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Sample records for safety information meeting

  1. Twenty-First Water Reaction Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 2, presents papers on severe accident research

  2. Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

  3. Transactions of the nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1991-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual summaries have been cataloged separately

  4. Transactions of the twenty-fifth water reactor safety information meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

  5. Transactions of the twenty-fifth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session

  6. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

  7. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  8. Transactions of the twenty-second water reactor safety information meeting

    International Nuclear Information System (INIS)

    1994-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 22nd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 24--26, 1994. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session. Individual papers have been cataloged separately

  9. Thirteenth water reactor safety research information meeting: proceedings Volume 1

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1986-02-01

    This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

  10. Transactions of the Twentieth Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 20th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 21--23, 1992. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included

  11. Meeting of the high committee for nuclear safety transparency and information. Proceedings of the June 18, 2008 meeting

    International Nuclear Information System (INIS)

    2008-01-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 3 main topics: 1 - the organization and stakes of nuclear safety and radiation protection in France, 2 - the plutonium imports and transports from England to France and their conformability with respect to the maritime, nuclear safety and nuclear security regulations, 3 - the role and operation of the HCTISN. This document is the proceedings of this meeting. (J.S.)

  12. High committee for nuclear safety transparency and information. March 17, 2009 meeting

    International Nuclear Information System (INIS)

    2009-03-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 9 main topics: 1 - presentation by the French nuclear safety authority (ASN) of a dismantling strategy for nuclear facilities, in particular taking into account a final state for the site and the information of populations; 2 - status of the next campaign of iodine tablets distribution; 3 - the management of ancient uranium mines and in particular the long-term environmental and health impact of mine tailings; 4 - the implementation of the high committee's recommendations; 5 - work progress of the working group on information transparency; 6 - Areva's invitation of the working group on information transparency to assist to the organisation of a Mox fuel convoy between Cherbourg and Japan; 7 - progress of the working group on the elaboration of a 'communication scale' comparable to the INES scale; 8 - presentation of the meetings organized by the ANCLI (French national association of local information commissions) about the implementation of the Aarhus convention; 9 - presentation by the IRSN (Institute of radiation protection and nuclear safety) of its communication approach towards the public. (J.S.)

  13. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan

  14. High committee for nuclear safety transparency and information. July 1, 2009 meeting

    International Nuclear Information System (INIS)

    2009-07-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 5 main points: 1 - radioactive waste management: status and steps of the June 28, 2006 law, ANDRA's projects of deep geologic disposal for long living/high-medium activity wastes and of low depth disposal for long living/low activity wastes, French nuclear safety authority (ASN) opinion about the sites choice, implementation of article 10 of the June 28, 2006 law relative to public information; 2 - progress of the working groups' works on transparency and secrecy, on the development of a communication scale, and on the creation of an Internet portal for the radio-ecological follow-up of nuclear sites; 3 - comments of the ASN's report on the nuclear safety and radiation protection in France in 2008; 4 - procedure of management of the radio-physicists shortage in order to warrant the patients' safety and information; 5 - miscellaneous points: project of European directive on nuclear safety, organisation of a visit day onboard of a ship for nuclear materials transportation, comments about the by-law from May 5, 2009, relative to the exemption to informing consumers about the addition of radionuclides to consumption and construction products. (J.S.)

  15. High committee for nuclear safety transparency and information. December 18, 2008 meeting

    International Nuclear Information System (INIS)

    2008-12-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 6 main topics: 1 - a presentation of nuclear medicine by Prof. Devaux, of its domains of application and the respect of radiation protection rules; 2 - the launching of a working group on the transparency/secrecy problem with nuclear activities; 3 - the elaboration of an environmental radioactivity index by the nuclear safety authority (ASN); 4 - the order addressed to the Cruas nuclear facility for the lack of standardized marking and maintenance of pipes used for the transport of explosive fluids; 5 - the consequences of the blocking of 2 fuel assemblies (out of 157) in the Tricastin reactor core; 6 - the flood at the Tricastin site, its origin and consequences. (J.S.)

  16. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    International Nuclear Information System (INIS)

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980

  17. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980.

  18. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 2, presents papers on: Severe accident research; Severe accident and policy implementation; and Accident management. The individual papers have been cataloged separately

  19. High committee for nuclear safety transparency and information. October 8, 2009 meeting

    International Nuclear Information System (INIS)

    2009-10-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 3 main points: 1 - the progress of the different working groups work: elaboration of a communication scale, comparable to the INES scale, for the evaluation of environmental radioactivity, the realisation of a web site for the HCTISN, the question of transparency and secrecy around the maritime transportation of radioactive materials after the visit by the High Committee of two ships from the British INS company; 2 - the management of radioactive wastes with the concept of storage reversibility: political, technical and decisional aspects, position of the National Evaluation Committee for the researches and studies relative to radioactive materials and wastes management (CNE), position of the ANCLI (French national association of local information commissions), debate; 3 - the shortage of radio-physicists in France and the information of populations and patients (declaration of incidents). Some miscellaneous points are reported as well: the first draft of the first annual report of the HCTISN, development of a societal approach for the research programs of the French institute of radiation protection and nuclear safety (IRSN), validation of a collaboration proposal with the ANCLI. (J.S.)

  20. High committee for nuclear safety transparency and information. November 20, 2009 meeting of the High Committee

    International Nuclear Information System (INIS)

    2009-11-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment, and, depending on the events, some extraordinary meetings. This document is the proceedings of an extraordinary meeting about the information and transparency in relation with the management of nuclear materials and wastes at all stages of the fuel cycle. The reason of this meeting is a request from the French Minister of ecology, energy, sustainable development and sea (MEEDDM) after the broadcast of a TV documentary entitled 'wastes: the nuclear industry nightmare' and the publication of a press article affirming that 'our nuclear wastes are hidden in Siberia'. The Minister expressed his wish to have the question of the international trade of nuclear materials examined by the HCTISN. The document is organized as follows: a first part presents the hearings of the general direction of energy and climate (DGEC), of the nuclear safety authority (ASN), of EdF, of Areva, of the CEA, of the senior official for the defense and security of the MEEDDM, of Rosatom company and of Greenpeace organisation. A second part examines the incident which took place in October 2009 at the plutonium technology workshop (ATPu) of Cadarache, where about 22 to 39 kg of plutonium powder were discovered in the gloveboxes of this facility, decommissioned in 2005 and undergoing dismantlement today. This part presents the hearings of the CEA, of AREVA, of the Institute of radiation protection and nuclear safety (IRSN), of the ASN, of the hygiene, safety and labour conditions committee (CHSCT) of Areva and CEA, and of the local information commission (CLI) of Cadarache, in relation with

  1. Report of the 52. meeting of the Superior Council of the Nuclear Safety and Information (project)

    International Nuclear Information System (INIS)

    2000-01-01

    Since june 2000, the CSSIN (Superior Council on Nuclear Safety and Information) decided to present the meeting of its sessions, on the Internet site of the Nuclear Safety Authority. This document is the meeting project concerning the session of the 27 june 2000. The following subjects have been treated: the Blayais accident and its consequences; the Euratom Directive transposition on the workers and people protection; methodology and organization of the CSSIN concerning the civil nuclear installations and the radiation protection; actualization of the CSSIN heading in the Internet site of the Nuclear Safety Authority. (A.L.B.)

  2. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 3, presents papers on: Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive light water researchers; Thermal Hydraulics; and Earth sciences. The individual papers have been cataloged separately

  3. Proceedings of fuel safety research specialists' meeting

    International Nuclear Information System (INIS)

    Suzuki, Motoe

    2002-08-01

    Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's ''Advanced LWR Fuel Performance and Safety Research Program''. A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting. The 10 of the presented papers are indexed individually. (J.P.N.)

  4. 77 FR 25502 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-04-30

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

  5. 75 FR 6407 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-02-09

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

  6. 78 FR 36793 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-06-19

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

  7. 75 FR 36697 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-06-28

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

  8. 78 FR 14314 - Towing Safety Advisory Committee; Meetings

    Science.gov (United States)

    2013-03-05

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

  9. Seventh ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Raeder, J.; Gordon, C.

    2000-01-01

    From February 15 to 18, 2000, the Seventy Technical Meeting on Safety and Environment was held at the Garching Joint Work Site which now hosts the Safety, Environment and Health Group of the ITER Joint Central Team. At this meeting, safety experts from the Home Teams worked with the SEHG members on reviews and agreements on the contents of GSSR and on the tasks and the schedule for the production of GSSR as well as the design information to be used and for the analyses to be done

  10. Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy`s efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees` requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees` post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant`s requests, a fourth information exchange will be held later in 1997.

  11. Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

    International Nuclear Information System (INIS)

    1997-04-01

    This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy's efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees' requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees' post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant's requests, a fourth information exchange will be held later in 1997

  12. Transactions of the twenty-third water reactor safety information meeting to be held at Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1995-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 23rd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory, Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  13. Transactions of the twenty-third water reactor safety information meeting to be held at Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 23rd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory, Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

  14. 75 FR 21602 - Online Safety and Technology Working Group Meeting

    Science.gov (United States)

    2010-04-26

    ... OSTWG is tasked with evaluating industry efforts to promote a safe online environment for children. The... and Technology Working Group Meeting AGENCY: National Telecommunications and Information... public meeting of the Online Safety and Technology Working Group (OSTWG). DATES: The meeting will be held...

  15. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

  16. 75 FR 1338 - Online Safety and Technology Working Group Meeting

    Science.gov (United States)

    2010-01-11

    ... promote a safe online environment for children. The Act requires the OSTWG to report its findings and... and Technology Working Group Meeting AGENCY: National Telecommunications and Information... public meeting of the Online Safety and Technology Working Group (OSTWG). DATES: The meeting will be held...

  17. Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately.

  18. Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

    International Nuclear Information System (INIS)

    Monteleone, S.

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately

  19. 40 CFR 68.48 - Safety information.

    Science.gov (United States)

    2010-07-01

    ...) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 2 Prevention Program § 68.48 Safety information. (a) The... regulated substances, processes, and equipment: (1) Material Safety Data Sheets that meet the requirements...) Equipment specifications; and (5) Codes and standards used to design, build, and operate the process. (b...

  20. Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Chaewoon [International Policy Department Policy and Standard Division, Korea Institute of Nuclear Safety, 19 Gusung-Dong Yuseong-Ku, 305-338 DAEJEON (Korea, Republic of)

    2008-07-01

    'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing

  1. High committee for nuclear safety transparency and information. September 23, 2008 meeting; Haut comite pour la transparence et l'information sur la securite nucleaire. Reunion du 23 septembre 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-09-15

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 6 main points: 1 - the terms of the High Committee operation and the internal rules for the meetings; 2 - the plutonium imports and transportation between Great Britain and France (contracts status, ship safety report, plutonium grade, return of plutonium-derived wastes): hearing of Areva, of the general direction of infrastructures, transports and sea (DGITM), of Greenpeace organisation, debate; 3 - the follow-up of the July 7, 2008 incident at the Socatri facility (Tricastin site (France)) where the overflow of a storage tank led to the spillage of a uraniferous solution on the ground: hearing of Areva (remedial action, re-start up of the facility, environmental monitoring, communication and transparency), hearing of the nuclear safety authority (ASN), of the institute of radiation protection and nuclear safety (IRSN), of the local commission of information (CIGEET), of the hygiene, safety and labour conditions committee (CHSCT) of Socatri company, of the direction of civil safety (DSC), debate about the information dissemination around this incident; 4 - Opinion of the High Committee about the plutonium transportation between Great Britain and France, and about the Socatri incident; 5 - referral to the High Committee of the radioecological follow up of all nuclear sites and of the quality of the information given to the public: ASN's reports about the radioecological follow-up of surface and ground waters and of the ancient radioactive waste storage sites, ASND's answer (Nuclear safety authority of defense), IRSN

  2. 17. meeting of the Society for Reactor Safety. Proceedings

    International Nuclear Information System (INIS)

    1994-06-01

    An autonomous and independent reactor safety research in Germany is indispensable. Three out of the four papers of the meeting deal with the protective aim concept of NPP. Deterministic safety assessment during periodic in-service inspections, a new generation of information engineering, and the incorporation of serious accidents in the containment design of new reactors are considered in detail. (DG) [de

  3. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

  4. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting

  5. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-01-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  6. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-01-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  7. Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  8. Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  9. Specialists' meeting on passive and active safety features of LMFRs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics.

  10. Specialists' meeting on passive and active safety features of LMFRs

    International Nuclear Information System (INIS)

    1991-01-01

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics

  11. Summary of fuel safety research meeting 2004

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

    2004-10-01

    Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

  12. 76 FR 34139 - Northeast Corridor Safety Committee; Meeting Postponement

    Science.gov (United States)

    2011-06-10

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

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

    International Nuclear Information System (INIS)

    1978-11-01

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

  14. 76 FR 23339 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-04-26

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

  15. IAEA meeting report of the consultants' meeting on safety improvements of WWER-440 model 230 nuclear power plants

    International Nuclear Information System (INIS)

    1998-05-01

    In 1992 the identification and ranking of safety issues for WWER-440/230 NPPs were completed. Some 100 safety issues have been identified and ranked according to their safety impact on the plant's defence in depth. The IAEA work was based on a conceptual design review and a series of safety review missions to each one of the four sites (Bohunice, Kozloduy, Novovoronezh and Kola) where WWER-440/230 NPPs were in operation. Results were published by the IAEA in February and May 1992. Since the initial publications the IAEA has continued its activities and conducted a number of follow-up missions and technical visits to the NPP sites to review the status of implementation of safety upgradings. In September of 1994 a Consultants Meeting (CM) was held in Vienna to consolidate all the information available to the AEA. The results of that meeting were included in the report WWER-SC-107. During 1995-1997 further information became available from technical visits conducted by the IAEA at the four sites. Therefore, in February 1998 the IAEA convened a CM in Vienna to prepare an up-to-date report on the status of safety improvements at WWER-440/230 NPPs. This report contains the results of that meeting. It reviews the status of remedial actions implemented at each plant in response to the safety issues originally identified in the IAEA reports and the remaining safety concerns. For convenience the issues are presented under broad titles related to: integrity of barriers (Section 2); performance of basic functions (Section 3); performance of supporting functions (Section 4); internal hazards (Section 5); external hazards (Section 6); accident analysis (Section 7); operational functions (Section 8); Section 9 provides an overview of the results of PSA studies performed and under way. Section 10 provides specific information on the status of Armenia NPP. It is presented separately because the IAEA assistance to this plant was provided in the framework of the national technical co

  16. 76 FR 65205 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2011-10-20

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

  17. Working group on VVER safety analysis - report of the 2010 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2010-01-01

    The AER Working Group D on WWER reactor safety analysis held its nineteenth meeting in Pisa, Italy, during the period 15-16 April, 2010. The meeting was hosted by the San Piero a Grado Nuclear Research Group of the University of Pisa and was held in conjunction with the second workshop on the OECD/NEA Benchmark for the Kalinin-3 WWER-1000 NPP and the fourth workshop on the OECD Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs. Altogether 12 participants attended the meeting of the working group D, 8 from AER member organizations and 4 guests from non-member organization. The co-ordinator of the working group, Mr. S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics:-Code validation and benchmarking including the calculation of the OECD/NEA Benchmark for the Kalinin-3 WWER-1000 NPP;-Safety analyses and code developments;-Future activities A list of the participants and a list of the handouts distributed at the meeting are attached to the report. The corresponding PDF-files can be obtained from the chairman. (Author)

  18. 77 FR 69899 - Public Conference on Geographic Information Systems (GIS) in Transportation Safety

    Science.gov (United States)

    2012-11-21

    ... NATIONAL TRANSPORTATION SAFETY BOARD Public Conference on Geographic Information Systems (GIS) in... Geographic Information Systems (GIS) in transportation safety on December 4-5, 2012. GIS is a rapidly... visualization of data. The meeting will bring researchers and practitioners in transportation safety and GIS...

