quality assurance program. To ensure the effectivity and to prove whether the realization of the program has been pursuant to the determined requirements, an internal audit must be conducted accordingly

  9. Gas-Cooled Reactor Programs annual progress report for period ending December 31, 1973

    International Nuclear Information System (INIS)

    Kasten, P.R.; Coobs, J.H.; Lotts, A.L.

    1976-04-01

    Progress is summarized in studies relating to HTGR fuel reprocessing, refabrication, and recycle; HTGR fuel materials development and performance testing; HTGR PCRV development; HTGR materials investigations; HTGR fuel chemistry; HTGR safety studies; and GCFR irradiation experiments and steam generator modeling

  10. Yearly program of safety research for nuclear facilities and others

    International Nuclear Information System (INIS)

    1987-01-01

    The development of FBRs in Japan has steadily progressed, and subsequently to the experimental reactor 'Joyo' and the prototype reactor 'Monju', by promoting the construction of a demonstration reactor, the stage of verifying and acquiring skill of the electricity generation plant technology of practical scale, improving the performance and establishing the economical efficiency is about to begin. The development of FBRs in Japan has been advanced independently as a national project, and the method of preventing accidents in the actual reactors has been thoroughly taken. 'On the way of thinking in the safety evaluation of FBRs' was decided by the Nuclear Safety Commission. When the safety research from 1987 is systematized, as the constituents of safety logic, the way of thinking of the defense in depth, the way of thinking of the classification according to importance, the way of thinking of multilayer barriers against radioactive substances, and the way of thinking on severe accidents were investigated. The research concerning the decision of safety design and evaluation policy, and the safety research regarding accident prevention and relaxation, accident evaluation and severe accidents are reported. (Kako, I.)

  11. Research program on nuclear technology and nuclear safety

    International Nuclear Information System (INIS)

    Dreier, J.

    2010-04-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed

  12. Observed Food Safety Practices in the Summer Food Service Program

    Science.gov (United States)

    Patten, Emily Vaterlaus; Alcorn, Michelle; Watkins, Tracee; Cole, Kerri; Paez, Paola

    2017-01-01

    Purpose/Objectives: The purpose of this exploratory, observational study was three-fold: 1) Determine current food safety practices at Summer Food Service Program (SFSP) sites; 2) Identify types of food served at the sites and collect associated temperatures; and 3) Establish recommendations for food safety training in the SFSP.…

  13. Joint FAM/Line Management Assessment Report on LLNL Machine Guarding Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, J. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-07-19

    The LLNL Safety Program for Machine Guarding is implemented to comply with requirements in the ES&H Manual Document 11.2, "Hazards-General and Miscellaneous," Section 13 Machine Guarding (Rev 18, issued Dec. 15, 2015). The primary goal of this LLNL Safety Program is to ensure that LLNL operations involving machine guarding are managed so that workers, equipment and government property are adequately protected. This means that all such operations are planned and approved using the Integrated Safety Management System to provide the most cost effective and safest means available to support the LLNL mission.

  14. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2003. Progress report

    International Nuclear Information System (INIS)

    2003-01-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers

  15. Annual report on Reactor Safety Research Projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 1999. Progress report

    International Nuclear Information System (INIS)

    2000-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to the classification system ''Joint Safety Research Index'' of the CEC (commission of the European communities). The reports are arranged in sequence of their project numbers. (orig.)

  16. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1978-04-11

    This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index.

  17. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Klein, A.

    1978-01-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index

  18. 75 FR 44051 - Resolicitation of Applications for the Railroad Safety Technology Program Grant Program (RS-TEC...

    Science.gov (United States)

    2010-07-27

    ... have a public benefit of improved railroad safety and efficiency. The program makes available $50... projects * * * that have a public benefit of improved safety and network efficiency.'' To be eligible for... percent grantee, cost share (cash or in-kind) requirement. Applications that do not clearly indicate at...

  19. Heavy-Section Steel Irradiation Program. Volume 5, No. 2, Progress report, April 1994--September 1994

    International Nuclear Information System (INIS)

    Corwin, W.R.

    1995-07-01

    The Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness curve shift in high-copper weldments (Series 5 and 6), (3) K lc and K la curve shifts in low upper-shelf (LUS) welds (Series 8), (4) irradiation effects in a commercial LUS weld (Series 10), (5) irradiation effects on weld heat-affected zone and plate materials (Series 11), (6) annealing effects in LUS welds (Series 9), (7) microstructural and microfracture analysis of irradiation effects, (8) in-service irradiated and aged material evaluations, (9) Japan Power Development Reactor (JPDR) steel examination, (10) fracture toughness curve shift method, (11) special technical assistance, (12) technical assistance for Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Groups 3 and 12, (13) correlation monitor materials, and (14) test reactor coordination. Progress on each task is reported

  20. Evaluation of Visual Field Progression in Glaucoma: Quasar Regression Program and Event Analysis.

    Science.gov (United States)

    Díaz-Alemán, Valentín T; González-Hernández, Marta; Perera-Sanz, Daniel; Armas-Domínguez, Karintia

    2016-01-01

    To determine the sensitivity, specificity and agreement between the Quasar program, glaucoma progression analysis (GPA II) event analysis and expert opinion in the detection of glaucomatous progression. The Quasar program is based on linear regression analysis of both mean defect (MD) and pattern standard deviation (PSD). Each series of visual fields was evaluated by three methods; Quasar, GPA II and four experts. The sensitivity, specificity and agreement (kappa) for each method was calculated, using expert opinion as the reference standard. The study included 439 SITA Standard visual fields of 56 eyes of 42 patients, with a mean of 7.8 ± 0.8 visual fields per eye. When suspected cases of progression were considered stable, sensitivity and specificity of Quasar, GPA II and the experts were 86.6% and 70.7%, 26.6% and 95.1%, and 86.6% and 92.6% respectively. When suspected cases of progression were considered as progressing, sensitivity and specificity of Quasar, GPA II and the experts were 79.1% and 81.2%, 45.8% and 90.6%, and 85.4% and 90.6% respectively. The agreement between Quasar and GPA II when suspected cases were considered stable or progressing was 0.03 and 0.28 respectively. The degree of agreement between Quasar and the experts when suspected cases were considered stable or progressing was 0.472 and 0.507. The degree of agreement between GPA II and the experts when suspected cases were considered stable or progressing was 0.262 and 0.342. The combination of MD and PSD regression analysis in the Quasar program showed better agreement with the experts and higher sensitivity than GPA II.

  1. Waste Management Program: Technical progress report, July-December 1985

    International Nuclear Information System (INIS)

    1987-12-01

    This report provides information on operations and development programs relating to the management of radioactive wastes at the Savannah River Plant. Information on environmental and safety assessments, waste form development, and process and equipment development are reported for long-term waste management. 13 refs., 20 figs., 16 tabs

  2. Waste Management Program: Technical progress report, January-June 1985

    International Nuclear Information System (INIS)

    1987-12-01

    This report provides information on operations and development programs relating to the management of radioactive wastes at the Savannah River Plant. Information on environmental and safety assessments, waste form development, and process and equipment development are reported for long-term waste management. 35 refs., 12 figs., 8 tabs

  3. Cadmium safety rod thermal tests

    International Nuclear Information System (INIS)

    Thomas, J.K.; Iyer, N.C.; Peacock, H.B.

    1992-01-01

    Thermal testing of cadmium safety rods was conducted as part of a program to define the response of Savannah River Site (SRS) production reactor core components to a hypothetical LOCA leading to a drained reactor tank. The safety rods are present in the reactor core only during shutdown and are not used as a control mechanism during operation; thus, their response to the conditions predicted for the LOCA is only of interest to the extent that it could impact the progression of the accident. This document provides a description of this testing

  4. Program plan for evaluation of the Ferrocyanide Waste Tank safety issue at the Hanford Site

    International Nuclear Information System (INIS)

    Borsheim, G.L.; Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1994-03-01

    This document describes the background, priorities, strategy and logic, and task descriptions for the Ferrocyanide Waste Tank Safety Program. The Ferrocyanide Safety Program was established in 1990 to provide resolution of a major safety issue identified for 24 high-level radioactive waste tanks at the Hanford Site

  5. Software programming languages for use in developing safety systems of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo

    1997-07-01

    This report provides guidance to a verifier on reviewing of programs for safety systems written in the high level languages, such as Ada, C, and C++. The focus of the report is on programming, not design, requirements engineering, or testing. We have defined the attributes, for example, reliability, robustness, traceability, and maintainability, which largely define a general quality of software related to safety. Although an extensive revision to the standard of Ada occurred in 1995, current compiler implementations are insufficiently mature to be considered for safety systems. The discussion on C program emphasized the problem in memory allocation and deallocation, pointers, control flow, and software interface. (author). 26 refs.

  6. Safety and protection for large scale superconducting magnets. FY 1984 report

    International Nuclear Information System (INIS)

    Thome, R.J.; Pillsbury, R.D. Jr.; Minervini, J.V.

    1984-11-01

    The Fusion Program is moving rapidly into design and construction of systems using magnets with stored energies in the range of hundreds of megajoules to gigajoules. For example, the toroidal field coil system alone for TFCX would store about 4 GJ and the mirror system MFTF-B would store about 1.6 GJ. Safety and protection analyses of the magnet subsystems become progressively more important as the size and complexity of the installations increase. MIT has been carrying out a program for INEL oriented toward safety and protection in large scale superconducting magnet systems. The program involves collection and analysis of information on actual magnet failures, analyses of general problems associated with safety and protection, and performance of safety oriented experiments. This report summarizes work performed in FY 1984

  7. 2011 Annual Progress Report: DOE Hydrogen and Fuel Cells Program (Book)

    Energy Technology Data Exchange (ETDEWEB)

    2011-11-01

    In the past year, the DOE Hydrogen and Fuel Cells Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  8. 30 CFR 77.1708 - Safety program; instruction of persons employed at the mine.

    Science.gov (United States)

    2010-07-01

    ... at the mine. 77.1708 Section 77.1708 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Miscellaneous § 77.1708 Safety program; instruction of persons...

  9. A peer-to-peer traffic safety campaign program.

    Science.gov (United States)

    2014-06-01

    The purpose of this project was to implement a peer-to-peer drivers safety program designed for high school students. : This project builds upon an effective peer-to-peer outreach effort in Texas entitled Teens in the Driver Seat (TDS), the : nati...

  10. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF.

  11. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF

  12. An Introduction of Behavior-Based Safety Program in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lim, Hyeon Kyo

    2011-01-01

    There are many methods and approaches for a human error assessment that is valuable for investigating the causes of undesirable events and counter-plans to prevent their recurrence in the nuclear power plants (NPPs). There is behavior-based safety refers to the process of using a proactive approach to safety and health management. It either focuses on risk of behaviors that can lead to an injury, or on safe behaviors that can contribute to injury prevention. Early applications of behavior based safety included the construction and manufacturing industries, but today behavior based safety is applied to a wide variety of industries and service lines. This behavior based safety program can offer a set of significant human error countermeasures to be considered for human error in NPPs as well as other fields of industry. The current methods for the human error prevention in NPPs are several techniques such as Self-Check, Peer Check, Concurrent Verification, 3-way Communication, etc. However, it is not enough to grasp the whole human error problems in operations because the things are needed in fields are a behavior technique not a simple knowledge. Therefore, we applied a behavior based safety program on the current methods

  13. Quarterly report on the Ferrocyanide Safety Program for the period ending, March 31, 1995

    International Nuclear Information System (INIS)

    Cash, R.J.; Meacham, J.E.; Dukelow, G.T.

    1995-04-01

    This quarterly report provides a status of the activities underway on the Ferrocyanide Safety Issue at the Hanford Site, including actions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 90-7 (FR 1990). In March 1991, a DNFSB implementation plan (Cash 1991) responding to the six parts of Recommendation 90-7 was prepared and sent to the DNFSB. A Ferrocyanide Safety Program Plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was released in October 1994 (DOE 1994b). Activities in the program plan are underway or have been completed, and the status of each is described in Sections 2.0 and 3.0 of this report

  14. Mark I containment, short term program. Safety evaluation report

    International Nuclear Information System (INIS)

    1977-12-01

    Presented is a Safety Evaluation Report (SER) prepared by the Office of Nuclear Reactor Regulation addressing the Short Term Program (STP) reassessment of the containment systems of operating Boiler Water Reactor (BWR) facilities with the Mark I containment system design. The information presented in this SER establishes the basis for the NRC staff's conclusion that licensed Mark I BWR facilities can continue to operate safely, without undue risk to the health and safety of the public, during an interim period of approximately two years while a methodical, comprehensive Long Term Program (LTP) is conducted. This SER also provides one of the basic foundations for the NRC staff review of the Mark I containment systems for facilities not yet licensed for operation

  15. Annual progress report FY 1977. [Computer calculations of light water reactor dynamics and safety

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, K.F.; Henry, A.F.

    1977-07-01

    Progress is summarized in a project directed toward development of numerical methods suitable for the computer solution of problems in reactor dynamics and safety. Specific areas of research include methods of integration of the time-dependent diffusion equations by finite difference and finite element methods; representation of reactor properties by various homogenization procedures; application of synthesis methods; and development of response matrix techniques.

  16. Cassini RTG Program. Monthly technical progress report, 27 November--31 December 1995

    International Nuclear Information System (INIS)

    1996-01-01

    This monthly technical progress report provided information on the following tasks: spacecraft integration and liaison; engineering support; safety analysis; qualified unicouple fabrication; ETG fabrication, assembly, and test; ground support equipment (GSE); RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, and reliability, and contractor acquired government owned (CAGO) property acquisition

  17. Analyzing and strengthening the vaccine safety program in Manitoba.

    Science.gov (United States)

    Montalban, J M; Ogbuneke, C; Hilderman, T

    2014-12-04

    The emergence of a novel influenza A virus in 2009 and the rapid introduction of new pandemic vaccines prompted an analysis of the current state of the adverse events following immunization (AEFI) surveillance response in several provinces. To highlight aspects of the situational analysis of the Manitoba Health, Healthy Living and Seniors (MHHLS's) AEFI surveillance system and to demonstrate how common business techniques could be usefully applied to a provincial vaccine safety monitoring program. Situational analysis of the AEFI surveillance system in Manitoba was developed through a strengths-weaknesses-opportunities-threats (SWOT) analysis and informed by the National Immunization Strategy vaccine safety priorities. Strategy formulation was developed by applying the threats-opportunities-weaknesses-strengths (TOWS) matrix. Thirteen strategies were formulated that use strengths to either take advantage of opportunities or avoid threats, that exploit opportunities to overcome weaknesses, or that rectify weaknesses to circumvent threats. These strategies entailed the development of various tools and resources, most of which are either actively underway or completed. The SWOT analysis and the TOWS matrix enabled MHHLS to enhance the capacity of its vaccine safety program.

  18. Progress of nuclear safety research, 1990

    International Nuclear Information System (INIS)

    1990-07-01

    Since the Japan Atomic Energy Research Institute (JAERI) was founded as a nonprofit, general research and development organization for the peaceful use of nuclear energy, it has actively pursued the research and development of nuclear energy. Nuclear energy is the primary source of energy in Japan where energy resources are scarce. The safety research is recognized at JAERI as one of the important issues to be clarified, and the safety research on nuclear power generation, nuclear fuel cycle, waste management and environmental safety has been conducted systematically since 1973. As of the end of 1989, 38 reactors were in operation in Japan, and the nuclear electric power generated in 1988 reached 29 % of the total electric power generated. 50 years have passed since nuclear fission was discovered in 1939. The objective of the safety research at JAERI is to earn public support and trust for the use of nuclear energy. The overview of the safety research at JAERI, fuel behavior, reliability of reactor structures and components, reactor thermal-hydraulics during LOCA, safety assessment of nuclear power plants and nuclear fuel cycle facilities, radioactive waste management and environmental radioactivity are reported. (K.I.)

  19. The Nordic program for nuclear safety 1990-1993

    International Nuclear Information System (INIS)

    1991-02-01

    The status of ongoing projects under The Nordic Program for Nuclear Safety (NKS) 1990-1993, and the economy of the programme is presented. A review of projects, projects managers and coordinators, and a list of members of NKS and associated members is included. (CLS)

  20. Overview of DOE/ONS criticality safety projects

    International Nuclear Information System (INIS)

    Barber, R.W.; Brown, B.P.; Hopper, C.M.

    1985-01-01

    The evolution of Federal involvement with nuclear criticality safety has traversed through the 1940's and early 1950's with the Manhattan Engineering District, the 1950's and 1960's with the Atomic Energy Commission, the early 1970's with the Energy Research and Development Administration, and the late 1970's to date with the US Department of Energy. The importance of nuclear criticality safety has been maintained throughout these periods; however, criticality safety has received shifting emphases in research/applications, promulgations of regulations/standards, origins of fiscal support and organization. In June 1981 the Office of Nuclear Safety was established in response to a Department of Energy study of the impact of the March 1979 Three Mile Island accident. The organizational structure of the ONS, its program for establishing and maintaining a progressive nuclear criticality safety program, and associated projects, and current history of ONS's fiscal support of program projects is presented. With the establishment of the ONS came concomitant missions to develop and maintain nuclear safety policy and requirements, to provide independent assurance that nuclear operations are performed safely, to provide resources and management for DOE responses to nuclear accidents, and to provide technical support. In the past four years, ONS has developed and initiated a continuing Department Nuclear Criticality Safety Program in such areas as communications and information, physics of criticality, knowledge of factors affecting criticality, and computational capability

  1. Progress report: nuclear safety and radiation protection in France in 2005; Rapport annuel: la surete nucleaire et la radioprotection en France en 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

  2. Liquefied gaseous fuels safety and environmental control assessment program: a status report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-05-01

    Progress is reported in research on the safety and environmental aspects of four principal liquefied gaseous material systems: liquefied natural gas (LNG), liquefied petroleum gas (LPG), hydrogen, and ammonia. Each section of the report has been abstracted and indexed individually. (JGB)

  3. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

  4. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

  5. Nuclear air cleaning programs in progress in France

    International Nuclear Information System (INIS)

    Mulcey, P.