  19. 1986 international meeting of nuclear reactor safety committees

    International Nuclear Information System (INIS)

    Moeller, D.W.

    1987-01-01

    During the week of Oct. 20-23, 1986, nuclear power-plant safety representatives from the Federal Republic of Germany (FRG), France, Japan, and the US assembled to discuss subjects of mutual interest. The meeting, the first of its kind, was organized under the leadership and direction of David A. Ward, Chairman, Advisory Committee on Reactor Safeguards, US Nuclear Regulatory Commission (NRC), and held at the Wingspread Conference Center of the Johnson Foundation in Racine, Wis. Approximately 40 representatives of the several countries attended. Discussions were candid and provided the participants an opportunity to share thoughts and information on nuclear safety concerns and solutions

  20. 77 FR 26790 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2012-05-07

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

  1. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  2. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  3. 77 FR 3326 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2012-01-23

    .... 3] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of Northeast Corridor Safety Committee Meeting. SUMMARY: FRA announced the first meeting of the Northeast Corridor Safety Committee, a Federal...

  4. 76 FR 32391 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2011-06-06

    .... 1] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of the Northeast Corridor Safety Committee Meeting. SUMMARY: FRA announces the first meeting of the Northeast Corridor Safety Committee, a...

  5. High committee for nuclear safety transparency and information. November 20, 2009 meeting of the High Committee; Haut comite pour la transparence et l'information sur la securite nucleaire. Reunion du Haut comite, 20 novembre 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-11-15

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment, and, depending on the events, some extraordinary meetings. This document is the proceedings of an extraordinary meeting about the information and transparency in relation with the management of nuclear materials and wastes at all stages of the fuel cycle. The reason of this meeting is a request from the French Minister of ecology, energy, sustainable development and sea (MEEDDM) after the broadcast of a TV documentary entitled 'wastes: the nuclear industry nightmare' and the publication of a press article affirming that 'our nuclear wastes are hidden in Siberia'. The Minister expressed his wish to have the question of the international trade of nuclear materials examined by the HCTISN. The document is organized as follows: a first part presents the hearings of the general direction of energy and climate (DGEC), of the nuclear safety authority (ASN), of EdF, of Areva, of the CEA, of the senior official for the defense and security of the MEEDDM, of Rosatom company and of Greenpeace organisation. A second part examines the incident which took place in October 2009 at the plutonium technology workshop (ATPu) of Cadarache, where about 22 to 39 kg of plutonium powder were discovered in the gloveboxes of this facility, decommissioned in 2005 and undergoing dismantlement today. This part presents the hearings of the CEA, of AREVA, of the Institute of radiation protection and nuclear safety (IRSN), of the ASN, of the hygiene, safety and labour conditions committee (CHSCT) of Areva and CEA, and of the local information commission (CLI) of Cadarache

  6. Building America Expert Meeting: Combustion Safety

    Energy Technology Data Exchange (ETDEWEB)

    Brand, L.

    2013-03-01

    This is a meeting overview of 'The Best Approach to Combustion Safety in a Direct Vent World', held June 28, 2012, in San Antonio, Texas. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

  7. Twenty-second water reactor safety information meeting: Proceedings. Volume 1: Plenary session; Advanced instrumentation and control hardware and software; Human factors research; IPE and PRA

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  8. Twenty-second water reactor safety information meeting: Proceedings. Volume 1: Plenary session; Advanced instrumentation and control hardware and software; Human factors research; IPE and PRA

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  9. 76 FR 67461 - Cosmetic Microbiological Safety Issues; Public Meeting

    Science.gov (United States)

    2011-11-01

    ...] Cosmetic Microbiological Safety Issues; Public Meeting AGENCY: Food and Drug Administration, HHS. ACTION... Administration (FDA) is announcing a public meeting entitled ``Cosmetic Microbiological Safety Issues.'' The... cosmetic microbiological safety and to suggest areas for the possible development of FDA guidance documents...

  10. Eighth ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Gordon, C.; Raeder, J.

    2000-01-01

    From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

  11. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  12. 76 FR 8372 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2011-02-14

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

  13. AER Working Group D on VVER safety analysis - report of the 2009 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2009-01-01

    The AER Working Group D on VVER reactor safety analysis held its 18-th meeting in Rez, Czech Republic, during the period 18-19 May, 2009. The meeting was hosted by the Nuclear Research Institute Rez. Altogether 17 participants attended the meeting of the working group D, 16 from AER member organizations and 1 guest from a non-member organization. The co-ordinator of the working group, S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics: 1) Code validation and benchmarking; 2) Safety analysis and code developments; 3) Reactor pressure vessel thermal hydraulics; 4) Future activities including discussion on the participation in the OECD/NEA Benchmark for the Kalinin-3 NPP

  14. 76 FR 32390 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2011-06-06

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

  15. 77 FR 46555 - Motor Carrier Safety Advisory Committee: Public Meeting

    Science.gov (United States)

    2012-08-03

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

  16. 75 FR 2923 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-01-19

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

  17. 75 FR 29384 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-05-25

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

  18. 75 FR 72863 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-11-26

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

  19. 75 FR 50797 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-08-17

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

  20. 77 FR 62248 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2012-10-12

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

  1. 78 FR 44958 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2013-07-25

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

  2. Twenty-First Water Reactor Safety Information Meeting. Volume 3, Primary system integrity; Aging research, products and applications; Structural and seismic engineering; Seismology and geology: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

  3. Proceedings of the specialist research meeting on nuclear science information, (5)

    International Nuclear Information System (INIS)

    Kimura, Itsuro; Takeuchi, Takayuki; Mizuma, Mitsuo

    1985-02-01

    The Research Reactor Institute of Kyoto University held two meetings on nuclear science information in the academic year of 1984. The titles of the presented papers are: (1) Information retieval in nuclear safety; (2) Information retrieval in high-pressure gas safety; (3) Construction of nuclear science information data base at the Research Reactor Institute of Kyoto University (II); (4) Nuclear science information data base at the Research Reactor Institute of Kyoto University (KURRIP)*; (5) Nuclear structure and disintegration data base; (6) Evaluated nuclear structure data file and (7) World climate data file. This report contains the full text of these papers. (author)

  4. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately

  5. Second Meeting for Evaluation of the Nuclear Safety Convention

    International Nuclear Information System (INIS)

    2002-01-01

    This report presents the results of the Second Meeting for Evaluation of the Nuclear Safety Convention. the CSN. as the only competent Government organism on nuclear safety, represented Spain in the preparation of the national report and at the Review Meeting, acquiring a set of obligations for the next three years, until the holding of third meeting. (Author)

  6. Methods of Certification tests PLC-Networks in Compliance Safety Information

    Directory of Open Access Journals (Sweden)

    A. A. Balaev

    2011-12-01

    Full Text Available The aim of this research was description of the methodology of the audit plc-network to meet the requirements of information security. The technique is based on the provisions of the guidance documents and model FSTEC Russia test object methods of information on safety information.

  7. 75 FR 45591 - Pipeline Safety: Notice of Technical Pipeline Safety Advisory Committee Meetings

    Science.gov (United States)

    2010-08-03

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

  8. RISK-INFORMED SAFETY MARGIN CHARACTERIZATION

    International Nuclear Information System (INIS)

    Dinh, Nam; Szilard, Ronaldo

    2009-01-01

    The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system's 'loading' and its 'capacity', plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  10. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    1982-09-01

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

  11. 78 FR 23815 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2013-04-22

    .... 6] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of the Northeast Corridor Safety Committee (NECSC) Meeting. [[Page 23816

  12. 76 FR 62455 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-10-07

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

  13. 78 FR 1265 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-01-08

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

  14. 76 FR 19147 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2011-04-06

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

  15. 78 FR 56941 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-09-16

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

  16. 77 FR 38090 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2012-06-26

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

  17. 75 FR 61219 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-10-04

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

  18. 77 FR 58413 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-09-20

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

  19. Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural & Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research & Regulatory Issues. Individual papers have been cataloged separately.

  20. Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

    International Nuclear Information System (INIS)

    Monteleone, S.

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural ampersand Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research ampersand Regulatory Issues. Individual papers have been cataloged separately

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

    International Nuclear Information System (INIS)

    1996-09-01

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

  2. 77 FR 60507 - Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting

    Science.gov (United States)

    2012-10-03

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

  3. Sixth ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Saji, G.; Baker, D.

    1997-01-01

    The article summarizes the topics of the Sixth Technical Meeting on Safety and Environment which was held to review the first draft of the Non-Site Specific Safety Report (NSSR-2) and the draft of the ITER Final Design Report Safety Assessment (FDR-Safety) during October 27 - November 4, 1997 at the ITER San Diego Joint Work Site

  4. 75 FR 2890 - OSHA Listens: Occupational Safety and Health Administration Stakeholder Meeting

    Science.gov (United States)

    2010-01-19

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0004] OSHA Listens: Occupational Safety and Health Administration Stakeholder Meeting AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of public meeting. SUMMARY: The Occupational Safety...

  5. Ninth ITER technical meeting on safety and environment

    International Nuclear Information System (INIS)

    Raeder, J.; Gordon, C.

    2001-01-01

    The ninth ITER Technical Meeting on safety and environment, the last in the course of the ITER Engineering Design Activities (EDA), was held at the ITER Garching Joint Work site, 8 to 10 May 2001. At this Meeting, safety experts from the House Teams worked together with the members of the Safety, Environment and Health Groups (SEHG) of the ITER Joint Central Team (JCT) in the following areas: finalization of the Generic Site Safety report (GSSR) which is considered to be the most important objective of the present work; summary of the safety related R and D work done by the Home Teams for ITER during EDA; review of verification and validation work done on computer codes being applied for Safety and Environment (S and E) analyses; outline of work considered necessary for improving the S and E database, quantifying uncertainties of the code results and preparing the adaptation of ITER to a specific site

  6. 2011 Annual Meeting of the Safety Pharmacology Society: an overview.

    Science.gov (United States)

    Cavero, Icilio

    2012-03-01

    The keynote address of 2011 Annual Meeting of the Safety Pharmacology Society examined the known and the still to be known on drug-induced nephrotoxicity. The nominee of the Distinguished Service Award Lecture gave an account of his career achievements particularly on the domain of chronically instrumented animals for assessing cardiovascular safety. The value of Safety Pharmacology resides in the benefits delivered to Pharma organizations, regulators, payers and patients. Meticulous due diligence concerning compliance of Safety Pharmacology studies to best practices is an effective means to ensure that equally stringent safety criteria are applied to both in-licensed and in-house compounds. Innovative technologies of great potential for Safety Pharmacology presented at the meeting are organs on chips (lung, heart, intestine) displaying mechanical and biochemical features of native organs, electrical field potential (MEA) or impedance (xCELLigence Cardio) measurements in human induced pluripotent stem cell-derived cardiomyocytes for unveiling cardiac electrophysiological and mechanical liabilities, functional human airway epithelium (MucilAir™) preparations with unique 1-year shelf-life for acute and chronic in vitro evaluation of drug efficacy and toxicity. Custom-designed in silico and in vitro assay platforms defining the receptorome space occupied by chemical entities facilitate, throughout the drug discovery phase, the selection of candidates with optimized safety profile on organ function. These approaches can now be complemented by advanced computational analysis allowing the identification of compounds with receptorome, or clinically adverse effect profiles, similar to those of the drug candidate under scrutiny for extending the safety assessment to potential liability targets not captured by classical approaches. Nonclinical data supporting safety can be quite reassuring for drugs with a discovered signal of risk. However, for marketing authorization

  7. 78 FR 77501 - NASA Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-12-23

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

  8. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

  9. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    International Nuclear Information System (INIS)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences

  10. 78 FR 5243 - Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees

    Science.gov (United States)

    2013-01-24

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

  11. Building America Expert Meeting. Combustion Safety

    Energy Technology Data Exchange (ETDEWEB)

    Brand, Larry [Partnership for Advanced Residential Retrofit (PARR), Des Plaines, IL (United States)

    2013-03-01

    This is an overview of "The Best Approach to Combustion Safety in a Direct Vent World," held June 28, 2012, in San Antonio, TX. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

  12. Occupational safety meets radiation protection

    International Nuclear Information System (INIS)

    Severitt, S.; Oehm, J.; Sobetzko, T.; Kloth, M.

    2012-01-01

    The cooperation circle ''Synergies in operational Security'' is a joint working group of the Association of German Safety Engineers (VDSI) and the German-Swiss Professional Association for Radiation Protection (FS). The tasks of the KKSyS are arising from the written agreement of the two associations. This includes work on technical issues. In this regard, the KKSyS currently is dealing with the description of the interface Occupational Safety / Radiation Protection. ''Ignorance is no defense'' - the KKSyS creates a brochure with the working title ''Occupational Safety meets radiation protection - practical guides for assessing the hazards of ionizing radiation.'' The target groups are entrepreneurs and by them instructed persons to carry out the hazard assessment. Our aim is to create practical guides, simple to understand. The practical guides should assist those, who have to decide, whether an existing hazard potential through ionizing radiation requires special radiation protection measures or whether the usual measures of occupational safety are sufficient. (orig.)