    1991-01-01

    A short presentation is given of the nuclear air cleaning programs in progress in France with respect to pressurized water reactors, fuel reprocessing plants, radioactive waste management facilities, and the dismantling of nuclear facilities. The effects of fires in rooms and ventilation ducts in all nuclear facilities is being studied and computer simulation codes are being developed. A brief review of filter development and filter testing is also presented

  6. Nuclear reactor safety program in U.S. Department of Energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1987-01-01

    The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)

  7. Identifying the Critical Factors Affecting Safety Program Performance for Construction Projects within Pakistan Construction Industry

    Directory of Open Access Journals (Sweden)

    Zubair Ahmed Memon

    2013-04-01

    Full Text Available Many studies have shown that the construction industry one of the most hazardous industries with its high rates of fatalities and injuries and high financial losses incurred through work related accident. To reduce or overcome the safety issues on construction sites, different safety programs are introduced by construction firms. A questionnaire survey study was conducted to highlight the influence of the Construction Safety Factors on safety program implementation. The input from the questionnaire survey was analyzed by using AIM (Average Index Method and rank correlation test was conducted between different groups of respondents to measure the association between different groups of respondent. The finding of this study highlighted that management support is the critical factor for implementing the safety program on projects. From statistical test, it is concluded that all respondent groups were strongly in the favor of management support factor as CSF (Critical Success Factor. The findings of this study were validated on selected case studies. Results of the case studies will help to know the effect of the factors on implementing safety programs during the execution stage.

  8. Price-Anderson Nuclear Safety Enforcement Program. 1996 Annual report

    International Nuclear Information System (INIS)

    1996-01-01

    This first annual report on DOE's Price Anderson Amendments Act enforcement program covers the activities, accomplishments, and planning for calendar year 1996. It also includes the infrastructure development activities of 1995. It encompasses the activities of the headquarters' Office of Enforcement in the Office of Environment, Safety and Health (EH) and Investigation and the coordinators and technical advisors in DOE's Field and Program Offices and other EH Offices. This report includes an overview of the enforcement program; noncompliances, investigations, and enforcement actions; summary of significant enforcement actions; examples where enforcement action was deferred; and changes and improvements to the program

  9. Nuclear waste management. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-04-01

    Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

  10. Radiation safety and protection in US dental hygiene programs

    International Nuclear Information System (INIS)

    Farman, A.G.; Hunter, N.; Grammer, S.

    1986-01-01

    A survey of radiation safety and protection measures used by programs teaching dental hygiene indicated some areas for concern. No barriers or radiation shieldings were used between operator and patient in four programs. Radiation monitoring devices were not worn by faculty operators in 16% of the programs. Fewer than half of the programs used thyroid shields for patients on a routine basis. Insufficient filtration for the kilovolt peak employed was used by 14% of the programs, and for 19% more the filtration was unknown or unspecified. Three programs used closed cones. Rectangular collimation was not used at all by 63% of the programs, and only 20% used E speed film routinely. Quality assurance for equipment maintenance and for film processing were in place at only 54% and 49% of the programs, respectively

  11. Screening of external hazards for NPP with bank type reactor. Modeling of safety related systems and equipment for RBMK. Probabilistic assessment of NPP safety on aircraft impact. Progress report

    International Nuclear Information System (INIS)

    Kostarev, V.

    1999-01-01

    This progress report was produced within the frame of IAEA research project on screening the hazards for NPP with bank type reactor. It covers the following tasks; development of the model for the primary loop system of RBMK; developing the models for safety related equipment of RBMK; developing of models for safety related models of EGP-6 type reactor (Bilibinskaya Nuclear Co-generated heat and Power Plant); and probabilistic assessment of NPP safety on aircraft impact

  12. Bohunice Nuclear Power Plant Safety Upgrading Program

    International Nuclear Information System (INIS)

    Toth, A.; Fagula, L.

    1996-01-01

    Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

  13. Status of the RERTR program: overview, progress and plans

    International Nuclear Information System (INIS)

    Travelli, A.

    1985-01-01

    The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a summary of the accomplishments which the RERTR Program had achieved by the end of 1984 with its many international partners, emphasis is placed on the progress achieved during 1985 and on current plans and schedules. A new miniplate series, concentrating on U 3 Si 2 -Al and U 3 Si-Al fuels, was fabricated and is well into irradiation. The whole-core ORR demonstration is scheduled to begin in November 1985, with U 3 Si 2 -Al fuel at 4.8 g U/cm 3 . Altogether, 921 full-size test and prototype elements have been ordered for fabrication with reduced enrichment and the new technologies. Qualification of U 3 Si-Al fuel with approx.7 g U/cm 3 is still projected for 1989. This progress could not have been achieved without the close international cooperation which has existed since the beginning, and whose continuation and intensification will be essential to the achievement of the long-term RERTR goals

  14. UMTRA project office federal employee occupational safety and health program plan

    International Nuclear Information System (INIS)

    1994-06-01

    This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

  15. Commercial Alpha Waste Program. Quarterly progress report, January--March, 1975

    International Nuclear Information System (INIS)

    Cooley, C.R.

    1975-10-01

    This is the fourth quarterly progress report on the Commercial Alpha Waste Program being conducted at the Hanford Engineering Development Laboratory (HEDL) for the Division of Nuclear Fuel Cycle and Production, U. S. Energy Research and Development Administration. Data on waste composition for fuel reprocessing operations are discussed as well as information on radwaste generation at nuclear power reactors. Progress to date on development of the acid digestion process for treating combustible waste is discussed including initial studies using a critically safe tray digester. Data on alpha waste generation and product storage are also presented

  16. Progress in the US ICF Program

    International Nuclear Information System (INIS)

    Sluyter, M.M.

    1996-01-01

    The ICF Program has made exciting progress in the past year towards its goal of the achievement of fusion ignition and gain in the laboratory. A series of experiments on the Nova laser facility has resolved the major technical issues involved in the design of an ignition target. A baseline target has been designed that ignites (calculationally) with a nominal drive of 1.35 MJ (at 351 nm). In parallel, a detailed conceptual design for the National Ignition Facility (NIF-a 1.8 MJ glass laser) has been completed and a successful laser beam line prototype has validated its architecture. As a result, the Department of Energy has requested funding for the preliminary design for the NIF from the U.S. Congress. With these developments, the attainment of the long-sought goal is in sight. In addition, two new laser facilities (OMEGA Upgrade and Nike) have recently been completed, and ion-beam fusion driver development is encouraging. Their availability expands the capability of the program to perform advanced ICF and plasma experiments. copyright 1996 American Institute of Physics

  17. A summary description of the flammable gas tank safety program

    International Nuclear Information System (INIS)

    Johnson, G.D.; Sherwood, D.J.

    1994-10-01

    Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks

  18. Progress in high energy physics and nuclear safety : Proceedings of the NATO Advanced Research Workshop on Safe Nuclear Energy

    CERN Document Server

    Polański, Aleksander; Begun, Viktor

    2009-01-01

    The book contains recent results on the progress in high-energy physics, accelerator, detection and nuclear technologies, as well as nuclear safety in high-energy experimentation and in nuclear industry, covered by leading experts in the field. The forthcoming experiments at the Large Hadron Collider (LHC) at CERN and cosmic-ray experiments are highlighted. Most of the current high-energy experiments and their physical motivation are analyzed. Various nuclear energy safety aspects, including progress in the production of new radiation-resistant materials, new and safe nuclear reactor designs, such as the slowly-burning reactor, as well as the use of coal-nuclear symbiotic methods of energy production can be found in the book.

  19. Technical specification optimization program - engineered safety features

    International Nuclear Information System (INIS)

    Andre, G.R.; Jansen, R.L.

    1986-01-01

    The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

  20. Building a Safety Culture in New Comers — A Case for Turkey

    International Nuclear Information System (INIS)

    Göktepe, B.G.; Dayday, N.; Oymaci, S.

    2016-01-01

    Background: Nuclear safety is a dynamic field. The nuclear power industry has been continuing to improve the safety and performance of operating reactors. However since the Fukushima event, nuclear safety and safety culture has become one of the highest priority issues around the world. Although a safety culture development program is necessary for all nuclear countries and companies, it is especially critical for new comers starting from the pre-operational phase. Safety Culture Aspects In Newcomers: When a country embarking on a Nuclear Power Program, there are many aspects to consider. Building a national nuclear power infrastructure as one of the priority is a complex issue, requiring several years of planning. Implementation of nuclear safety infrastructure includes various steps. Major progressive steps for ensuring nuclear safety requires the availability of suitably qualified staff and the establishment of an effective safety culture in the country of concern.

  1. Progress of the RERTR program in 2001

    International Nuclear Information System (INIS)

    Travelli, A.

    2002-01-01

    This paper describes the 2001 progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners. Postirradiation examinations of microplates have continued to reveal excellent irradiation behavior of U-Mo dispersion fuels in a variety of compositions and irradiating conditions. Irradiation of two new batches of mini plates of greater sizes was completed in the ATR to investigate the swelling behavior of these fuels under prototypic conditions. These materials hold the promise of achieving the program goal of developing LEU research reactor fuels with uranium densities in the 8-9 g/cm 3 range. Qualification of the U-Mo dispersion fuels has been declared by a patent issue involving KAERI. Test fuel elements with uranium density of 6 g/cm 3 are being fabricated by BWXT and are expected to begin undergoing irradiation in the HFR-Petten reactor around March 2003, with a goal of qualifying this fuel by mid 2005. U-Mo fuel with uranium density of 8-9 g/cm 3 is expected to be qualified by mid 2007. Final irradiation tests of LEU 99 Mo targets in the RAS-GAS reactor at BATAN, in Indonesia, had to be postponed because of the 9/11 attacks, but the results collected to date indicate that these targets will soon be ready for commercial production. Excellent cooperation is also in progress with the CNEA in Argentina, MDSN/ AECL in Canada, and ANSTO in Australia. Irradiation testing of five WWR-M2 tube-type fuel assemblies fabricated by the NZChK and containing LEU UO 2 dispersion fuel was successfully completed within the Russian RERTR program. A new LEU U-Mo pin-type fuel that could be used to convert most Russian-designed research reactors has been developed by VNIJNM and is ready for testing. Four additional shipments containing 822 spent fuel assemblies from foreign research reactors were accepted by the U.S. by September 30, 2001. Altogether, 4'562 spent fuel assemblies from foreign research

  2. Progress of the RERTR program in 2001

    Energy Technology Data Exchange (ETDEWEB)

    Travelli, A. [Technology Development Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439-4841 (United States)

    2002-07-01

    This paper describes the 2001 progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners. Postirradiation examinations of microplates have continued to reveal excellent irradiation behavior of U-Mo dispersion fuels in a variety of compositions and irradiating conditions. Irradiation of two new batches of mini plates of greater sizes was completed in the ATR to investigate the swelling behavior of these fuels under prototypic conditions. These materials hold the promise of achieving the program goal of developing LEU research reactor fuels with uranium densities in the 8-9 g/cm{sup 3} range. Qualification of the U-Mo dispersion fuels has been declared by a patent issue involving KAERI. Test fuel elements with uranium density of 6 g/cm{sup 3} are being fabricated by BWXT and are expected to begin undergoing irradiation in the HFR-Petten reactor around March 2003, with a goal of qualifying this fuel by mid 2005. U-Mo fuel with uranium density of 8-9 g/cm{sup 3} is expected to be qualified by mid 2007. Final irradiation tests of LEU {sup 99}Mo targets in the RAS-GAS reactor at BATAN, in Indonesia, had to be postponed because of the 9/11 attacks, but the results collected to date indicate that these targets will soon be ready for commercial production. Excellent cooperation is also in progress with the CNEA in Argentina, MDSN/ AECL in Canada, and ANSTO in Australia. Irradiation testing of five WWR-M2 tube-type fuel assemblies fabricated by the NZChK and containing LEU UO{sub 2} dispersion fuel was successfully completed within the Russian RERTR program. A new LEU U-Mo pin-type fuel that could be used to convert most Russian-designed research reactors has been developed by VNIJNM and is ready for testing. Four additional shipments containing 822 spent fuel assemblies from foreign research reactors were accepted by the U.S. by September 30, 2001. Altogether, 4'562 spent fuel

  3. Status and progress of the RERTR program in the year 2004

    International Nuclear Information System (INIS)

    Travelli, A.

    2005-01-01

    The overall status of the RERTR program at the time of the last RERTR meeting is reviewed and the progress achieved since that meeting is described. In the fuel area, unexpected failures of LEU U-Mo dispersion plates and tubes under irradiation testing have prompted a revision of the plans to qualify these fuels. While potential solutions to the difficulties with U-Mo dispersion fuels are being explored in collaboration with our international partners, greater emphasis has been placed on accelerating development of monolithic LEU U-Mo fuel. The feasibility of converting several Russian-designed research reactors to LEU fuels has been addressed, and progress has been made in the development of LEU based 99 Mo production processes. The Russian RERTR program has made significant advances. A very important event of 2004 was the US DOE establishment of the Global Threat Reduction Initiative (GTRI). This new program accelerates and combines under the same US DOE management several programs, including RERTR, which aim to secure, remove, or dispose of, nuclear and other radioactive materials throughout the world that are vulnerable to theft by terrorists. (author)

  4. IMPLEMENTATION OF A SAFETY PROGRAM FOR THE WORK ACCIDENTS’ CONTROL. A CASE STUDY IN THE CHEMICAL INDUSTRY

    Directory of Open Access Journals (Sweden)

    Edison Cesar de Faria Nogueira

    2015-03-01

    Full Text Available This article presents a case study related to the implementation of a Work Safety Program in a chemical industry, based on the Process Safety Program, PSP, of a huge energy company. The research was applied, exploratory, qualitative and with and data collection method through documentary and bibliographical research. There will be presented the main practices adopted in order to make the Safety Program a reality inside a chemical industry, its results and contributions for its better development. This paper proposes the implementation of a Safety Program must be preceded by a diagnosis of occupational safety and health management system and with constant critical analysis in order to make the necessary adjustments.

  5. The Role and Quality of Software Safety in the NASA Constellation Program

    Science.gov (United States)

    Layman, Lucas; Basili, Victor R.; Zelkowitz, Marvin V.

    2010-01-01

    In this study, we examine software safety risk in the early design phase of the NASA Constellation spaceflight program. Obtaining an accurate, program-wide picture of software safety risk is difficult across multiple, independently-developing systems. We leverage one source of safety information, hazard analysis, to provide NASA quality assurance managers with information regarding the ongoing state of software safety across the program. The goal of this research is two-fold: 1) to quantify the relative importance of software with respect to system safety; and 2) to quantify the level of risk presented by software in the hazard analysis. We examined 154 hazard reports created during the preliminary design phase of three major flight hardware systems within the Constellation program. To quantify the importance of software, we collected metrics based on the number of software-related causes and controls of hazardous conditions. To quantify the level of risk presented by software, we created a metric scheme to measure the specificity of these software causes. We found that from 49-70% of hazardous conditions in the three systems could be caused by software or software was involved in the prevention of the hazardous condition. We also found that 12-17% of the 2013 hazard causes involved software, and that 23-29% of all causes had a software control. Furthermore, 10-12% of all controls were software-based. There is potential for inaccuracy in these counts, however, as software causes are not consistently scoped, and the presence of software in a cause or control is not always clear. The application of our software specificity metrics also identified risks in the hazard reporting process. In particular, we found a number of traceability risks in the hazard reports may impede verification of software and system safety.

  6. Patient Safety Movement: History and Future Directions.

    Science.gov (United States)

    Lark, Meghan E; Kirkpatrick, Kay; Chung, Kevin C

    2018-02-01

    Despite progress within the past 15 years, improving patient safety in health care remains an important public health issue. The history of safety policies, research, and development has revealed that this issue is more complex than initially perceived and is pertinent to all health care settings. Solutions, therefore, must be approached at the systems level and supplemented with a change in safety culture, especially in higher risk fields such as surgery. To do so, health care agents at all levels have started to prioritize the improvement of nontechnical skills such as teamwork, communication, and accountability, as reflected by the development of various checklists and safety campaigns. This progress may be sustained by adopting teamwork training programs that have proven successful in other high-risk industries, such as crew resource management in aviation. These techniques can be readily implemented among surgical teams; however, successful application depends heavily on the strong leadership and vigilance of individual surgeons. Copyright © 2018 American Society for Surgery of the Hand. Published by Elsevier Inc. All rights reserved.

  7. Evaluation of the League General Insurance Company child safety seat distribution program

    Science.gov (United States)

    1982-05-01

    This report presents an evaluation of the child safety seat distribution initiated by the League General Insurance Company in June 1979. The program provides child safety seats as a benefit under the company's auto insurance policies to policy-holder...

  8. Analyzing and strengthening the vaccine safety program in Manitoba

    Science.gov (United States)

    Montalban, JM; Ogbuneke, C; Hilderman, T

    2014-01-01

    Background: The emergence of a novel influenza A virus in 2009 and the rapid introduction of new pandemic vaccines prompted an analysis of the current state of the adverse events following immunization (AEFI) surveillance response in several provinces. Objectives To highlight aspects of the situational analysis of the Manitoba Health, Healthy Living and Seniors (MHHLS’s) AEFI surveillance system and to demonstrate how common business techniques could be usefully applied to a provincial vaccine safety monitoring program. Method Situational analysis of the AEFI surveillance system in Manitoba was developed through a strengths-weaknesses-opportunities-threats (SWOT) analysis and informed by the National Immunization Strategy vaccine safety priorities. Strategy formulation was developed by applying the threats-opportunities-weaknesses-strengths (TOWS) matrix. Results Thirteen strategies were formulated that use strengths to either take advantage of opportunities or avoid threats, that exploit opportunities to overcome weaknesses, or that rectify weaknesses to circumvent threats. These strategies entailed the development of various tools and resources, most of which are either actively underway or completed. Conclusion The SWOT analysis and the TOWS matrix enabled MHHLS to enhance the capacity of its vaccine safety program. PMID:29769910

  9. Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

    International Nuclear Information System (INIS)

    1994-09-01

    Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA's Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project

  10. Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA`s Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project.

  11. [Evaluating training programs on occupational health and safety: questionnaire development].