  13. Twenty-third water reactor safety information meeting: Volume 2, Human factors research; Advanced I and C hardware and software; Severe accident research; Probabilistic risk assessment topics; Individual plant examination: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 2, present topics in human factors research, advanced instrumentation and control hardware and software, severe accident research, probabilistic risk assessment, and individual plant examination. Individual papers have been cataloged separately.

  14. Fast reactor safety: proceedings of the international topical meeting. Volume 2

    International Nuclear Information System (INIS)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments

  15. 76 FR 37375 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2011-06-27

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

  16. 76 FR 2916 - Houston/Galveston Navigation Safety Advisory Committee; Meetings

    Science.gov (United States)

    2011-01-18

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

  17. Animal Product Safety Information

    Science.gov (United States)

    ... Home Animal & Veterinary Safety & Health Product Safety Information Product Safety Information Share Tweet Linkedin Pin it More ... to report adverse experiences with veterinary drugs. Additional Product Information Questions and Answers: Evanger’s Dog and Cat ...

  18. 75 FR 30859 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2010-06-02

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

  19. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 2: Human reliability analysis and human performance evaluation; Technical issues related to rulemakings; Risk-informed, performance-based initiatives; High burn-up fuel research

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) human reliability analysis and human performance evaluation; (2) technical issues related to rulemakings; (3) risk-informed, performance-based initiatives; and (4) high burn-up fuel research

  20. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  1. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

  2. Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

    Energy Technology Data Exchange (ETDEWEB)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

  3. Safety of and regulations for nuclear fuel cycle facilities. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-05-01

    In order to compile information on the nature of the safety concerns and current status of the regulations concerning nuclear fuel cycle facilities in Member States, an IAEA Technical Committee meeting on this topic was convened from 8 to 12 May 2000 in Vienna. The present publication contains the results of this meeting. The contributions of the participants in Annex 3 exemplify the work done in some Member States to develop an adequate regulatory framework to oversee the safe operation of these facilities

  4. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

    International Nuclear Information System (INIS)

    1995-10-01

    There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

  5. International Experts’ Meeting on Reactor and Spent Fuel Safety in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant. Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The primary objectives of this International Experts’ Meeting (IEM) were: to analyse relevant technical aspects of reactor and spent nuclear fuel management safety and performance related to severe accidents; to review what is known to date about the accident at the Fukushima Daiichi nuclear power plant in order to understand more fully its root causes; and to share the lessons learned from the accident. The meeting identified the necessary priorities for further actions in these areas in different power reactor types, focusing in particular on boiling water reactors (BWRs) and pressurized water reactors (PWRs). The meeting provided a forum for discussions and exchange of information among technical experts from Member States on reactor and spent nuclear fuel safety and performance under severe conditions. The meeting was of particular interest to technical experts from utilities, research and design organizations, regulatory bodies, manufacturing and service companies and other stakeholders. In particular, the objectives of the meeting was to: • Identify and analyse reactor and spent nuclear fuel safety and performance issues; • Consider the design, engineering and analysis of current and new systems for accident prevention and mitigation; • Exchange information on national assessments of reactor and spent nuclear fuel safety and performance; and • Identify potential priority areas for research and development, technology development and management

  6. 77 FR 73734 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2012-12-11

    .... 5] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of a Northeast Corridor Safety... Committee is made up of stakeholders operating on the [[Page 73735

  7. National nuclear safety report 2005. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2006-01-01

    This National Nuclear Safety Report was presented at the 3rd. Review meeting. In general the information contained in the report are: Highlights / Themes; Follow-up from 2nd. Review meeting; Challenges, achievements and good practices; Planned measures to improve safety; Updates to National report to 3rd. Review meeting; Questions from peer review of National Report; and Conclusions

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

    International Nuclear Information System (INIS)

    Rafferty, Barbara

    2002-01-01

    identified that require special attention, particularly, with regard to safety management, safety culture, plant ageing, upgrading and effectiveness of regulatory practices, as well as maintaining competence and knowledge in the industry, regulatory bodies and research institutions. The review process highlighted factors and circumstances, external to nuclear safety as such, which nevertheless may impact on nuclear safety. Contracting Parties were invited to provide further information in their next national reports on maintaining competence and motivation of staff needed for safe regulation and operation of nuclear installation. Since the 1999 Review Meeting, several Contracting Parties have restructured their regulatory bodies and adopted new legislation or improved existing legislation to more closely meet the requirements of the Convention. Examples of areas of new legislation are: establishing independent regulatory bodies; emergency preparedness; decommissioning; and radiation protection provisions consistent with the International Commission on Radiological Protection's 1990 Recommendations (ICRP 60) and the International Basic Safety Standards published by the IAEA (BSS). Full implementation of the ICRP 60 recommendations and BSS is not complete in some countries. Contracting Parties reported on their individual national regulatory strategies. Some Contracting Parties use probabilistic safety assessment (PSA) as an additional tool in optimizing their regulatory or inspection activities, and some use performance indicators, whether they be quantitative or qualitative, to monitor the safety of their nuclear installations. In discussions, comparison was made of the advantages and disadvantages of regulations that are detailed and prescriptive in nature as compared to less prescriptive, goal-oriented approaches and the complementary use of risk assessments. Contracting Parties agreed to review their experience and report at the next Review Meeting. All Contracting

  9. 78 FR 76627 - Health Information Technology Standards Committee Advisory Meeting: Notice of Meeting

    Science.gov (United States)

    2013-12-18

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Health Information Technology Standards Committee Advisory Meeting: Notice of Meeting AGENCY: Office of the National Coordinator for Health Information Technology... committee of the Office of the National Coordinator for Health Information Technology (ONC). These meeting...

  10. 78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

    Science.gov (United States)

    2013-03-20

    ... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

  11. 77 FR 20690 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2012-04-05

    .... 4] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of the Northeast Corridor Safety... NECSC is made up of stakeholders operating on the Northeast Corridor (NEC), and the purpose of the...

  12. 'AER Working Group D On WWER Safety Analysis' Report Of The Meeting In Pisa, Italy, 26-27 April 2006

    International Nuclear Information System (INIS)

    Siltanen, P.

    2006-01-01

    AER Working Group D on WWER reactor safety analysis held its 15 t h meeting in Grand Hotel Duomo in Pisa, Italy during the period 26-27 April 2006. The meeting was hosted by the University of Pisa following the fourth workshop on the OECD/DOE/CEA WWER-1000 Coolant Transient Benchmark (W1000-CT) held at the same location on 24-25 April. Altogether 15 participants attended the Working Group D meeting, 11 from AER member organizations and 4 guests from non-member organizations. The coordinator for the working group, Mr. P. Siltanen (FNS) served as chairman. In addition to general information exchange on recent activities in the participating organizations, the topics of the meeting included: 1) Code development and benchmarking for reactor dynamics applications. 2) Safety analysis methodology and results. 3) Future activities. A list of participants and a list of handouts distributed at the meeting are attached to the report (Author)

  13. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 2: Human reliability analysis and human performance evaluation; Technical issues related to rulemakings; Risk-informed, performance-based initiatives; High burn-up fuel research

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) human reliability analysis and human performance evaluation; (2) technical issues related to rulemakings; (3) risk-informed, performance-based initiatives; and (4) high burn-up fuel research. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  14. Online and Off-line Visualization of Meeting Information and Meeting Support

    NARCIS (Netherlands)

    Nijholt, Antinus; Rienks, R.J.; Zwiers, Jakob; Reidsma, Dennis

    2006-01-01

    In current meeting research we see modest attempts to visualize the information that has been obtained by either capturing and probably more importantly by interpreting the activities that take place during a meeting. The meetings being considered take place in smart meeting rooms. Cameras,

  15. Online and Off-line Visualization of Meeting Information and Meeting Support

    NARCIS (Netherlands)

    Nijholt, Antinus; Seah, H.S.; Rienks, R.J.; Zwiers, Jakob; Reidsma, Dennis

    2006-01-01

    In current meeting research we see modest attempts to visualize the information that has been obtained by either capturing and, probably more importantly, by interpreting the activities that take place during a meeting. The meetings being considered take place in smart meeting rooms. Cameras,

  16. Safety campaigns. TIS Launches New Safety Information Campaign

    CERN Multimedia

    2001-01-01

    Need to start a new installation and worried about safety aspects? Or are you newly responsible for safety matters in a CERN building? Perhaps you're simply interested in how to make the working environment safer for yourself and your colleagues. Whatever the case, a new information campaign launched by TIS this week can help. The most visible aspects of the new campaign will be posters distributed around the Laboratory treating a different subject each month. The Web site - http://safety.cern.ch/ - which provides all safety related information. But these are not the only aspects of the new campaign. Members of the TIS/GS group, whose contact details can be found on the safety web site, are available to give information and advice on a one-to-one basis at any time. The campaign's launch has been timed to coincide with European Safety Week, organized by the European Agency for Safety and Health at Work and the subject treated in the first posters is safety inspection. This particular topic only concerns thos...

  17. 19th JANNAF Safety and Environmental Protection Subcommittee Meeting. Volume 1

    Science.gov (United States)

    Cocchiaro, J. E. (Editor); Becker, D. L. (Editor)

    2002-01-01

    This volume, the first of two volumes, is a compilation of 22 unclassified/unlimited technical papers presented at the 19th Joint Army-Navy-NASA-Air Force (JANNAF) Safety & Environmental Protection Subcommittee Meeting. The meeting was held 18-21 March 2002 at the Sheraton Colorado Springs Hotel, Colorado Springs, Colorado. Topics covered include green energetic materials and life cycle pollution prevention; space launch range safety; propellant/munitions demilitarization, recycling, and reuse: and environmental and occupational health aspects of propellants and energetic materials.

  18. 75 FR 34520 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-06-17

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

  19. Safety Information System Guide

    International Nuclear Information System (INIS)

    Bullock, M.G.

    1977-03-01

    This Guide provides guidelines for the design and evaluation of a working safety information system. For the relatively few safety professionals who have already adopted computer-based programs, this Guide may aid them in the evaluation of their present system. To those who intend to develop an information system, it will, hopefully, inspire new thinking and encourage steps towards systems safety management. For the line manager who is working where the action is, this Guide may provide insight on the importance of accident facts as a tool for moving ideas up the communication ladder where they will be heard and acted upon; where what he has to say will influence beneficial changes among those who plan and control his operations. In the design of a safety information system, it is suggested that the safety manager make friends with a computer expert or someone on the management team who has some feeling for, and understanding of, the art of information storage and retrieval as a new and better means for communication

  20. Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety

    International Nuclear Information System (INIS)

    1997-01-01

    The fifth international topical meeting on nuclear thermohydraulics, operations and safety was convened in Beijing in April 14-18, 1997. The topical meeting was sponsored by the Chinese Nuclear Society and cosponsored by American Nuclear Society, Atomic Energy Society of Japan, American Society of Mechanical Engineers, Canada Nuclear Society, Korean Nuclear Society, Mexican Nuclear Society, Nuclear Society of Slovenia and Spanish Nuclear Society. There were 262 articles were published in the meeting. They are related nuclear power thermohydraulics, operations and safety

  1. Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

    International Nuclear Information System (INIS)

    2014-01-01

    The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-10) in Okinawa, Japan is sponsored by Atomic Energy Society of Japan, in cooperation with the International Atomic Energy Agency, and co-sponsored by American Nuclear Society Thermal Hydraulics Division among others. Enhanced safety and reducing cost are going together, which can be achieved through continued research and development efforts. NUTHOS keeps you abreast of the most updated information in the advancement of science and technology in nuclear thermal hydraulics, operations and safety, and provides you insights into the future. (J.P.N.)

  2. Topical session proceedings of the 5. IGSC meeting on: observations regarding the safety case in recent safety assessment studies

    International Nuclear Information System (INIS)

    Hooper, Alan J.; Voinis, Sylvie; Van Luik, Abraham E.

    2004-01-01

    Within the NEA, the IGSC (Integration Group for the Safety Case) has, as an essential role, to develop common views on such key aspects of the safety case. Therefore, since the inauguration of the IGSC in 2000, four meetings were organised with topical sessions to explore various of these key aspects. This is a report on the fifth such topical session, held as part of the 5. plenary meeting of the IGSC. The session was attended by 36 participants, representing waste management organisations and regulatory authorities from 16 NEA member countries, the IAEA and the European Commission. The purpose of this topical session was to provide support to the finalising of the IGSC safety case brochure by getting a description of the safety case content of the IAEA Draft Safety Requirements document and by getting an overview of progress that could be observed from national organisations on developing their cases for system safety and/or developing the required methodologies. The objective was that the IGSC safety case brochure should be supportive of the IAEA/NEA document, and be reflective of the experience of the IGSC member programmes and organisations. The topical session was mainly aimed at exchanging information on: - The safety case related content of the proposed IAEA/NEA document (currently titled: 'IAEA Safety Standards Series, Geological Disposal of Radioactive Waste, Draft Safety Requirements (DS-154)'). - National programmes where safety assessments have recently been completed, e.g. ONDRAF/NIRAS, Nagra and Andra. - Feedback from international peer reviews, e.g. the Andra Dossier 2001 Argile, the Belgian SAFIR 2 report, the SR 97 report and the US-DOE Yucca Mountain TSPA. - The evolution of some national assessment methods and approaches e.g. SKB and Nagra. - The content of the draft IGSC safety case brochure entitled: 'The Nature and Purpose of the Post-closure Safety Case in Geological Disposal'. This document presents the various

  3. Flu Vaccine Safety Information

    Science.gov (United States)

    ... Influenza Types Seasonal Avian Swine Variant Pandemic Other Flu Vaccine Safety Information Questions & Answers Language: English (US) ... safety of flu vaccines monitored? Egg Allergy Are flu vaccines safe? Flu vaccines have good safety record. ...

  4. Proceedings of a topical meeting on safety of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1996-01-01

    The topical meeting on the safety of the nuclear fuel cycle is composed of 17 papers grouped into four sessions which titles are: operational safety in nuclear fuel facilities; safety criteria and regulatory philosophy; plant hazard analysis and mitigation; plant experience and emergency planning

  5. 33 CFR 96.230 - What objectives must a safety management system meet?

    Science.gov (United States)

    2010-07-01

    ... management system meet? 96.230 Section 96.230 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.230 What objectives must a safety...