    Science.gov (United States)

    Zhou, Xiao-Yan; Wang, Zhi-Ming; Wang, Mian-Zhen

    2006-03-01

    To develop a questionnaire to evaluate the quality of training programs on occupational health and safety. A questionnaire comprising five subscales and 21 items was developed. The reliability and validity of the questionnaire was tested. Final validation of the questionnaire was undertaken in 700 workers in an oil refining company. The Cronbach's alpha coefficients of the five subscales ranged from 0.6194 to 0.6611. The subscale-scale Pearson correlation coefficients ranged from 0.568 to 0.834 . The theta coefficients of the five subscales were greater than 0.7. The factor loadings of the five subscales in the principal component analysis ranged from 0.731 to 0.855. Use of the questionnaire in the 700 workers produced a good discriminability, with excellent, good, fair and poor comprising 22.2%, 31.2%, 32.4% and 14.1 respectively. Given the fact that 18.7% of workers had never been trained and 29.7% of workers got one-off training only, the training program scored an average of 57.2. The questionnaire is suitable to be used in evaluating the quality of training programs on occupational health and safety. The oil refining company needs to improve training for their workers on occupational health and safety.

  12. Fusion Reactor Safety Research program. Annual report, FY-80

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1981-06-01

    The report is in three sections. Outside contracts includes a report of newly-started study at the General Atomic Company to consider safety implications of low-activation materials, portions of two papers from ongoing work at PNL and ANL, reports of the lithium spill work at HEDL, the LITFIRE code development at MIT, and risk assessment at MIT, all of which are an expansion of FY-79 outside contracts. EG and G Activities includes adaptations of four papers of ongoing work in transient code development, tritium system risk assessment, heat transfer and fluid flow analysis, and fusion safety data base. Program Plan Development includes the Executive Summary of the Plan, which was completed in FY-80, and is accompanied by a list of publications and a brief outline of proposed FY-81 activities to be based on the Program Plan

  13. From Safety Critical Java Programs to Timed Process Models

    DEFF Research Database (Denmark)

    Thomsen, Bent; Luckow, Kasper Søe; Thomsen, Lone Leth

    2015-01-01

    frameworks, we have in recent years pursued an agenda of translating hard-real-time embedded safety critical programs written in the Safety Critical Java Profile [33] into networks of timed automata [4] and subjecting those to automated analysis using the UPPAAL model checker [10]. Several tools have been...... built and the tools have been used to analyse a number of systems for properties such as worst case execution time, schedulability and energy optimization [12–14,19,34,36,38]. In this paper we will elaborate on the theoretical underpinning of the translation from Java programs to timed automata models...... and briefly summarize some of the results based on this translation. Furthermore, we discuss future work, especially relations to the work in [16,24] as Java recently has adopted first class higher order functions in the form of lambda abstractions....

  14. Information literacy progression within the Environmental science program at Linköping University

    Directory of Open Access Journals (Sweden)

    Kajsa Gustafsson Åman

    2013-12-01

    Full Text Available Since the Environmental Science program at Linköping University started 1998 the author has been liaison librarian. The program is a three-year candidate program with approximately 60 students enrolled per year. Information literacy is of vital importance for the teachers and the students. Collaboration between the liaison librarian, the teachers and the administrator is the fundament. During the years a curriculum for Information literacy has evolved. The initiative for the evolvement comes from both librarian and teachers. The program consists today of fifteen different parts with education in information literacy with a progression during the three-year program. Special concern is given to progression, learning design, learning environments and quality development. An important part is appendixes in connection to the student essay. The appendixes consist of reflections on the search of information for the essay in order to make the students more conscious about their Information Literacy processes.

  15. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 2005. Progress report

    International Nuclear Information System (INIS)

    2005-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  16. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

    International Nuclear Information System (INIS)

    2004-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  17. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  18. Structural Aging Program technical progress for period, January 1, 1992--December 31, 1992

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.

    1993-07-01

    The Structural Aging (SAG) Program is conducted for the Nuclear Regulatory Commission (NRC) by the Oak Ridge National Laboratory (ORNL). The program has the overall objective of preparing an expandable handbook or report which will provide potential structural safety issues and acceptance criteria for use by the NRC in nuclear power plant evaluations of continued service. Initial focus of the program is on concrete and concrete-related materials which comprise safety-related (Category I) structures in light-water reactor facilities. The SAG Program is organized into four tasks: Task S.1 -- Program Management, Task S.2 -- Materials Property Data Base, Task S.3 -- Structural Component Assessment/Repair Technology, and Task S.4 -- Quantitative Methodology for Continued Service Determinations. In meeting the individual objectives of these tasks resources are drawn from ORNL with subcontract support from universities and other research laboratories. This report provides an overview of principal developments in each of the four program tasks from January 1, 1992 to December 31, 1992. Planned activities under each of these tasks are also presented

  19. [Progress in synthetic biology of "973 Funding Program" in China].

    Science.gov (United States)

    Chen, Guoqiang; Wang, Ying

    2015-06-01

    This paper reviews progresses made in China from 2011 in areas of "Synthetic Biology" supported by State Basic Research 973 Program. Till the end of 2014, 9 "synthetic biology" projects have been initiated with emphasis on "microbial manufactures" with the 973 Funding Program. Combined with the very recent launch of one project on "mammalian cell synthetic biology" and another on "plant synthetic biology", Chinese "synthetic biology" research reflects its focus on "manufactures" while not giving up efforts on "synthetic biology" of complex systems.

  20. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

  1. Analytical Chemistry Division annual progress report for period ending December 31, 1985

    International Nuclear Information System (INIS)

    Shultz, W.D.

    1986-05-01

    Progress reports are presented for the four major sections of the division: analytical spectroscopy, radioactive materials laboratories, inorganic chemistry, and organic chemistry. A brief discussion of the division's role in the Laboratory's Environmental Restoration and Facilities Upgrade is given. Information about quality assurance and safety programs is presented, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited

  2. Safety analysis report for packaging (onsite) transuranic performance demonstration program sample packaging

    International Nuclear Information System (INIS)

    Mccoy, J.C.

    1997-01-01

    The Transuranic Performance Demonstration Program (TPDP) sample packaging is used to transport highway route controlled quantities of weapons grade (WG) plutonium samples from the Plutonium Finishing Plant (PFP) to the Waste Receiving and Processing (WRAP) facility and back. The purpose of these shipments is to test the nondestructive assay equipment in the WRAP facility as part of the Nondestructive Waste Assay PDP. The PDP is part of the U. S. Department of Energy (DOE) National TRU Program managed by the U. S. Department of Energy, Carlsbad Area Office, Carlsbad, New Mexico. Details of this program are found in CAO-94-1045, Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program (CAO 1994); INEL-96/0129, Design of Benign Matrix Drums for the Non-Destructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996a); and INEL-96/0245, Design of Phase 1 Radioactive Working Reference Materials for the Nondestructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996b). Other program documentation is maintained by the national TRU program and each DOE site participating in the program. This safety analysis report for packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the TRU PDP sample packaging meets the onsite transportation safety requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for an onsite Transportation Hazard Indicator (THI) 2 packaging. This SARP, however, does not include evaluation of any operations within the PFP or WRAP facilities, including handling, maintenance, storage, or operating requirements, except as they apply directly to transportation between the gate of PFP and the gate of the WRAP facility. All other activities are subject to the requirements of the facility safety analysis reports (FSAR) of the PFP or WRAP facility and requirements of the PDP

  3. DOE high-level waste tank safety program Final report, Task 002

    International Nuclear Information System (INIS)

    1998-01-01

    The overall objective of the work on Task 002 was to provide LANL with support to the DOE High-Level Waste Tank Safety program. The objective of the work was to develop safety documentation in support of the unsafe tank mitigation activities at Hanford. The work includes the development of safety assessment and an environmental assessment. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective are provided. The two tasks were: Task 2.1--safety assessment for instrumentation insertion; and Task 2.2--environmental assessment

  4. Seismic Safety Margins Research Program: a concluding look

    International Nuclear Information System (INIS)

    Cummings, G.E.

    1984-01-01

    The Seismic Safety Margins Research Program (SSMRP) was started in 1978 with the goal of developing tools and data bases to compute the probability of earthquake - caused radioactive release from commercial nuclear power plants. These tools and data bases were to help NRC to assess seismic safety at nuclear plants. The methodology to be used was finalized in 1982 and applied to the Zion Nuclear Power Station. The SSMRP will be completed this year with the development of a more simplified method of analysis and a demonstration of its use on Zion. This simplified method is also being applied to a boiling-water-reactor, LaSalle

  5. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Klein, A.

    1977-01-01

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication

  6. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1977-02-23

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

  7. Liquefied gaseous fuels safety and environmental control assessment program: third status report

    Energy Technology Data Exchange (ETDEWEB)

    1982-03-01

    This Status Report contains contributions from all contractors currently participating in the DOE Liquefied Gaseous Fuels (LG) Safety and Environmental Control Assessment Program and is presented in two principal sections. Section I is an Executive Summary of work done by all program participants. Section II is a presentation of fourteen individual reports (A through N) on specific LGF Program activities. The emphasis of Section II is on research conducted by Lawrence Livermore National Laboratory (Reports A through M). Report N, an annotated bibliography of literature related to LNG safety and environmental control, was prepared by Pacific Northwest Laboratory (PNL) as part of its LGF Safety Studies Project. Other organizations who contributed to this Status Report are Aerojet Energy Conversion Company; Applied Technology Corporation; Arthur D. Little, Incorporated; C/sub v/ International, Incorporated; Institute of Gas Technology; and Massachusetts Institute of Technology. Separate abstracts have been prepared for Reports A through N for inclusion in the Energy Data Base.