  6. Trends in safety pharmacology: posters presented at the annual meetings of the Safety Pharmacology Society 2001-2010.

    Science.gov (United States)

    Redfern, William S; Valentin, Jean-Pierre

    2011-01-01

    The inaugural meeting of the Safety Pharmacology Society (SPS) was in 2001, soon after ICH S7A had been adopted. The 10th anniversary is an appropriate milestone at which to analyse trends in the science and themes of safety pharmacology, as reflected in posters presented at the annual meetings. The source information was the poster abstract booklets from each of the first ten annual meetings. The number of posters rose steadily from 34 in 2001 to 201 in 2010. The proportion of posters containing in vitro data has remained constant throughout the decade at ~30%. In terms of organ functions, themes relating to the cardiovascular system (CVS) have always generated the majority of posters, remaining above 60% of the total for the last 9years. The dominant theme has been around 'QT liability'. This peaked in 2003 at 68% of all posters presented, around the time of the ICHS7B discussions, and has remained above 30% thereafter. Apart from 2003 (dipping to 4%), CNS-related posters have remained steady at 11-17% throughout the decade. Respiratory-related posters have remained at 5-8% over the last 5years. Gastrointestinal (GI)-related posters have contributed 2-6% throughout the decade, and renal-related posters 1-3%. Posters on combined organ assessments have appeared in recent years. The relative emphasis on the different organ functions is broadly proportional to the causes of candidate drug attrition preclinically, whereas both CNS and GI are under-represented when considering their contribution to significant adverse effects during clinical development. Trends are either regulatory-driven (e.g. increase in posters on abuse-dependence liability since EMEA/CHMP/SWP/94227/2004), technology-driven (e.g. automated hERG assay; left ventricular function; non-invasive CVS measurements; stem cells, etc.), or relate to the predictive ability of safety pharmacology data (e.g. clinical translation initiatives; concordance between in vitro and in vivo preclinical data; integrated

  7. Informal meeting on ITER developments

    International Nuclear Information System (INIS)

    Canobbio, E.

    2000-01-01

    The International Fusion Research Council (IFRC), advisory body of the IAEA, organized an informal meeting on the general status and outlook for ITER, held October 9 at Sorrento, Italy, in conjunction with the 18th IAEA Fusion Energy Conference. This article describes the main events at the meeting

  8. 75 FR 44998 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-07-30

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

  9. Proceedings of the U.S. Nuclear Regulatory Commission on the fifteenth water reactor safety information meeting. V. 2. Materials engineering/pressure vessel research; materials engineering/radiation and degraded piping effects; non-destructive evaluation; environmental effects in primary systems

    International Nuclear Information System (INIS)

    Weiss, Allen J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the fifteenth water reactor safety information meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included twenty-two different papers presented by researchers from Belgium, Czechoslovakia, Germany, Italy, Japan, Russia, Spain, Sweden, The Netherlands and the United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. (author)

  10. Presentations from the 1992 Coal Mining Impoundment Informational Meeting

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    On May 20 and 21, 1992, the MSHA Coal Mining Impoundment Informational Meeting was held at the National Mine Health and Safety Academy in Beckley, West Virginia. Fifteen presentations were given on key issues involved in the design and construction of dams associated with coal mining. The attendees were told that to improve the consistency among the plan reviewers, engineers from the Denver and Pittsburgh Technical Support Centers meet twice annually to discuss specific technical issues. It was soon discovered that the topics being discussed needed to be shared with anyone involved with coal waste dam design, construction, or inspection. The only way to accomplish that goal was through the issuance of Procedure Instruction Letters. The Letters present a consensus of engineering philosophy that could change over time. They do not present policy or carry the force of law. Currently, thirteen position papers have been disseminated and more will follow as the need arises. The individual paper were not even entered into the database.

  11. The Commodity Form of Safety Information

    Directory of Open Access Journals (Sweden)

    Rodrigo Finkelstein

    2015-10-01

    Full Text Available The production of safety information is deemed a vital resource to protect human lives at the work site. The injury rate, lost days, incapacity rate, and fatality rate, are key indicators to prop up labour risk awareness and identify job hazards. However, safety information gets highly distorted because it does not only measure risk but serves as a means of exchange. It determines the amount of money to be swapped between Workers’ Compensation Boards and their client corporations. Moreover, as a depository of exchange value, safety information tends to exert pressure over social reality rather than just being a passive reflection of it. This paper discloses the commodity form of safety information. Based on a political economy of information framework, it identifies, describes, and analyses the safety information commodity in its active role of organizing safety and labour health.

  12. AER Working Group D on VVER safety analysis minutes of the meeting in Rez, Czech Republic 18-20 May 1998

    International Nuclear Information System (INIS)

    Siltanen, P.

    1998-01-01

    AER Working Group D on VVER reactor safety analysis held its seventh meeting in Hotel Vltava in Rez near Prague during the period 18-20 May 1998. There were altogether 11 participants from 8 member organisations. The coordinator for the working group, Mr. P. Siltanen (IVO) served as chairman. In addition to the general information exchange on recent activities, the topics of the meeting included: First review of solutions to the 3-dimensional AER Dynamic Benchmark Problem No. 5 on a steam line break accident. This benchmark involves a break of the main steam header. Safety analysis of reactivity events. Recent code development work and fuel behaviour. Coolant mixing calculations and experiments related to diluted slugs. A list of participants and a list of handouts distributed at the meeting are attached to the minutes. (author)

  13. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  14. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  15. Providing public information in the Slovenian Nuclear Safety Administration

    International Nuclear Information System (INIS)

    Fon Jager, Mojca

    2000-01-01

    Full text: Good safety culture is strongly related to transparent and timely information. Experience has shown that radiation and nuclear safety are under continuous surveillance by the public. The provision of open and authentic information to the public is a fundamental policy of the SNSA. The SNSA endeavors to provide substantial and reliable information to the interested institutions, mass media and to the citizens through press conferences, public statements, media discussions, and active participation in domestic and international meetings, symposia and congresses, through publications, the Internet and direct contacts with the interested public. The SNSA regularly provides information on nuclear safety to the Government, the National Assembly and the citizens of the Republic of Slovenia. The Annual Report on Nuclear and Radiation Safety is published in Poroeevalec (Reporter) - the publication of the National Assembly - in autumn, and is available in public libraries throughout Slovenia. Annual Report is available also on the Internet (http://www.sigov.si/ursjv/uvod.html) in Slovene and English. Access to data of the Central Radiation Early Warning System of Slovenia (CROSS), recording the real time (at half-hour intervals) gamma dose rate levels, is also available through Internet. The report in English is sent every year to Slovenian embassies world-wide, to certain foreign embassies in Slovenia and to other organizations participating in the activities in the nuclear and radiological field. Reports on the SNSA activities are also published in the bulletin Okolje in prostor (Environment and Spatial Planning), published by the Ministry of Environment and Spatial Planning. The SNSA regularly contributes articles on courses, seminars and symposia attended at home and abroad. The articles are intended to give basic information on training and the names of contact persons to provide additional information on certain topics to those interested. More than half of

  16. 'AER working group D on VVER safety analysis' minutes of the meeting in Rossendorf, Germany, 10-12 May 1999

    International Nuclear Information System (INIS)

    Siltanen, P.

    1999-01-01

    AER Working Group D on VVER reactor safety analysis held its eighth meeting in Research Centre Rossendorf during the period 10-12 May 1999. There were altogether 14 participants from eight member organizations. In addition to the general information exchange on recent activities, the topics of the meeting included: Final conclusions and lessons from the solution of the AER Dynamic Benchmark Problem No. 5 on a main steam header break accident; Validation of dynamics codes and the definition of a 6th dynamic benchmark; Safety analyses and reactivity issues: approaches and results; Advances in development of models and codes for reactor dynamics applications; Documentation of dynamic benchmark problems and solutions for the AER Benchmark Book; Future activities. (author)

  17. Proceedings of the specialist meeting on nuclear fuel and control rods: operating experience, design evolution and safety aspects

    International Nuclear Information System (INIS)

    1997-01-01

    Design and management of nuclear fuel has undergone a strong evolution process during past years. The increase of the operating cycle length and of the discharge burnup has led to the use of more advanced fuel designs, as well as to the adoption of fuel efficient operational strategies. The analysis of recent operational experience highlighted a number of issues related to nuclear fuel and control rod events raising concerns about the safety aspects of these new designs and operational strategies, which led to the organisation of this Specialists Meeting on fuel and control rod issues. The meeting was intended to provide a forum for the exchange of information on lessons learned and safety concern related to operating experience with fuel and control rods (degradation, reliability, experience with high burnup fuel, and others). After an opening session 6 papers), this meeting was subdivided into four sessions: Operating experience and safety concern (technical session I - 6 papers), Fuel performance and operational issues (technical session II - 7 papers), Control rod issues (technical session III - 9 papers), Improvement of fuel design (technical session IV.A - 4 papers), Improvement on fuel fabrication and core management (technical session IV.B - 6 papers)

  18. Meeting the regulatory information needs of users of radioactive materials

    International Nuclear Information System (INIS)

    MacDurmon, G.W.

    1996-01-01

    The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff

  19. Meeting the regulatory information needs of users of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    MacDurmon, G.W. [American Cyanamid Company, Princeton, NJ (United States)

    1996-10-01

    The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff.

  20. 77 FR 34123 - Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines

    Science.gov (United States)

    2012-06-08

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0100] Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines AGENCY: Office of Pipeline Safety, Pipeline and Hazardous Materials Safety Administration, DOT. ACTION...

  1. National nuclear safety report 2004. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2004-01-01

    The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

  2. Extracting Information from Multimedia Meeting Collections

    OpenAIRE

    Gatica-Perez, Daniel; Zhang, Dong; Bengio, Samy

    2005-01-01

    Multimedia meeting collections, composed of unedited audio and video streams, handwritten notes, slides, and electronic documents that jointly constitute a raw record of complex human interaction processes in the workplace, have attracted interest due to the increasing feasibility of recording them in large quantities, by the opportunities for information access and retrieval applications derived from the automatic extraction of relevant meeting information, and by the challenges that the ext...

  3. 33 CFR 96.240 - What functional requirements must a safety management system meet?

    Science.gov (United States)

    2010-07-01

    ... a safety management system meet? 96.240 Section 96.240 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.240 What functional...

  4. 77 FR 65000 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-10-24

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

  5. 78 FR 30929 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2013-05-23

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

  6. Results of the 3rd Review Meeting of the Convention on Nuclear Safety and Preparatory Works for the 4th Meeting

    International Nuclear Information System (INIS)

    Choi, Young Sung; Choi, Kwang Sik; Kim, Woong Sik

    2006-01-01

    The 3 rd Review Meeting of the Convention on Nuclear Safety (CNS) took place from April 11-22, 2005. Fifty out of fifty-five Contracting Parties (CPs) participated with over 500 delegates in attendance. It was concluded that all CPs in attendance were in compliance with the requirements of the CNS. It was also noted that although the focus tends to be on the triennial national reports and review meetings, the CNS should emphasize an ongoing process that continually promotes the advancement of nuclear safety. With regard to this continuity process, the President of the 3 rd Review Meeting sent to all the CPs a message to remind of the lessons offered and learned from the Meeting and to put them into action as well. The president also asked that the CPs start in earnest later this year their preparations for the Forth Meeting in 2008. This paper introduces the results of the 3 rd Review Meeting and presents some suggestions on preparatory works that should be done for the next Review Meeting

  7. Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

  8. 77 FR 75176 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-12-19

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

  9. 28 CFR 16.205 - Closed meetings-Informal procedures.

    Science.gov (United States)

    2010-07-01

    ... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Closed meetings-Informal procedures. 16.205 Section 16.205 Judicial Administration DEPARTMENT OF JUSTICE PRODUCTION OR DISCLOSURE OF MATERIAL OR INFORMATION Public Observation of Parole Commission Meetings § 16.205 Closed meetings—Informal...

  10. 76 FR 52016 - NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-08-19

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

  11. 75 FR 17417 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-04-06

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

  12. A qualitative exploration of the perceptions and information needs of public health inspectors responsible for food safety

    Directory of Open Access Journals (Sweden)

    Sargeant Jan M

    2010-06-01

    Full Text Available Abstract Background In Ontario, local public health inspectors play an important frontline role in protecting the public from foodborne illness. This study was an in-depth exploration of public health inspectors' perceptions of the key food safety issues in public health, and their opinions and needs with regards to food safety information resources. Methods Four focus group discussions were conducted with public health inspectors from the Central West region of Ontario, Canada during June and July, 2008. A questioning route was used to standardize qualitative data collection. Audio recordings of sessions were transcribed verbatim and data-driven content analysis was performed. Results A total of 23 public health inspectors participated in four focus group discussions. Five themes emerged as key food safety issues: time-temperature abuse, inadequate handwashing, cross-contamination, the lack of food safety knowledge by food handlers and food premise operators, and the lack of food safety information and knowledge about specialty foods (i.e., foods from different cultures. In general, participants reported confidence with their current knowledge of food safety issues and foodborne pathogens. Participants highlighted the need for a central source for food safety information, access to up-to-date food safety information, resources in different languages, and additional food safety information on specialty foods. Conclusions The information gathered from these focus groups can provide a basis for the development of resources that will meet the specific needs of public health inspectors involved in protecting and promoting food safety.

  13. 78 FR 41496 - Pipeline Safety: Meetings of the Gas and Liquid Pipeline Advisory Committees

    Science.gov (United States)

    2013-07-10

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

  14. Use of probabilistic safety assessment in the regulatory process. Report of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    A Technical Committee Meeting (TCM) was organized between 5-8 December 1994 to discuss and review the international situation in connection with the use made, whether formally or informally, by regulatory bodies of probabilistic safety assessment (PSA) in the course of their work, and the related question of the use and value of adopting probabilistic safety criteria (PSC) as an aid to judging the results of PSAs. The document includes the output from the four working groups, as well as 11 papers from the 12 papers presented to the TCM. A separate abstract was prepared for each paper. Refs, figs, tabs

  15. Annual Information Meeting of the Pension Fund

    CERN Multimedia

    2014-01-01

    All members and beneficiaries of the Pension Fund are invited to attend the Annual Information Meeting.   Annual Information Meeting to be held in the CERN Council Chamber on Tuesday, 16 September 2014 from 9.00 a.m. to 10.30 a.m. Copies of the 2013 Pension Fund Financial Statements are already available in accessible PDF on the Pension Fund website and will also be distributed at this session. Coffee and croissants will be served prior to the meeting as of 8:30 a.m. N.B. Date change: 16 September 2014

  16. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 3: Thermal hydraulic research and codes; Digital instrumentation and control; Structural performance

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-04-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) thermal hydraulic research and codes; (2) digital instrumentation and control; (3) structural performance

  17. Computerized reactor protection and safety related systems in nuclear power plants. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on ''Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants'' was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international forum for the presentation and discussion on R and D, in-plant experiences in I and C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the final general discussion

  18. Meeting challenges through good practice. Using the highlights from the third review meeting of the Convention on Nuclear Safety to improve national regulatory systems

    International Nuclear Information System (INIS)

    Keen, L.J.; Cameron, J.K.