  8. EUMENES, a computer software for managing the radiation safety program information at an institutional level

    International Nuclear Information System (INIS)

    Hernandez Saiz, Alejandro; Cornejo Diaz, Nestor; Valdes Ramos, Maryzury; Martinez Gonzalez, Alina; Gonzalez Rodriguez, Niurka; Vergara Gil, Alex

    2008-01-01

    The correct application of national and international regulations in the field of Radiological Safety requires the implementation of Radiation Safety Programs appropriate to the developed practice. These Programs demand the preparation and keeping of an important number of records and data, the compliance with working schedules, systematic quality controls, audits, delivery of information to the Regulatory Authority, the execution of radiological assessments, etc. Therefore, it is unquestionable the necessity and importance of having a computer tool to support the management of the information related to the Radiation Safety Program in any institution. The present work describes a computer program that allows the efficient management of these data. Its design was based on the IAEA International Basic Safety Standards recommendations and on the requirements of the Cuban national standards, with the objective of being flexible enough to be applied in most of the institutions using ionizing radiations. The most important records of Radiation Safety Programs were incorporated and reports can be generated by the users. An additional tools-module allows the user to access to a radionuclide data library, and to carry out different calculations of interest in radiological protection. The program has been developed in Borland Delphi and manages Microsoft Access databases. It is a user friendly code that aims to support the optimization of Radiation Safety Programs. The program contributes to save resources and time, as the generated information is electronically kept and transmitted. The code has different security access levels according to the user responsibility at the institution and also provides for the analysis of the introduced data, in a quick and efficient way, as well as to notice deadlines, the exceeding of reference levels and situations that require attention. (author)

  9. The Energy-Related Inventions Program: A decade of commercial progress

    Energy Technology Data Exchange (ETDEWEB)

    Brown, M.A.; Franchuk, C.A. (Oak Ridge National Lab., TN (United States)); Wilson, C.R. (Tennessee Univ., Knoxville, TN (United States))

    1991-12-01

    This report provides information on the recent commercial progress of inventions supported by the US Department of Energy's Energy-Related Inventions Programs (ERIP). It describes the results of the latest in a series of ERIP evaluation projects that have been completed since 1980. It focuses on the economic impacts of the program, notably sales and employment benefits. The period of interest is 1980 through 1990. The evaluation is based on data collected through mail and telephone surveying of 143 participants in the Program. As of October 1989, a total of 486 inventions were recommended to DOE by the National Institute for Standards and Technology, which screens all submitted inventions in terms of technical merit, potential for commercial success, and potential energy impact. By the end of 1990, at least 109 of these inventions had entered the market, generating total cumulative sales of more than $500 million. With $25.7 million in grants awarded from 1975 through 1990, and $63.1 million in program appropriations over the same period, ERIP has generated a 20:1 return in terms of sales values to grants, and an 8:1 return in sales versus program appropriations. It is estimated that 25% of all ERIP inventions had achieved sales by the end of 1990. While it is difficult to make exact comparisons between these percentages and other indicators of the success rates of technological innovations as a whole, the ERIP figures remain impressive. The commercial progress of spin-off technologies is also documented.

  10. The Energy-Related Inventions Program: A decade of commercial progress

    Energy Technology Data Exchange (ETDEWEB)

    Brown, M.A.; Franchuk, C.A. [Oak Ridge National Lab., TN (United States); Wilson, C.R. [Tennessee Univ., Knoxville, TN (United States)

    1991-12-01

    This report provides information on the recent commercial progress of inventions supported by the US Department of Energy`s Energy-Related Inventions Programs (ERIP). It describes the results of the latest in a series of ERIP evaluation projects that have been completed since 1980. It focuses on the economic impacts of the program, notably sales and employment benefits. The period of interest is 1980 through 1990. The evaluation is based on data collected through mail and telephone surveying of 143 participants in the Program. As of October 1989, a total of 486 inventions were recommended to DOE by the National Institute for Standards and Technology, which screens all submitted inventions in terms of technical merit, potential for commercial success, and potential energy impact. By the end of 1990, at least 109 of these inventions had entered the market, generating total cumulative sales of more than $500 million. With $25.7 million in grants awarded from 1975 through 1990, and $63.1 million in program appropriations over the same period, ERIP has generated a 20:1 return in terms of sales values to grants, and an 8:1 return in sales versus program appropriations. It is estimated that 25% of all ERIP inventions had achieved sales by the end of 1990. While it is difficult to make exact comparisons between these percentages and other indicators of the success rates of technological innovations as a whole, the ERIP figures remain impressive. The commercial progress of spin-off technologies is also documented.

  11. Development of computer program for safety of nuclear power plant against tsunami

    International Nuclear Information System (INIS)

    Jin, S. B.; Choi, K. R.; Lee, S. K.; Cho, Y. S.

    2001-01-01

    The main objective of this study is the development of a computer program to check the safety of nuclear power plants along the coastline of the Korean Peninsula. The computer program describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. The computer program has been applied to several ideal and simplified problems. Obtained numerical solutions are compared to existing and available solutions and measurements. A very good agreement between numerical solutions and existing measurement is observed. The computer program developed in this study can be to check the safety analysis of nuclear power plants against tsunamis. The program can also be used to study the propagation of tsunamis for a long distance, and associated run-up and run-down process along a shoreline. Furthermore, the computer program can be used to provide the proper design criteria of coastal facilities and structures

  12. The association between event learning and continuous quality improvement programs and culture of patient safety.

    Science.gov (United States)

    Mazur, Lukasz; Chera, Bhishamjit; Mosaly, Prithima; Taylor, Kinley; Tracton, Gregg; Johnson, Kendra; Comitz, Elizabeth; Adams, Robert; Pooya, Pegah; Ivy, Julie; Rockwell, John; Marks, Lawrence B

    2015-01-01

    To present our approach and results from our quality and safety program and to report their possible impact on our culture of patient safety. We created an event learning system (termed a "good catch" program) and encouraged staff to report any quality or safety concerns in real time. Events were analyzed to assess the utility of safety barriers. A formal continuous quality improvement program was created to address these reported events and make improvements. Data on perceptions of the culture of patient safety were collected using the Agency for Health Care Research and Quality survey administered before, during, and after the initiatives. Of 560 good catches reported, 367 could be ascribed to a specific step on our process map. The calculated utility of safety barriers was highest for those embedded into the pretreatment quality assurance checks performed by physicists and dosimetrists (utility score 0.53; 93 of 174) and routine checks done by therapists on the initial day of therapy. Therapists and physicists reported the highest number of good catches (24% each). Sixty-four percent of events were caused by performance issues (eg, not following standardized processes, including suboptimal communications). Of 31 initiated formal improvement events, 26 were successfully implemented and sustained, 4 were discontinued, and 1 was not implemented. Most of the continuous quality improvement program was conducted by nurses (14) and therapists (7). Percentages of positive responses in the patient safety culture survey appear to have increased on all dimensions (p continuous quality improvement programs can be successfully implemented and that there are contemporaneous improvements in the culture of safety. Copyright © 2015 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

  13. Annual report on reactor safety research projects sponsored by the Minister for Research and Technology of the Federal Republic of Germany 1989

    International Nuclear Information System (INIS)

    1990-08-01

    Investigations on the safety of light water reactors (LWR) being performed in the framework of his research program on reactor safety are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT) (Federal Minister for Research and Technology). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The Gesellschaft fuer Reaktorsicherheit (GRS), (Society for Reactor Safety), by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP)

  14. Nuclear data needs within the U. S. Nuclear Criticality Safety program

    International Nuclear Information System (INIS)

    McKnight, R.D.; Dunn, M.E.; Little, R.C.; Felty, J.R.; McKamy, J.N.

    2008-01-01

    This paper will present the nuclear data needs currently identified within the US Nuclear Criticality Safety Program (NCSP). It will identify the priority data needs; it will describe the process of prioritizing those needs; and it will provide brief examples of recent data advances which have successfully addressed some of the priority criticality safety data needs.

  15. Food Safety Programs Based on HACCP Principles in School Nutrition Programs: Implementation Status and Factors Related to Implementation

    Science.gov (United States)

    Stinson, Wendy Bounds; Carr, Deborah; Nettles, Mary Frances; Johnson, James T.

    2011-01-01

    Purpose/Objectives: The objectives of this study were to assess the extent to which school nutrition (SN) programs have implemented food safety programs based on Hazard Analysis and Critical Control Point (HACCP) principles, as well as factors, barriers, and practices related to implementation of these programs. Methods: An online survey was…

  16. Technical progress by major task. Semiannual technical progress report, September 29, 1997 - March 29, 1998

    International Nuclear Information System (INIS)

    1998-01-01

    The technical progress achieved during the period 29 September 1997 through 29 March 1998 on Contract DE-AC03-91SF18852 Radioisotope Thermoelectric Generators and Ancillary Activities is described in this report. The report is organized by program task structure: spacecraft integration and liaison; engineering support; safety; qualified unicouple production; RTG fabrication, assembly, and test; ground support equipment; RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, reliability, contract changes, CAGO acquisition (operating funds), and CAGO maintenance and repair

  17. Prospects for probabilistic safety assessment

    International Nuclear Information System (INIS)

    Hirschberg, S.