    2006-01-01

    The third review meeting of the Convention on Nuclear Safety (CNS), held in April 2005, demonstrated collective progress on ensuring worldwide nuclear safety. The Contracting Parties highlighted areas of focus to be brought back to the fourth review meeting and also committed to a continuity process to revitalize the review processes under the CNS. Specific progress has been achieved in the first year since the conclusion of the third review meeting, but further commitment to progress is required, by the Contracting Parties and the Secretariat of the IAEA, over the next year, especially if changes to the review processes are to be achieved for the fourth review meeting in 2008. (author)

  19. Improving operational safety management through probabilistic safety assessment on personal computers

    International Nuclear Information System (INIS)

    1988-10-01

    The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs

  20. 39 CFR 7.8 - Open meetings, Freedom of Information, and Privacy of Information.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Open meetings, Freedom of Information, and Privacy of Information. 7.8 Section 7.8 Postal Service UNITED STATES POSTAL SERVICE THE BOARD OF GOVERNORS OF THE U.S. POSTAL SERVICE PUBLIC OBSERVATION (ARTICLE VII) § 7.8 Open meetings, Freedom of Information, and Privacy of Information. The provisions o...

  1. AER working group D on WWER safety analysis - report of the 2007 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2007-01-01

    The AER working group D on WWER reactor safety analysis held its sixteenth meeting in Paris, France during the period 08-09 May 2007. The meeting was hosted by the CEA France. It followed the final workshop on the OECD/DOE/CEA WWER-1000 Coolant Transient Benchmark held at 07 May. Altogether 11 participants attend the meeting of the working group D, 7 from AER member organizations and 4 guests from non-member organizations. The co-ordinator of the working group, Mr. S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics: -Code development and benchmarking for reactor dynamics applications; -Safety analysis methodology and results; -Future activities. New solutions for three different benchmarks were presented and discussed. These are the Second AER Dynamic Benchmark on control rod ejection at hot zero power (S. Kliem, FZD), the WWER-1000 Coolant Transient Benchmark (E. Syrjaelahti, VTT) and the stationary AER-FCM101 Benchmark considering a WWER-1000 reactor (C. Parisi, UniPisa). A. Kereszturi (AEKI) presented a statistical evaluation of the possibility to observe a fuel assembly mis loading event. The second presentation of E. Syrjaelahti was dedicated to the description how best-estimate coupled code calculations at VTT are supported by uncertainty and sensitivity analyses. K. Velkov (GRS) presented preliminary results of BIPR8KN/ATHLET calculations with a very detailed resolution of the calculation grid on the assessment of coolant mixing inside WWER-1000 assembly heads. Coolant mixing experiments at three different mixing test facilities, modeling different reactor types, were presented and compared by S. Kliem. A calculation study using the coupled code system KORSAR/GP on the consequences of the injection of a slug of un borated water into the reactor core was

  2. 76 FR 63929 - Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and...

    Science.gov (United States)

    2011-10-14

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

  3. 75 FR 23782 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2010-05-04

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

  4. INFORMATION CULTURE AND INFORMATION SAFETY OF SCHOOLCHILDREN

    Directory of Open Access Journals (Sweden)

    E. G. Belyakova

    2017-01-01

    Full Text Available Introduction. The article is devoted to the problem of interaction between schoolchildren and possible informational risks transmitted on the Internet. Considering the lack of external filters on the way of harmful information streams, it is actually necessary to develop information culture of schoolchildren, their abilities to sensibly and critically interpret the information on the Internet, and choice of adequate behaviour models surfing the Web. The aim of the present research is to analyze the state of informational safety of schoolchildren while using the Internet; gaining an understanding of the role of external restrictions and opportunities of intrapersonal filtration of the harmful Internet content depending on children age. Methodology and research methods. The methodology of the research is based on modern methods aimed to consider the problem of personal socialization in modern information society. Thus, the Internet Initiatives Development Fund (IIDF questionnaire let the authors define the level of awareness of recipients on the problem under consideration. Results and scientific novelty. The theoretical analysis helped the authors predict the correlation of basic methods in order to guarantee personal safety of schoolchildren taking into account the process of maturity as well as the decrease of external filters that may stop harmful content. Empirical part of the research has enabled to reveal decrease in external control of staying of a child in network in the process of growing up against the background of restrictive attitudes prevalence among teachers and parents. Therefore, the research supposed to improve information culture of schoolchildren from the earliest ages encouraging them to sensibly and correctly interpret the information on the Internet. Practical significance. The practical recommendations to parents and teachers in order to improve informational personal safety of schoolchildren are proposed. The relevancy

  5. RH Department Information Meeting

    CERN Multimedia

    HR Department

    2010-01-01

    Dear Colleagues, HR Department would like to invite you to an information meeting which will be held on Thursday 30 September 2010 at 9:30 am in the Main Auditorium (Building 500)* A welcome coffee will be available from 9:00 a.m. The presentation will cover the CERN Competency Model which consists of the technical and behavioral competencies that are intrinsic to our Organization and its application in the various HR processes. This presentation will be followed by a questions & answers session. We look forward to seeing you all on 30 September! Best regards, Anne-Sylvie Catherin Head, Human Resources Department *This meeting will be simultaneously retransmitted and thereafter available at the following address: http://webcast.cern.ch.

  6. 78 FR 15976 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2013-03-13

    ... to providing the following information no less than 10 working days prior to the meeting: full name... contact Ms. Susan Burch at [email protected] or by telephone at (202) 358-0550 at least 48 hours in...) are requested to submit their name and affiliation 3 working days prior to the meeting to Crystal...

  7. Development of a check sheet for collecting information necessary for occupational safety and health activities and building relevant systems in overseas business places.

    Science.gov (United States)

    Kajiki, Shigeyuki; Kobayashi, Yuichi; Uehara, Masamichi; Nakanishi, Shigemoto; Mori, Koji

    2016-06-07

    This study aimed to develop an information gathering check sheet to efficiently collect information necessary for Japanese companies to build global occupational safety and health management systems in overseas business places. The study group consisted of 2 researchers with occupational physician careers in a foreign-affiliated company in Japan and 3 supervising occupational physicians who were engaged in occupational safety and health activities in overseas business places. After investigating information and sources of information necessary for implementing occupational safety and health activities and building relevant systems, we conducted information acquisition using an information gathering check sheet in the field, by visiting 10 regions in 5 countries (first phase). The accuracy of the information acquired and the appropriateness of the information sources were then verified in study group meetings to improve the information gathering check sheet. Next, the improved information gathering check sheet was used in another setting (3 regions in 1 country) to confirm its efficacy (second phase), and the information gathering check sheet was thereby completed. The information gathering check sheet was composed of 9 major items (basic information on the local business place, safety and health overview, safety and health systems, safety and health staff, planning/implementation/evaluation/improvement, safety and health activities, laws and administrative organs, local medical care systems and public health, and medical support for resident personnel) and 61 medium items. We relied on the following eight information sources: the internet, company (local business place and head office in Japan), embassy/consulate, ISO certification body, university or other educational institutions, and medical institutions (aimed at Japanese people or at local workers). Through multiple study group meetings and a two-phased field survey (13 regions in 6 countries), an information

  8. High committee for transparency and information on nuclear safety: meeting of April 29, 2010

    International Nuclear Information System (INIS)

    2010-01-01

    The committee members first discuss the report project concerning the State minister's and OPECST (parliamentary office of scientific and technological choices) chairman's submission regarding the transparency of the nuclear fuel cycle. They discuss the project of a portal web site gathering information on French nuclear power plant operations. They comment the 2009 ASN assessment on medical nuclear activities, the implementation of the Cancer Plan (presentation by the minister of public health, statements by the French nuclear safety authority or ASN, the French institute for radiation protection and nuclear safety or IRSN, and by associations of patients). They discuss the presentation by the ASN of a return on experience after the ATPu event and the presentation by the IRSN of technical form on the criticality risk. Other topics are addressed: extensions of storage sites under construction in La Hague, modification of the Grenelle II bill to improve public consultation in some procedures regarding base nuclear installations

  9. 40 CFR 68.65 - Process safety information.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 3 Prevention Program § 68.65 Process safety... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Process safety information. 68.65... compilation of written process safety information before conducting any process hazard analysis required by...

  10. Analysis and design on airport safety information management system

    Directory of Open Access Journals (Sweden)

    Yan Lin

    2017-01-01

    Full Text Available Airport safety information management system is the foundation of implementing safety operation, risk control, safety performance monitor, and safety management decision for the airport. The paper puts forward the architecture of airport safety information management system based on B/S model, focuses on safety information processing flow, designs the functional modules and proposes the supporting conditions for system operation. The system construction is helpful to perfecting the long effect mechanism driven by safety information, continually increasing airport safety management level and control proficiency.

  11. EPR meets the next generation PWR safety requirements

    International Nuclear Information System (INIS)

    Bouteille, Francois; Czech, Juergen; Sloan, Sandra

    2006-01-01

    At the origin was the common decision in 1989 of Framatome and Siemens to cooperate to design a Nuclear Island which meets the future needs of utilities. EDF and a group of main German Utilities joined this effort in 1991 and from that point were completely involved in the progress of the work. Compliance of the EPR with the European Utility Requirements (EUR) was verified to ensure a large acceptability of the design by other participating utilities. In addition, the entire process was backed up to the end of 1998 by the French and the German Safety Authorities which engaged into a long-lasting cooperation to define common requirements applicable to future Nuclear Power Plants. Upon signature of the Olkiluoto 3 contract, STUK, the Finnish safety and radiation authority, began reviewing the design of the EPR. Upon the favorable recommendation of STUK, the Finnish government delivered a Construction License for the Olkiluoto 3 NPP on February 17, 2005. Following the positive conclusion of the political debate in France with regard to nuclear energy, EDF will also submit a request to start the construction of an EPR on the Flamanville site. In the US, the first steps in view of a Design Certification by the NRC have been taken. These three independent decisions make the EPR the leading first generation 3+ design under construction. Important safety functions are assured by separate systems in a straightforward operating mode. Four separate, redundant trains for all safety systems are installed in four separate layout division for which a strict separation is ensured so that common mode failure, for example due to internal hazards, can be ruled out. A reduction in common mode failure potential is also obtained by design rules ensuring the systematic application of functional diversity. A four train-redundancy for the major safety systems provides flexibility in adapting the design to maintenance requirements, thus contributing to reduce the outage duration. Additional

  12. National Nuclear Safety Report 2001. Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    2001-01-01

    The First National Nuclear Safety Report was presented at the first review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This second National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the first review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex 1. In general, the information contained in this Report has been updated since March 31, 1998 to March 31, 2001. Those aspects that remain unchanged were not addressed in this second report with the objective of avoiding repetitions and in order to carry out a detailed analysis considering article by article. As a result of the above mentioned detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention

  13. Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

  14. 49 CFR 211.61 - Informal safety inquiries.

    Science.gov (United States)

    2010-10-01

    ... information on selected topics relating to railroad safety. A notice of each such inquiry will be published in... 49 Transportation 4 2010-10-01 2010-10-01 false Informal safety inquiries. 211.61 Section 211.61..., DEPARTMENT OF TRANSPORTATION RULES OF PRACTICE Miscellaneous Safety-Related Proceedings and Inquiries § 211...

  15. Proceedings of 2nd PHWR operating safety experience meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-04-01

    Papers presented during the eight sessions of the meeting were devoted to the impact of PHWR operating experience on design of civil structures (reactor building integrity); operating experiences related to pressure tubes, nuclear steam supply system, plant stability; reactor maintenance and control systems, reactor operational safety. Some events concerned with reactor shutdown due to power failures are described, as well as action undertaken to prevent major damage.

  16. Proceedings of 2nd PHWR operating safety experience meeting

    International Nuclear Information System (INIS)

    1991-04-01

    Papers presented during the eight sessions of the meeting were devoted to the impact of PHWR operating experience on design of civil structures (reactor building integrity); operating experiences related to pressure tubes, nuclear steam supply system, plant stability; reactor maintenance and control systems, reactor operational safety. Some events concerned with reactor shutdown due to power failures are described, as well as action undertaken to prevent major damage

  17. INFOTECH `92: DOE Technical Information (TI) Meeting, October 21--23, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Blanton, J.M.

    1992-10-01

    This proceedings contains papers presented at the 1992 Department of Energy (DOE) Technical Information Meeting held at the Office of Scientific and Technical Information (OSTI), Oak Ridge, Tennessee, October 21--23, 1992. It is composed of written presentation given orally at the meeting in either large-group or break-out sessions. The proceedings is provided as a reference tool for those who attended the meeting as well as an information document for those unable to attend. The annual DOE Technical Information meeting is designed for information professionals involved in the management of the Department`s scientific and technical information (STI). Speakers include members of the OSTI staff as well as DOE and DOE contractors and other invited specialists in the field of information. The major objective of the meeting is to provide a forum within the Department for discussing current and future information policies, trends, and management techniques as well as the technologies and standards available for managing and accessing scientific and technical information.

  18. Convention on nuclear safety 2012 extra ordinary meeting. The Swedish National Report

    International Nuclear Information System (INIS)

    2012-01-01

    During the 5th Review Meeting of the Convention on Nuclear Safety (CNS), the Contracting Parties in attendance agreed to hold an Extraordinary Meeting in August 2012 with the aim to enhance safety through reviewing and sharing lessons learned and actions taken by Contracting Parties in response to events at TEPCO Fukushima Dai-ichi. It was agreed that a brief and concise National Report should be developed by each Contracting Party to support the Extraordinary Meeting. This report should be submitted three months prior to the meeting to the Secretariat via the Convention-secured website for peer review by other Contracting Parties. It was also agreed that the Contracting Parties should organize their reports by topics that cross the boundaries of multiple CNS Articles. Each National Report should provide specific information on these topics to address the lessons learned and activities undertaken by each Contracting Party. The National Report should include a description of the activities the Contracting Party has completed and any activities it intends to complete along with scheduled completion dates. The present report is therefore structured in accordance with the guidance given by the General Committee for CNS. In Chapter 0, a brief description of Swedish nuclear power plants is given with an emphasis on measures that have been taken gradually as a result of new knowledge and experience. The following chapters deal with the six topics, which are: 1) External events, 2) Design issues, 3) Severe accident management and recovery, 4) National organizations, 5) Emergency preparedness and response and post-accident management, and 6) International cooperation. Each chapter concludes with a table illustrating a high-level summary of the items identified. To clarify the relationship between the text and table contained in each chapter, the parts of the text appearing in the table are underlined. Furthermore, the text of some sections/subsections in different chapters

  19. Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

    International Nuclear Information System (INIS)

    1998-01-01

    The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

  20. 75 FR 57103 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-09-17

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

  1. 75 FR 60163 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-09-29

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

  2. Safety Case Development as an Information Modelling Problem

    Science.gov (United States)

    Lewis, Robert

    This paper considers the benefits from applying information modelling as the basis for creating an electronically-based safety case. It highlights the current difficulties of developing and managing large document-based safety cases for complex systems such as those found in Air Traffic Control systems. After a review of current tools and related literature on this subject, the paper proceeds to examine the many relationships between entities that can exist within a large safety case. The paper considers the benefits to both safety case writers and readers from the future development of an ideal safety case tool that is able to exploit these information models. The paper also introduces the idea that the safety case has formal relationships between entities that directly support the safety case argument using a methodology such as GSN, and informal relationships that provide links to direct and backing evidence and to supporting information.

  3. 76 FR 26316 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-05-06

    ... following information no less than 10 working days prior to the meeting: Full name; gender; date/place of.... Susan Burch at [email protected] or by telephone at (202) 358-0550 at least 48 hours in advance. Any... can provide identifying information 3 working days in advance [[Page 26317

  4. Discussion about risk-informed regulations on the nuclear safety

    International Nuclear Information System (INIS)

    Gu Yeyi

    2008-01-01

    The article introduces the background and status quo of regulations on the nuclear safety in China, and points out the inadequacies existing with the current regulations. The author explains the risk-informed safety management concerning its development, status quo, and achievements made, in an attempt to make out the trend of improving regulations on the nuclear safety through risk-informed methods. Combining the U.S. development program of establishing risk-informed regulations on the nuclear safety, the author narrates principles and features of the new regulations system, and provides suggestions for the promotion of risk-informed safety management and establishment of risk-informed regulations on the nuclear safety. (author)

  5. Specialized meeting on 'Current topics of reactor safety research in Germany'

    International Nuclear Information System (INIS)

    Kruessenberg, Anne

    2013-01-01

    On October 11 and 12, 2012, the 2-day specialized meeting organized by the Thermodynamics and Fluid Dynamics Group together with the Dresden-Rossendorf Helmholtz Center and TUeV NORD SysTec GmbH and Co.KG was held at the Dresden-Rossendorf Helmholtz Center within the series of events on 'Current Topics of Safety Research in Germany.' The program of lectures was supplemented by poster presentations and exhibitions by the members of the joint research groups and companies working in the fields. The meeting again was very well attended by over 100 persons. (orig.)

  6. State Traffic Safety Information

    Data.gov (United States)

    Department of Transportation — The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic...

  7. High Committee for transparency and information on nuclear safety: Annual activity report (January 2010 - December 2010)

    International Nuclear Information System (INIS)

    2010-01-01

    After a description of the operation of the French 'High Committee for transparency and information on nuclear safety' (HCTISN), of its missions, its organisation and its means, the progress report presents the High Committee activity for 2010 with summaries of its report on the transparency of nuclear material and waste management, its meetings, its work groups, its visits and participations to other events

  8. Safety culture in nuclear installations: Summary of an international topical meeting

    International Nuclear Information System (INIS)

    Carnino, A.; Derrough, M.; Weimann, G.

    1996-01-01

    An international topical meeting, Safety Culture in Nuclear Installations, was organized by the American Nuclear Society (ANS) Austria Local Section, cosponsored by the ANS Nuclear Reactor Safety and Human Factors Divisions in cooperation with the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA/OECD) and held in Vienna April 24-28, 1995. Some 250 experts from 30 different countries and organizations took part in the 85 paper presentations and two workshops. The concept of safety culture was initially used in the first International Nuclear Safety Advisory Group (INSAG) report on the Chernobyl accident analysis report in 1986. Although some elements of safety culture have been used over the years in nuclear safety activities, the new phrase safety culture and the concept were found interesting as highlighting the 'soft' aspects of safety and as encompassing more than human errors. Unfortunately, for many years it was used more in the way of identifying lack of safety culture. Conscious of this application, INSAG further developed the safety culture concept in the INSAG 4 report: The report contains a definition, the universal aspects of safety culture, the two main components of safety culture management and individual behaviour, and performance indicators of a good safety culture. This report is now quite famous and adopted with some additions or complementary definitions by many institutes and organizations for their daily activities

  9. Waste Isolation Safety Assessment Program. Task 4. Third Contractor Information Meeting

    International Nuclear Information System (INIS)

    1980-06-01

    The study subject of this meeting was the adsorption and desorption of radionuclides on geologic media under repository conditions. This volume contans eight papers. Separate abstracts were prepared for all eight papers

  10. Issues relating to safety standards on the geological disposal of radioactive waste. Proceedings of a specialists meeting

    International Nuclear Information System (INIS)

    2002-06-01

    Within the International Atomic Energy Agency focus is currently being placed on establishing safety standards for the geological disposal of radioactive waste. This is a challenging task and a Specialists Meeting was held from 18 to 22 June 2001 with the intention of providing a mechanism for promoting discussion on some of the associated scientific and technical issues and as a means of developing the consensus needed for establishing the standards. The meeting used, as its basis, a number of position papers developed in recent years with the help of a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, together with selected relevant regional and national papers. The report contains the summaries of the sessions of the Specialists Meeting together with the conclusions drawn relevant to the establishment of standards. The sessions of the Meeting addressed the following topics: Common framework for radioactive waste disposal; Making the safety case - demonstrating compliance; Safety indicators; Reference critical groups and biospheres; Human intrusion; Reversibility and retrievability; Monitoring and institutional control. The publication contains 26 individual presentations delivered by participants. Each of these presentations was indexed separately

  11. 75 FR 19662 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-04-15

    ... in addition to providing the following information no less than 10 working days prior to the meeting... least 48 hours in advance. Any member of the public is permitted to file a written statement with the..., attendees with U.S. citizenship can provide identifying information 3 working days in advance by contacting...

  12. 77 FR 1955 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-01-12

    ... the following information no less than 10 working days prior to the meeting: full name; gender; [email protected] or by telephone at (202) 358-0550 at least 48 hours in advance. Any member of the public... can provide identifying information 3 working days in advance by contacting Susan Burch via email at...

  13. 78 FR 78362 - National Institute for Occupational Safety and Health Personal; Notice of public meeting in...

    Science.gov (United States)

    2013-12-26

    ... Institute for Occupational Safety and Health Personal; Notice of public meeting in Endicott, New York AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease Control.... SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease...

  14. International exchange of safety and licensing information

    International Nuclear Information System (INIS)

    Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

    1977-01-01

    A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the US Nuclear Regulatory Commission. For developing countries such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that USNRC has accumulated. USNRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the USNRC is in providing for reciprocal communication, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly discovered problem in a nuclear reactor be brought immediately to the attention of other governments that are responsible for the safety of similar reactors. Definite progress has been made in the USA in defining categories of information that USNRC can receive in confidence from foreign countries, and can protect from disclosure under the US Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of USNRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of a country building its first power reactor is described. (author)

  15. Annual Information Meeting of the Pension Fund

    CERN Multimedia

    2013-01-01

    All members and beneficiaries of the Pension Fund are invited to attend the   Annual Information Meeting to be held in the CERN Council Chamber on  Wednesday, 11 September 2013 from 10.00 a.m. to 12.00 midday. Copies of the 2012 Pension Fund Financial Statements can be obtained from departmental secretariats and will also be available at the meeting.

  16. 78 FR 70623 - Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory...

    Science.gov (United States)

    2013-11-26

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

  17. International exchange of safety and licensing information

    International Nuclear Information System (INIS)

    Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

    1977-01-01

    A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the U.S. Nuclear Regulatory Commission. For developing countries, such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that NRC has accumulated. NRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the NRC is in providing for reciprocal communicaion, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly-discovered problem in a nuclear reactor be brought immediately to the attention of other governments which are responsible for the safety of similar reactors. Definite progress has been made in the U.S. Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of NRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of country building its first power reactor is described

  18. Activation Analysis. Proceedings of an Informal Study Group Meeting

    International Nuclear Information System (INIS)

    1971-01-01

    As part of its programme to promote the exchange of information relating to nuclear science and technology, the International Atomic Energy Agency convened in Bangkok, Thailand, from 6-8 July 1970, an informal meeting to discuss the topic of Activation Analysis. The meeting was attended by participants drawn from the following countries: Australia, Burma, Ceylon, Republic of China, India, Indonesia, Prance, Japan, Republic of Korea, New Zealand, Philippines, Singapore, Thailand, United States of America and Vietnam. The proceedings consist of the contributions presented at the meeting with minor editorial changes

  19. Activation Analysis. Proceedings of an Informal Study Group Meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-07-01

    As part of its programme to promote the exchange of information relating to nuclear science and technology, the International Atomic Energy Agency convened in Bangkok, Thailand, from 6-8 July 1970, an informal meeting to discuss the topic of Activation Analysis. The meeting was attended by participants drawn from the following countries: Australia, Burma, Ceylon, Republic of China, India, Indonesia, Prance, Japan, Republic of Korea, New Zealand, Philippines, Singapore, Thailand, United States of America and Vietnam. The proceedings consist of the contributions presented at the meeting with minor editorial changes.

  20. Meetings of all the contracting parties of agreements on Nuclear Safety of the IAEA

    International Nuclear Information System (INIS)

    Ripoll Carulla, S.

    2003-01-01

    One of the most original aspects at the Convention on Nuclear Safety was the incorporation of the mechanism for Meetings with Contracting States into Chapter III. This mechanism has become one of the most characteristic elements at the convention, which is usually defined as a motivational convention, due in large part to the actual existence of these meetings. (Author)

  1. 76 FR 36937 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-06-23

    ... information no less than 10 working days prior to the meeting: full name; gender; date/place of birth... by telephone at (202) 358-0550 at least 48 hours in advance. Any member of the public is permitted to... identifying information 3 working days in advance by contacting Crystal McCrimmon at 301-286-6296 or email...

  2. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors

  3. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [Brookhaven National Lab., Upton, NY (United States)] [comp.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

  4. Enabling social listening for cardiac safety monitoring: Proceedings from a drug information association-cardiac safety research consortium cosponsored think tank.

    Science.gov (United States)

    Seifert, Harry A; Malik, Raleigh E; Bhattacharya, Mondira; Campbell, Kevin R; Okun, Sally; Pierce, Carrie; Terkowitz, Jeffrey; Turner, J Rick; Krucoff, Mitchell W; Powell, Gregory E

    2017-12-01

    This white paper provides a summary of the presentations and discussions from a think tank on "Enabling Social Listening for Cardiac Safety Monitoring" trials that was cosponsored by the Drug Information Association and the Cardiac Safety Research Consortium, and held at the White Oak headquarters of the US Food and Drug Administration on June 3, 2016. The meeting's goals were to explore current methods of collecting and evaluating social listening data and to consider their applicability to cardiac safety surveillance. Social listening is defined as the act of monitoring public postings on the Internet. It has several theoretical advantages for drug and device safety. First, these include the ability to detect adverse events that are "missed" by traditional sources and the ability to detect adverse events sooner than would be allowed by traditional sources, both by affording near-real-time access to data from culturally and geographically diverse sources. Social listening can also potentially introduce a novel patient voice into the conversation about drug safety, which could uniquely augment understanding of real-world medication use obtained from more traditional methodologies. Finally, it can allow for access to information about drug misuse and diversion. To date, the latter 2 of these have been realized. Although regulators from the Food and Drug Administration and the United Kingdom's Medicines and Healthcare Products Regulatory Agency participated in the think tank along with representatives from industry, academia, and patient groups, this article should not be construed to constitute regulatory guidance. Copyright © 2017 Elsevier Inc. All rights reserved.

  5. Proceedings of the Eleventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation

    International Nuclear Information System (INIS)

    2012-01-01

    Partitioning and transmutation (P and T) is one of the key technologies for reducing the radiotoxicity and volume of radioactive waste arisings. Recent developments indicate the need for embedding P and T strategies in advanced fuel cycles considering both waste management and economic issues. In order to provide experts a forum to present and discuss state-of-the-art developments in the P and T field, the OECD/NEA has been organising biennial information exchange meetings on actinide and fission product partitioning and transmutation since 1990. The previous meetings were held in Mito (Japan) in 1990, at Argonne (United States) in 1992, in Cadarache (France) in 1994, in Mito (Japan) in 1996, in Mol (Belgium) in 1998, in Madrid (Spain) in 2000, in Jeju (Korea) in 2002, in Las Vegas (United States) in 2004, in Nimes (France) in 2006 and in Mito (Japan) in 2008. They have often been co-sponsored by the European Commission (EC) and the International Atomic Energy Agency (IAEA). The 11. Information Exchange Meeting was held in San Francisco, California, United States on 1-4 November 2010, comprising a plenary session on national P and T programmes and six technical sessions covering various fields of P and T. The meeting was hosted by the Idaho National Laboratory (INL), United States. The information exchange meetings on P and T form an integral part of NEA activities on advanced nuclear fuel cycles. The meeting covered scientific as well as strategic/policy developments in the field of P and T, such as: fuel cycle strategies and transition scenarios; radioactive waste forms; the impact of P and T on geological disposal; radioactive waste management strategies (including secondary wastes); transmutation fuels and targets; pyro and aqueous separation processes; materials, spallation targets and coolants; transmutation physics, experiments and nuclear data; transmutation systems (design, performance and safety); handling and transportation of transmutation fuels; and

  6. Annual Information Meeting of the Pension Fund | 26 October

    CERN Multimedia

    2016-01-01

    All members and beneficiaries of the Pension Fund are invited to attend the Annual Information Meeting of the Pension Fund.   Meeting to be held in the Main Auditorium on Wednesday 26 October 2016 from 9:30 a.m. to 11:30 a.m. Following a presentation by the Chief Executive Officer of the Fund there will be a Questions and Answers session. Members and Beneficiaries are welcome to send questions in advance of the meeting by post to: Mr Matthew Eyton-Jones “Annual Information Meeting” CEO CERN Pension Fund Office 5-5-012, Postbox C23800 CH- 1211 Geneva 23 - Switzerland Copies of the 2015 Pension Fund Annual Report & Financial Statements are already available in accessible PDF on the Pension Fund website and will also be distributed at the annual meeting. *Coffee and croissants will be served prior to the meeting as of 9:00 a.m.*

  7. Evaluating the horizontal alignment of safety management activities through cross-reference of data from safety audits, meetings and investigations

    NARCIS (Netherlands)

    Karanikas, Nektarios

    2017-01-01

    Vertical and horizontal alignment within organizations are seen as prerequisites for meeting strategic objectives and indications of effective management. In the area of safety management, the concept of vertical alignment has been followed through the introduction of hierarchical structures and

  8. Information Flow for Timed Automata

    DEFF Research Database (Denmark)

    Nielson, Flemming; Nielson, Hanne Riis; Vasilikos, Panagiotis

    2017-01-01

    One of the key demands of cyberphysical systems is that they meet their safety goals. Timed Automata has established itself as a formalism for modelling and analysing the real-time safety aspects of cyberphysical systems. Increasingly it is also demanded that cyberphysical systems meet a number o...... of security goals for confidentiality and integrity. Information Flow Control is an approach to ensuring that there are no flows of information that violate the stated security policy....