    1992-01-01

    This article provides some reflections on future developments of Probabilistic Safety Assessment (PSA) in view of the present state of the art and evaluates current trends in the use of PSA for safety management. The main emphasis is on Level 1 PSA, although Level 2 aspects are also highlighted to some extent. As a starting point, the role of PSA is outlined from a historical perspective, demonstrating the rapid expansion of the uses of PSA. In this context the wide spectrum of PSA applications and the associated benefits to the users are in focus. It should be kept in mind, however, that PSA, in spite of its merits, is not a self-standing safety tool. It complements deterministic analysis and thus improves understanding and facilitating prioritization of safety issues. Significant progress in handling PSA limitations - such as reliability data, common-cause failures, human interactions, external events, accident progression, containment performance, and source-term issues - is described. This forms a background for expected future developments of PSA. Among the most important issues on the agenda for the future are PSA scope extensions, methodological improvements and computer code advancements, and full exploitation of the potential benefits of applications to operational safety management. Many PSA uses, if properly exercised, lead to safety improvements as well as major burden reductions. The article provides, in addition, International Atomic Energy Agency (IAEA) perspective on the topics covered, as reflected in the current PSA programs of the agency. 74 refs., 6 figs., 1 tab

  18. INPP safety upgrade programme. Accomplishments and progress

    International Nuclear Information System (INIS)

    Vaisnys, P.

    1996-01-01

    The safety upgrade programme consists of the following parts: Post Chernobyl immediate modifications undertaken to remove obvious deficiencies discovered in the course of analysis of the main causes of Chernobyl accident; Modifications to remove gaps in safety provision discovered as a result of safety assessment investigations; Modifications to remove evident discrepancies in respect to internationally accepted standard. As it follows from above the deep safety investigations were undertaken to put their findings into concrete improvement programme

  19. Risk Perceptions That Effect Behavior and Attitudes in Safety Programs

    Science.gov (United States)

    2004-01-01

    Turner, B.A. (1978), Man-made Disasters. London, Wykeham. Van Manen , Max. 1990. Reasearching lived experience: Human Science for an Action Sensitive Pedagogy. New York: State University of New York. ...question guided the study: (1) what factors determine a successful safety program? METHOD In my approach I used Phenomenological inquiry...method employed tried to capture the “essence” of lived experiences, which may have an impact on aviation safety. In Max Van Manen’s book

  20. Safety program of the Oak Ridge National Laboratory: a different approach

    International Nuclear Information System (INIS)

    Burger, G.H.

    1981-01-01

    The uniqueness and therefore different approach to Oak Ridge National Laboratory's safety program is not a result of elimination of the usual industrial safety organization, but results from the three organizations which supplement it and the areas of safety concerns that they cover. While industrial safety is primarily concerned with day-to-day routine worker activities (wearing of safety glasses and hard hats, adherence to electrical safety work procedures, proper safety lockout and tagout of equipment for maintenance activities, etc.), the other organizations, the Office of Operational Safety, Division Safety Officers and Radiation Control Officers, and the Laboratory director's Review Committees, are concerned with themuch broader spectrum of the total work environment. These organizations are concerned not only with the day-to-day worker activities but the design and conduction of all operations from a process viewpoint. The emphasis of these groups is assuring first that operations, experiments, facilities, etc., are designed properly and then secondly operated properly to assure safety of the operators, Laboratory population, and the public. Responsibilities of the three safety organizations constituting operational or process safety are described and discussed

  1. Beneficial uses program. Progress report ending December 31, 1978. [Irradiated sewage sludge

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-01

    The Beneficial Uses Program is a comprehensive program to develop the necessary technologies for cost-beneficial uses of existing and future surplus radioactive materials. The major portion of the work at Sandia is concentrated in two sub-programs: The Waste Resources Utilization Program and the Separation Technology and Source Development Program. Progress is reported on: (1) the Sandia Irradiator for Dried Sewage Sludge; (2) bacteriology; (3) mycology; (4) virology; (5) animal feeds containing irradiated sewage solids; (6) use of irradiated sewage sludge as fertilizer; and (7) development of /sup 90/Sr and /sup 137/Cs radiation sources obtained from radioactive wastes. (TFD)

  2. Safety and efficacy results of the advanced renal cell carcinoma sorafenib expanded access program in North America.

    Science.gov (United States)

    Stadler, Walter M; Figlin, Robert A; McDermott, David F; Dutcher, Janice P; Knox, Jennifer J; Miller, Wilson H; Hainsworth, John D; Henderson, Charles A; George, Jeffrey R; Hajdenberg, Julio; Kindwall-Keller, Tamila L; Ernstoff, Marc S; Drabkin, Harry A; Curti, Brendan D; Chu, Luis; Ryan, Christopher W; Hotte, Sebastien J; Xia, Chenghua; Cupit, Lisa; Bukowski, Ronald M

    2010-03-01

    The Advanced Renal Cell Carcinoma Sorafenib (ARCCS) program made sorafenib available to patients with advanced renal cell carcinoma (RCC) before regulatory approval. In this nonrandomized, open-label expanded access program, 2504 patients from the United States and Canada were treated with oral sorafenib 400 mg twice daily. Safety and efficacy were explored overall and in subgroups of patients including those with no prior therapy, nonclear cell (nonclear cell) RCC, brain metastases, prior bevacizumab treatment, and elderly patients. Sorafenib was approved for RCC 6 months after study initiation, at which time patients with no prior therapy or with nonclear cell RCC could enroll in an extension protocol for continued assessment for a period of 6 months. The most common grade > or =2 drug-related adverse events were hand-foot skin reaction (18%), rash (14%), hypertension (12%), and fatigue (11%). In the 1891 patients evaluable for response, complete response was observed in 1 patient, partial response in 67 patients (4%), and stable disease for at least 8 weeks in 1511 patients (80%). Median progression-free survival in the extension population was 36 weeks (95% confidence interval [CI], 33-45 weeks; censorship rate, 56%); median overall survival in the entire population was 50 weeks (95% CI, 46-52 weeks; censorship rate, 63%). The efficacy and safety results were similar across the subgroups. Sorafenib 400 mg twice daily demonstrated activity and a clinically acceptable toxicity profile in all patient subsets enrolled in the ARCCS expanded access program (clinicaltrials.gov identifier: NCT00111020).

  3. Analytical Chemistry Division annual progress report for period ending December 31, 1985

    Energy Technology Data Exchange (ETDEWEB)

    Shultz, W.D.

    1986-05-01

    Progress reports are presented for the four major sections of the division: analytical spectroscopy, radioactive materials laboratories, inorganic chemistry, and organic chemistry. A brief discussion of the division's role in the Laboratory's Environmental Restoration and Facilities Upgrade is given. Information about quality assurance and safety programs is presented, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited.

  4. Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE`s overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program.

  5. Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

    International Nuclear Information System (INIS)

    1994-02-01

    In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE's overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program

  6. Electrical Safety Program: Nonelectrical Crafts at LANL, Live #12175

    Energy Technology Data Exchange (ETDEWEB)

    Glass, George [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-12-22

    Los Alamos National Laboratory (LANL) and the federal government require those working with or near electrical equipment to be trained on electrical hazards and how to avoid them. Although you might not be trained to work on electrical systems, your understanding of electricity, how it can hurt you, and what precautions to take when working near electricity could save you or others from injury or death. This course, Electrical Safety Program: Nonelectrical Crafts at LANL (12175), provides knowledge of basic electrical concepts, such as current, voltage, and resistance, and their relationship to each other. You will learn how to apply these concepts to safe work practices while learning about the dangers of electricity—and associated hazards—that you may encounter on the job. The course also discusses what you can do to prevent electrical accidents and what you should do in the event of an electrical emergency. The LANL Electrical Safety Program is defined by LANL Procedure (P) 101-13. An electrical safety officer (ESO) is well versed in this document and should be consulted regarding electrical questions. Appointed by the responsible line manager (RLM), ESOs can tell you if a piece of equipment or an operation is safe or how to make it safe.

  7. Waste isolation safety assessment program

    International Nuclear Information System (INIS)

    Brandstetter, A.; Harwell, M.A.