  9. 77 FR 38092 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting

    Science.gov (United States)

    2012-06-26

    .... The meeting will be held for the purpose of soliciting from the information technology community and... NAC Information Technology Infrastructure Committee meeting in Building 28. All U.S. citizens and... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-048] NASA Advisory Council; Information...

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

    International Nuclear Information System (INIS)

    2009-03-01

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

  11. Proceedings of the Specialist Meeting on the Seismic Probabilistic Safety Assessment of Nuclear Facilities

    International Nuclear Information System (INIS)

    2007-01-01

    The main objectives of the Meeting were to review recent advances in the methodology of Seismic Probabilistic Safety Assessment (SPSA), to discuss practical applications, to review the current state of the art, and to identify methodological issues where further research would be beneficial in enhancing the usefulness of the methodology. Applications of the Seismic Margin Assessment methodology (SMA), a methodology related to SPSA, were also discussed. One specific objective was to compare the situation today with the situation at the time of the 1999 Tokyo workshop, and to develop a set of findings and recommendations that would update those from that earlier workshop. There was a consensus at the Specialists Meeting that SPSA is now in widespread use throughout the nuclear-power industry worldwide, by the operating nuclear power plants (NPPs) themselves, by the various national regulatory agencies, and by the designers of new NPPs. It was also widely agreed that it can systematically accomplish several very important objectives; specifically, it can contribute: - To understanding the seismic risk arising from NPPs. - To understanding the safety significance of seismic design shortfalls. - To prioritizing seismic safety improvements. - To evaluating and improving seismic regulations. - To modifying the seismic regulatory/licensing basis of an individual NPP. Compared to the situation in 1999, when the first Workshop was held in Tokyo, there have been significant expansions in the use of SPSA in many different areas. Some countries provided detailed information on their regulatory framework for using seismic PSA. Many other countries also provided some information in their papers as background for conducting SPSA. During the Meeting, a small number of important weaknesses in SPSA methodology were identified. None of these are new, all having been widely recognized for many years. However, for some of the weaknesses, extensive discussions during the Meeting provided

  12. Proceedings of the Specialist Meeting on the Seismic Probabilistic Safety Assessment of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-14

    The main objectives of the Meeting were to review recent advances in the methodology of Seismic Probabilistic Safety Assessment (SPSA), to discuss practical applications, to review the current state of the art, and to identify methodological issues where further research would be beneficial in enhancing the usefulness of the methodology. Applications of the Seismic Margin Assessment methodology (SMA), a methodology related to SPSA, were also discussed. One specific objective was to compare the situation today with the situation at the time of the 1999 Tokyo workshop, and to develop a set of findings and recommendations that would update those from that earlier workshop. There was a consensus at the Specialists Meeting that SPSA is now in widespread use throughout the nuclear-power industry worldwide, by the operating nuclear power plants (NPPs) themselves, by the various national regulatory agencies, and by the designers of new NPPs. It was also widely agreed that it can systematically accomplish several very important objectives; specifically, it can contribute: - To understanding the seismic risk arising from NPPs. - To understanding the safety significance of seismic design shortfalls. - To prioritizing seismic safety improvements. - To evaluating and improving seismic regulations. - To modifying the seismic regulatory/licensing basis of an individual NPP. Compared to the situation in 1999, when the first Workshop was held in Tokyo, there have been significant expansions in the use of SPSA in many different areas. Some countries provided detailed information on their regulatory framework for using seismic PSA. Many other countries also provided some information in their papers as background for conducting SPSA. During the Meeting, a small number of important weaknesses in SPSA methodology were identified. None of these are new, all having been widely recognized for many years. However, for some of the weaknesses, extensive discussions during the Meeting provided

  13. 75 FR 67805 - The Future of Aviation Advisory Committee (FAAC) Subcommittee on Aviation Safety; Notice of Meeting

    Science.gov (United States)

    2010-11-03

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

  14. The impact of health information technology on patient safety

    Directory of Open Access Journals (Sweden)

    Yasser K. Alotaibi

    2017-12-01

    Full Text Available Since the original Institute of Medicine (IOM report was published there has been an accelerated development and adoption of health information technology with varying degrees of evidence about the impact of health information technology on patient safety. This article is intended to review the current available scientific evidence on the impact of different health information technologies on improving patient safety outcomes. We conclude that health information technology improves patient’s safety by reducing medication errors, reducing adverse drug reactions, and improving compliance to practice guidelines. There should be no doubt that health information technology is an important tool for improving healthcare quality and safety. Healthcare organizations need to be selective in which technology to invest in, as literature shows that some technologies have limited evidence in improving patient safety outcomes.

  15. The impact of health information technology on patient safety.

    Science.gov (United States)

    Alotaibi, Yasser K; Federico, Frank

    2017-12-01

    Since the original Institute of Medicine (IOM) report was published there has been an accelerated development and adoption of health information technology with varying degrees of evidence about the impact of health information technology on patient safety.  This article is intended to review the current available scientific evidence on the impact of different health information technologies on improving patient safety outcomes. We conclude that health information technology improves patient's safety by reducing medication errors, reducing adverse drug reactions, and improving compliance to practice guidelines. There should be no doubt that health information technology is an important tool for improving healthcare quality and safety. Healthcare organizations need to be selective in which technology to invest in, as literature shows that some technologies have limited evidence in improving patient safety outcomes.

  16. 75 FR 50774 - Towing Safety Advisory Committee; Meetings

    Science.gov (United States)

    2010-08-17

    ... electronically on or before August 24, 2010. ADDRESSES: The meetings will be held at the Doubletree Hotel and...). Information on and directions to the Doubletree Hotel and Suites may be found on its Web site at http://www...

  17. 77 FR 67028 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting

    Science.gov (United States)

    2012-11-08

    .... SUPPLEMENTARY INFORMATION: The agenda topics for the meeting will include: Information Technology--The Effects... Center Chandra/X-Ray Astronomy Mobile Applications Wide Area Networks The meeting will be open to the....S. visa information to include type, number, and expiration date, U.S. Social Security Number (if...

  18. Report of a consultants meeting on accidents during shutdown conditions for WWER nuclear power plants. Extrabudgetary programme on the safety of WWER NPPs

    International Nuclear Information System (INIS)

    1996-07-01

    The main objectives of the meeting were to exchange information on the operational occurrences, studies performed and countermeasures taken for the accidents during shutdown for WWERs, and to define the necessity and directions of the further activities which may promote the improvement of WWER safety under shutdown conditions. The consultants have discussed some aspects concerning vulnerability of safety functions during shutdown conditions, several steps required to performed accident analysis and selected operational aspects for shutdown conditions. The discussion was supported by an evaluation of selected operational occurrences. The consultants have agreed that the discussion during the meeting in major parts is relevant to all the WWER designs (i.e. WWER-1000, WWER-440/213 and WWER-440/230). As for the plant conditions, the consultants have agreed to bound the discussion mainly by the cold shutdown and refuelling modes. Refs, figs, tabs

  19. Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

    International Nuclear Information System (INIS)

    McMahon, T.T.; Sievers, R.H.

    1991-09-01

    Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

  20. 78 FR 7460 - Stakeholder Meeting on the Nationally Recognized Testing Laboratory Program

    Science.gov (United States)

    2013-02-01

    ...] Stakeholder Meeting on the Nationally Recognized Testing Laboratory Program AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of stakeholder meeting. SUMMARY: OSHA invites interested parties to attend an informal stakeholder meeting concerning Nationally Recognized Testing...

  1. Mass-media information campaigns about road safety. [previously known as: Public information about road safety.

    NARCIS (Netherlands)

    2009-01-01

    In the Netherlands, public information is often used as an instrument to improve road safety. The purpose of each public information campaign is a voluntary and lasting change in traffic behaviour. This requires road users to have sufficient knowledge about a problem and to adapt their behaviour.

  2. Patient safety goals for the proposed Federal Health Information Technology Safety Center.

    Science.gov (United States)

    Sittig, Dean F; Classen, David C; Singh, Hardeep

    2015-03-01

    The Office of the National Coordinator for Health Information Technology is expected to oversee creation of a Health Information Technology (HIT) Safety Center. While its functions are still being defined, the center is envisioned as a public-private entity focusing on promotion of HIT related patient safety. We propose that the HIT Safety Center leverages its unique position to work with key administrative and policy stakeholders, healthcare organizations (HCOs), and HIT vendors to achieve four goals: (1) facilitate creation of a nationwide 'post-marketing' surveillance system to monitor HIT related safety events; (2) develop methods and governance structures to support investigation of major HIT related safety events; (3) create the infrastructure and methods needed to carry out random assessments of HIT related safety in complex HCOs; and (4) advocate for HIT safety with government and private entities. The convening ability of a federally supported HIT Safety Center could be critically important to our transformation to a safe and effective HIT enabled healthcare system. © The Author 2014. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  3. Aviation Safety Hotline Information System -

    Data.gov (United States)

    Department of Transportation — The Aviation Safety Hotline Information System (ASHIS) collects, stores, and retrieves reports submitted by pilots, mechanics, cabin crew, passengers, or the public...

  4. 77 FR 72431 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-12-05

    ... other IMO bodies --Global Maritime Distress and Safety System (GMDSS): --Review and modernization of the... operational and technical coordination provisions of maritime safety information (MSI) services, including the... business --Report to the Maritime Safety Committee Members of the public may attend this meeting up to the...

  5. A Network Diffusion Model of Food Safety Scare Behavior considering Information Transparency

    Directory of Open Access Journals (Sweden)

    Tingqiang Chen

    2017-01-01

    Full Text Available This study constructs the network diffusion model of food safety scare behavior under the effect of information transparency and examines the network topology and evolution characteristics of food safety scare behavior in a numerical simulation. The main conclusions of this study are as follows. (1 Under the effect of information transparency, the network degree distribution of food safety scare behavior diffusion demonstrates the decreasing characteristics of diminishing margins. (2 Food safety scare behavior diffusion increases with the information dissemination rate and consumer concern about food safety incidents and shows the characteristics of monotone increasing. And with the increasing of the government food safety supervision information transparency and media food safety supervision information transparency, the whole is declining characteristic of diminishing marginal. In addition, the extinction of food safety scare behavior cannot be achieved gradually given a single regulation of government food safety supervision information transparency and media food safety supervision information transparency. (3 The interaction effects between improving government food safety supervision information transparency or media food safety supervision information transparency and declining consumer concerns about food safety incidents or information transmission rate can engender the suppression of food safety scare behavior diffusion.

  6. Computer aided safety analysis 1989

    International Nuclear Information System (INIS)

    1990-04-01

    The meeting was conducted in a workshop style, to encourage involvement of all participants during the discussions. Forty-five (45) experts from 19 countries, plus 22 experts from the GDR participated in the meeting. A list of participants can be found at the end of this volume. Forty-two (42) papers were presented and discussed during the meeting. Additionally an open discussion was held on the possible directions of the IAEA programme on Computer Aided Safety Analysis. A summary of the conclusions of these discussions is presented in the publication. The remainder of this proceedings volume comprises the transcript of selected technical papers (22) presented in the meeting. It is the intention of the IAEA that the publication of these proceedings will extend the benefits of the discussions held during the meeting to a larger audience throughout the world. The Technical Committee/Workshop on Computer Aided Safety Analysis was organized by the IAEA in cooperation with the National Board for Safety and Radiological Protection (SAAS) of the German Democratic Republic in Berlin. The purpose of the meeting was to provide an opportunity for discussions on experiences in the use of computer codes used for safety analysis of nuclear power plants. In particular it was intended to provide a forum for exchange of information among experts using computer codes for safety analysis under the Technical Cooperation Programme on Safety of WWER Type Reactors (RER/9/004) and other experts throughout the world. A separate abstract was prepared for each of the 22 selected papers. Refs, figs tabs and pictures

  7. France - Convention on Nuclear Safety. Sixth National report for the 2014 review meeting

    International Nuclear Information System (INIS)

    2013-07-01

    The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 in order to contribute to maintaining a high level of nuclear safety worldwide. The convention sets a number of nuclear safety objectives and defines measures to meet them. France signed the Convention on 20 September 1994, the date on which it was opened for signature during the IAEA General Conference, and approved it on 13 September 1995. The Convention entered into force on 24 October 1996. For many years France has been participating actively in international initiatives to enhance nuclear safety. It considers the Convention on Nuclear Safety to be an important instrument for achieving this aim. The areas covered by the Convention have long been part of the French approach to nuclear safety. The purpose of this sixth report, which was drafted pursuant to Article 5 of the Convention and which covers the period 2010 to mid-2013, is to present the measures taken by France in order to fulfil each of its obligations as specified in the said Convention. Since the Convention applies to all nuclear-power generating reactors most of this report is dedicated to the measures taken in order to ensure their safety. However, as in previous reports, France has decided in this sixth report also to present the measures that were taken for all research reactors. First of all, research reactors are actually subject to the same overall regulations as nuclear-power reactors with regard to safety and radiation protection. Then, within the framework of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, to which France is a Contracting Party, an account was made of the measures taken in those respective fields with regard to research reactors. Lastly, the Board of Governors of the International Atomic Energy Agency (IAEA), of which France is a member, in March 2004 approved the Code

  8. 78 FR 23899 - Codex Alimentarius Commission: Meeting of the Codex Alimentarius Commission

    Science.gov (United States)

    2013-04-23

    ... information to regulations, directives, and notices. Customers can add or delete subscriptions themselves, and... meeting on June 18, 2013. The objective of the public meeting is to provide information and receive public... Rome, Italy. The Under Secretary for Food Safety recognizes the importance of providing interested...