    1979-05-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE), through the National Waste Terminal Storage (NWTS) Program, is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Among the analyses required for isolation system evaluation is the detailed assessment of the post-closure performance of nuclear waste repositories in geologic formations. This assessment is essential, since it is concerned with aspects of the nuclear power program which previously have not been addressed. Specifically, the nature of the isolation systems (e.g., involving breach scenarios and transport through the geosphere), and the time-scales necessary for isolation, dictate the development, demonstration and application of novel assessment capabilities. The assessment methodology needs to be thorough, flexible, objective, and scientifically defensible. Further, the data utilized must be accurate, documented, reproducible, and based on sound scientific principles

  8. IAEA Team Reviews Safety Progress at French Nuclear Power Plant 19-23 May 2014

    International Nuclear Information System (INIS)

    2014-01-01

    An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has evaluated the Gravelines Nuclear Power Plant (NPP) in France to assess how the station has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2012. The IAEA assembled a team of experts at the request of the Government of France to conduct the follow-up OSART mission at Gravelines NPP from 19 to 23 May 2014. Follow-up missions are standard components of the OSART programme; they are typically conducted 15-24 months after the initial OSART mission. The IAEA mission in 2012 made a number of recommendations and suggestions for consideration by the Gravelines NPP operators. The station thoroughly analyzed the OSART recommendations and suggestions and developed corrective action plans. In 18 months, the Gravelines plant has achieved the level ''resolved;; or ''satisfactory progress'' in almost all of the recommendations and suggestions made by the OSART in November 2012. During the follow-up mission, the team assessed that the operators have resolved the issues in several areas, including: Undertaking initiatives to improve fire prevention; Reinforcing contamination control practices; and Enhancing capabilities to protect emergency workers in the event of a release of radioactivity. The team identified some issues which have achieved satisfactory progress toward resolution, but need further work, including: Further improvement of measures to preventing the ingress of items or chemicals into circuits and equipment; Comprehensive application of the corrective actions programme; and Reinforcement of the containment protection system in the event of an extremely adverse situation. The team identified the following issue as one which has made insufficient progress toward resolution and needs further work: Emergency response arrangements do not follow current IAEA safety standards recommending that the plant should have a person on

  9. FERMILAB ACCELERATOR R&D PROGRAM TOWARDS INTENSITY FRONTIER ACCELERATORS : STATUS AND PROGRESS

    Energy Technology Data Exchange (ETDEWEB)

    Shiltsev, Vladimir [Fermilab

    2016-11-15

    The 2014 P5 report indicated the accelerator-based neutrino and rare decay physics research as a centrepiece of the US domestic HEP program at Fermilab. Operation, upgrade and development of the accelerators for the near- term and longer-term particle physics program at the Intensity Frontier face formidable challenges. Here we discuss key elements of the accelerator physics and technology R&D program toward future multi-MW proton accelerators and present its status and progress. INTENSITY FRONTIER ACCELERATORS

  10. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 2007. Progress report

    International Nuclear Information System (INIS)

    2007-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Research Management Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system 'Joint Safety Research Index (JSRI)'. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  11. System safety program plan for the Isotope Brayton Ground Demonstration System (phase I)

    International Nuclear Information System (INIS)

    1976-01-01

    The safety engineering effort to be undertaken in achieving an acceptable level of safety in the Brayton Isotope Power System (BIPS) development program is discussed. The safety organizational relationships, the methods to be used, the tasks to be completed, and the documentation to be published are described. The plan will be updated periodically as the need arises

  12. Development of a safety and regulation systems simulation program II

    International Nuclear Information System (INIS)

    1985-05-01

    This report describes the development of a safety and regulation systems simulation program under contract to the Atomic Energy Control Board of Canada. A systems logic interaction simulation (SLISIM) program was developed for the AECB's HP-1000 computer which operates in the interactive simulation (INSIM) program environment. The SLISIM program simulates the spatial neutron dynamics, the regulation of the reactor power and in this version the CANDU-PHW 600 MW(e) computerized shutdown systems' trip parameters. The modular concept and interactive capability of the INSIM environment provides the user with considerable flexibility of the setup and control of the simulation

  13. Nuclear criticality safety program at the University of Tennessee-Knoxville

    International Nuclear Information System (INIS)

    Basoglu, B.; Bentley, C.; Brewer, R.; Dunn, M.; Haught, C.; Plaster, M.; Wilkinson, A.; Dodds, H.; Elliott, E.; Waddell, W.

    1993-01-01

    This paper presents an overview of the nuclear criticality safety (NCS) educational program at the University of Tennessee-Knoxville. The program is an academic specialization for nuclear engineering graduate students pursuing either the MS or PhD degree and includes special NCS courses and NCS research projects. Both the courses and the research projects serve as partial fulfillment of the requirements for the degree being pursued

  14. Safety implications of control systems

    International Nuclear Information System (INIS)

    Smith, O.L.

    1983-01-01

    The Safety Implications of Control Systems Program has three major activities in support of USI-A47. The first task is a failure mode and effects analysis of all plant systems which may potentially induce control system disturbance that have safety implications. This task has made a preliminary study of overfill events and recommended cases for further analysis on the hybrid simulator. Work continues on overcooling and undercooling. A detailed investigation of electric power network is in progress. LERs are providing guidance on important failure modes that will provide initial conditions for further simulator studies. The simulator taks is generating a detailed model of the control system supported by appropriate neutronics, hydraulics, and thermodynamics submodels of all other principal plant components. The simulator is in the last stages of development. Checkout calculations are in progress to establish model stability, robustness, and qualitative credibility. Verification against benchmark codes and plant data will follow

  15. The Nordic nuclear safety program 1994-1997. Project handbook

    International Nuclear Information System (INIS)

    1997-06-01

    This is a new revision of the handbook for administrators of the Nordic reactor safety program NKS. The most important administrative functions in project management are described, which should secure a uniform management approach in all the projects. The description of the organizational scheme of the NKS and distribution of responsibilities is followed by examples of various administrative routines and document forms. In the annex the names and addresses of the staff involved in administration of the NKS program are listed. (EG)

  16. Environmental Management Science Program awards. Fiscal year 1997 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, A. [ed.; Benner, W.H.; DePaolo, D.J.; Faybishenko, B.; Majer, E.L.; Pallavicini, M.; Russo, R.E.; Shultz, P.G.; Wan, J.

    1997-10-01

    Lawrence Berkeley National Laboratory was awarded eight Environmental Management Science Program (EMSP) research grants in Fiscal Year 1996. This report summarizes the progress of each grant in addressing significant DOE site cleanup issues after completion of the first year of research. The technical progress made to date in each of the research projects is described in greater detail in individual progress reports. The focus of the research projects covers a diversity of areas relevant to site cleanup, including bioremediation, health effects, characterization, and mixed waste. Some of the projects cut across a number of focus areas. Three of the projects are directed toward characterization and monitoring at the Idaho National Engineering and Environmental Laboratory, as a test case for application to other sites.

  17. Environmental Management Science Program awards. Fiscal year 1997 annual progress report

    International Nuclear Information System (INIS)

    Simmons, A.; Benner, W.H.; DePaolo, D.J.; Faybishenko, B.; Majer, E.L.; Pallavicini, M.; Russo, R.E.; Shultz, P.G.; Wan, J.

    1997-10-01

    Lawrence Berkeley National Laboratory was awarded eight Environmental Management Science Program (EMSP) research grants in Fiscal Year 1996. This report summarizes the progress of each grant in addressing significant DOE site cleanup issues after completion of the first year of research. The technical progress made to date in each of the research projects is described in greater detail in individual progress reports. The focus of the research projects covers a diversity of areas relevant to site cleanup, including bioremediation, health effects, characterization, and mixed waste. Some of the projects cut across a number of focus areas. Three of the projects are directed toward characterization and monitoring at the Idaho National Engineering and Environmental Laboratory, as a test case for application to other sites

  18. Technical safety appraisal of buildings 9206 and 9212, Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    1989-03-01

    This report covers the results of a Safety Performance Review of the Y-12 Plant conducted during the period July 25 through August 3, 1988. A Safety Performance Review is a followup to assess changes in performance since the 1986 Technical Safety Appraisal (TSA). This review is patterned after a TSA and covered the overall safety performance at Y-12, evaluating progress to date against standards of accepted practice. The review included coverage of actions taken in response to recommendations in the TSA conducted in July--August 1986. Remaining issues were identified through an assessment of safety program deficiencies and their root causes. For each of the 14 safety-related functional areas at the Y-12 Plant, results of this review are listed in Section V. These results include a discussion, conclusions, and any new safety concerns for each program. Appendix A contains a description of the system for categorizing concerns, and the concerns are summarily tabulated in Appendix B for all programs. Appendix C describes the contractor's response and current status of each of the 59 recommendations contained in the 1986 TSA

  19. Healthcare reform from the inside: A neurosurgical clinical quality program

    OpenAIRE

    Afsar-Manesh, Nasim; Martin, Neil A.

    2012-01-01

    During the past decade, the U.S. health care system has faced increasing challenges in delivering high quality of care, ensuring patient safety, providing access to care, and maintaining manageable costs. While reform progresses at a national level, health care providers have a responsibility and obligation to advance quality and safety. In 2009, the authors implemented a department-wide Clinical Quality Program. This Program comprised of an inter-disciplinary group of providers and staff wor...

  20. An augmented audit program for assuring radiation safety during radiographic examination operations

    International Nuclear Information System (INIS)

    Jervey, R.A. Jr.; Papin, P.J.

    1993-01-01

    Auditing a gamma radiography program is required as part of the authorizing license. Checklists and cursory reviews are the typical approach to addressing program requirements. A more proactive approach is recommended. The audit program described was prepared for a specific set of operating conditions but can be applied to any given program. Improvements in the effectiveness of the radiography safety program can be made with additional examination and emphasis on direct observation of licensed activities