  9. Improving plant state information for better operational safety

    International Nuclear Information System (INIS)

    Girard, C.; Olivier, E.; Grimaldi, X.

    1994-01-01

    Nuclear Power Plant (NPP) safety is strongly dependent on components' reliability and particularly on plant state information reliability. This information, used by the plant operators in order to produce appropriate actions, have to be of a high degree of confidence, especially in accidental conditions where safety is threatened. In this perspective, FRAMATOME, EDF and CEA have started a joint research program to prospect different solutions aiming at a better reliability for critical information needed to safety operate the plant. This paper gives the main results of this program and describes the developments that have been made in order to assess reliability of different information systems used in a Nuclear Power Plant. (Author)

  10. 77 FR 13172 - Occupational Information Development Advisory Panel Meeting

    Science.gov (United States)

    2012-03-05

    ... SOCIAL SECURITY ADMINISTRATION [Docket No. SSA-2012-0017] Occupational Information Development Advisory Panel Meeting AGENCY: Social Security Administration (SSA). ACTION: Notice of Upcoming Quarterly Panel Meeting. DATES: March 22, 2012, 8:30 a.m.-3:30 p.m. (EDT). Location: Pier 5 Hotel. ADDRESSES: 711...

  11. 78 FR 19277 - Navigation Safety Advisory Council; Meeting

    Science.gov (United States)

    2013-03-29

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

  12. 78 FR 40726 - National Telecommunications and Information Administration Multistakeholder Meeting To Develop...

    Science.gov (United States)

    2013-07-08

    ... application transparency. For additional information, please see the Multistakeholder Meeting Notice. [[Page...-application-transparency , for the most current information. Place: The rescheduled meeting will be held in...-process-mobile-application-transparency , for the most current information. Dated: July 2, 2013. Kathy...

  13. Interprofessional team meetings: Opportunities for informal interprofessional learning.

    Science.gov (United States)

    Nisbet, Gillian; Dunn, Stewart; Lincoln, Michelle

    2015-01-01

    This study explores the potential for workplace interprofessional learning, specifically the learning that occurs between health professionals as part of their attendance at their regular interprofessional team meetings. While most interprofessional learning research to date has focused on formal structured education programs, this study adds to our understanding of the complexities of the learning processes occurring between health professionals as part of everyday practice. Through observations of team meetings and semi-structured interviews, we found that the interprofessional team meeting provided a practical, time-efficient, and relevant means for interprofessional learning, resulting in perceived benefits to individuals, teams, and patients. The learning process, however, was influenced by members' conceptions of learning, participation within the meeting, and medical presence. This study provides a basis for further research to assist health professionals capitalize on informal learning opportunities within the interprofessional meeting.

  14. Proceedings of the first technical committee meeting held in Vienna, Austria, 17-20 November 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This was the first Technical Committee meeting organized by the International Atomic Energy Agency on reactivity transient accidents as a response to recommendations made during the Chernobyl Post Accident Review Meeting (25-29 August 1986) and the subsequent Member States Experts meeting to review the IAEA expanded nuclear safety programme. The Technical Committee meeting was attended by 46 representatives from 28 countries and 1 international organization. The objectives of the Technical Committee meeting were: to review the state of knowledge and to assess the remaining safety questions relating to reactivity initiated accidents (RIAs); to share experience and information on RIA assessment and relevant fuel experiments; to formulate conclusions on what the consensus might be on safety aspects of the RIAs; and to provide recommendations for sharing the technical information and for IAEA assistance to Member States. A separate abstract was prepared for each of the 17 presentations of this meeting. Refs, figs and tabs

  15. 15 September: Annual Information Meeting of the Pension Fund

    CERN Multimedia

    2015-01-01

    All members and beneficiaries of the Pension Fund are invited to attend the Annual Information Meeting. *** Please note the room change *** CERN Main Auditorium Tuesday, 15 September 2015 9:30 a.m. - 11:30 a.m. Following a presentation by the Chief Executive Officer of the Fund there will be a Questions and Answers session. Members and Beneficiaries are welcome to send questions in advance of the meeting by post to: Mr Matthew Eyton-Jones “Annual Information Meeting” CEO - CERN Pension Fund Office 5-5-012, Postbox C23800 CH- 1211 Geneva 23 - Switzerland Copies of the 2014 Pension Fund Financial Statements are already available as a printable PDF on the Pension Fund website (http://pensionfund.cern.ch/en/financial-management/financial-statements) and will also be distributed at the annual meeting. *Coffee and croissants will be served prior to the meeting as of 9:00 a.m.* CERN Pension Fund

  16. 14. informal meeting on reactor noise

    International Nuclear Information System (INIS)

    1981-01-01

    The present booklet contains abstracts of papers from the 14th informal meeting on reactor noise held at St. Englmar in April 1981. The main topics dealt with are vibration and loose part monitoring, leak detection, noise theory and noise applications and in the final part data processing and pattern recognition techniques. (orig.)

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

    Science.gov (United States)

    2010-06-25

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

  18. 75 FR 27353 - Navigation Safety Advisory Council; Meeting

    Science.gov (United States)

    2010-05-14

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

  19. 76 FR 59142 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-09-23

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

  20. Proceedings of the international information exchange meeting on diffusion phenomena in bentonite and rock. Aiming at the safety assessment of the geological disposal

    International Nuclear Information System (INIS)

    Sato, Haruo; Hatanaka, Koichiro

    2009-12-01

    The international information exchange meeting on diffusion phenomena in bentonite and rock was held at Horonobe Underground Research Center on 18th July, 2006. This meeting was hosted by Japan Atomic Energy Agency (JAEA) and supported by Hokkaido University and Radioactive Waste Management Funding and Research Center (RWMC). Totally 18 scientists who are specialists of diffusion participated from Finland (VTT) and Japan (7 research organizations) in the meeting. 6 presentations were made on recent research activities and outputs on diffusion phenomena in bentonite and rock. The 6 papers are indexed individually. (J.P.N.)

  1. Report: Information Meeting / Awareness of Actors on the Chemical Information Exchange Network (CIEN)

    International Nuclear Information System (INIS)

    Senghor, Cheikh

    2015-01-01

    As part of the implementation of the Stockholm Convention, Senegal has established a Chemical Information Exchange Network. The overall objective of this meeting was to identify the various actors involved in the management of chemicals information and to study the modalities for the implementation of the chemical information exchange network in Senegal.

  2. 77 FR 15453 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-03-15

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... information collection titled, ``Gas Pipeline Safety Program Certification and Hazardous Liquid Pipeline... collection request that PHMSA will be submitting to OMB for renewal titled, ``Gas Pipeline Safety Program...

  3. 76 FR 13643 - FDA Food Safety Modernization Act: Title III-A New Paradigm for Importers; Public Meeting

    Science.gov (United States)

    2011-03-14

    ... Act: Title III--A New Paradigm for Importers; Public Meeting AGENCY: Food and Drug Administration, HHS... announcing a public meeting entitled ``FDA Food Safety Modernization Act: Title III--A New Paradigm for... provided. Request special accommodations due By March 22, 2011.... Patricia M. Kuntze, 301- to disability...

  4. Development of the Advanced Nuclear Safety Information Management (ANSIM) System

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

  5. Think over nuclear safety. ''Information asymmetry'' and ''comminicative action''

    International Nuclear Information System (INIS)

    Suzuki, Atsuyuki

    2006-01-01

    Nuclear safety should be fully understood not only technically but also socially. In order to think over nuclear safety socially, four different concepts were recommended to refer, which were ''procedural rationality'', information asymmetry'', ''certainty effect'' and ''communicative action'' proposed by three economists and a philosopher respectively. Risk-based communication approach for nuclear safety could be effective within the higher frequency area than safety goal, but not good for the lower frequency area than safety goal. The latter could be highly subjective and more qualitative. For this area, ''safety communication'' would be highly maintained with taking account of existence of ''information asymmetry'' and need of ''communicative action''. (T.Tanaka)

  6. Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Lin, C.; Strupczewski, A. [International Atomic Energy Agency, Vienna (Austria)

    1995-12-31

    At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

  7. Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Lin, C; Strupczewski, A [International Atomic Energy Agency, Vienna (Austria)

    1996-12-31

    At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

  8. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key topic / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Traichel, Anke [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany). Dept. of Safety Engineering and Assessment / Proposals Engineering

    2017-04-15

    Summary report on the Key Topic ''Enhanced Safety and Operation Excellence'' Technical Session ''Safety, IT, Hazards and PSA'' of the 47th Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016.

  9. Risk-informed, performance-based safety-security interface

    International Nuclear Information System (INIS)

    Mrowca, B.; Eltawila, F.

    2012-01-01

    Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

  10. Information systems in food safety management.

    Science.gov (United States)

    McMeekin, T A; Baranyi, J; Bowman, J; Dalgaard, P; Kirk, M; Ross, T; Schmid, S; Zwietering, M H

    2006-12-01

    Information systems are concerned with data capture, storage, analysis and retrieval. In the context of food safety management they are vital to assist decision making in a short time frame, potentially allowing decisions to be made and practices to be actioned in real time. Databases with information on microorganisms pertinent to the identification of foodborne pathogens, response of microbial populations to the environment and characteristics of foods and processing conditions are the cornerstone of food safety management systems. Such databases find application in: Identifying pathogens in food at the genus or species level using applied systematics in automated ways. Identifying pathogens below the species level by molecular subtyping, an approach successfully applied in epidemiological investigations of foodborne disease and the basis for national surveillance programs. Predictive modelling software, such as the Pathogen Modeling Program and Growth Predictor (that took over the main functions of Food Micromodel) the raw data of which were combined as the genesis of an international web based searchable database (ComBase). Expert systems combining databases on microbial characteristics, food composition and processing information with the resulting "pattern match" indicating problems that may arise from changes in product formulation or processing conditions. Computer software packages to aid the practical application of HACCP and risk assessment and decision trees to bring logical sequences to establishing and modifying food safety management practices. In addition there are many other uses of information systems that benefit food safety more globally, including: Rapid dissemination of information on foodborne disease outbreaks via websites or list servers carrying commentary from many sources, including the press and interest groups, on the reasons for and consequences of foodborne disease incidents. Active surveillance networks allowing rapid dissemination

  11. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection; 3. Congreso Regional sobre Seguridad Radiologica y Nuclear, Congreso Regional IRPA y 3. Congreso Peruano de Proteccion Radiologica. Libro de Resumenes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting.

  12. Functional safety of health information technology.

    LENUS (Irish Health Repository)

    Chadwick, Liam

    2012-03-01

    In an effort to improve patient safety and reduce adverse events, there has been a rapid growth in the utilisation of health information technology (HIT). However, little work has examined the safety of the HIT systems themselves, the methods used in their development or the potential errors they may introduce into existing systems. This article introduces the conventional safety-related systems development standard IEC 61508 to the medical domain. It is proposed that the techniques used in conventional safety-related systems development should be utilised by regulation bodies, healthcare organisations and HIT developers to provide an assurance of safety for HIT systems. In adopting the IEC 61508 methodology for HIT development and integration, inherent problems in the new systems can be identified and corrected during their development. Also, IEC 61508 should be used to develop a healthcare-specific standard to allow stakeholders to provide an assurance of a system\\'s safety.

  13. 76 FR 2923 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-01-18

    ... by telephone at (202) 358-0550 at least 48 hours in advance. Any member of the public is permitted to... copy of their passport, visa, or green card in addition to providing the following information no less than 10 working days prior to the meeting: full name; gender; date/place of birth; citizenship; visa...

  14. ACCU Meeting

    CERN Multimedia

    PH Department

    2011-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 15 June 2011 At 9:15 a.m. in room 60-6-002 Chairperson’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS department Update on Safety at CERN Reports from ACCU representatives on other Committees a. Scientific Information Policy Board (SIPB) b. IT Service Review Meeting (ITSRM) c. GS User Commission Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairperson in writing or by e-mail to Michael.Hauschild@cern.ch Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in bra...

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

    International Nuclear Information System (INIS)

    Kocherov, N.

    1982-01-01

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

  16. Criticality Safety Information Resource Center Web portal: www.csirc.net

    International Nuclear Information System (INIS)

    Harmon, C.D. II; Jones, T.

    2000-01-01

    The Nuclear Criticality Safety Group (ESH-6) at Los Alamos National Laboratory (LANL) is in the process of collecting and archiving historical and technical information related to nuclear criticality safety from LANL and other facilities. In an ongoing effort, this information is being made available via the Criticality Safety Information Resource Center (CSIRC) web site, which is hosted and maintained by ESH-6 staff. Recently, the CSIRC Web site was recreated as a Web portal that provides the criticality safety community with much more than just archived data

  17. 47 CFR 80.1135 - Transmission of maritime safety information.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Transmission of maritime safety information. 80... RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety System (GMDSS) Operating Procedures for Distress and Safety Communications § 80.1135 Transmission of maritime safety...

  18. Geothermal Energy and the Eastern US: Technical Information Interchange Meeting, Minutes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    The technical interchange meeting documented here is the fourth meeting where people interested in geothermal energy in the Eastern US have met to interchange technical information. These meetings are intended to assist all in the difficult task of balancing time and effort in doing their assigned jobs and keeping track of what others are doing in similar or related tasks. All of the aforementioned meetings have served their intended purpose and further regional and national meetings are sure to follow.

  19. Statement to Second Extraordinary Meeting of Contracting Parties to Convention on Nuclear Safety, 27 August 2012, Vienna, Austria

    International Nuclear Information System (INIS)

    Amano, Y.

    2012-01-01

    Full Text: I am pleased to address this Second Extraordinary Meeting of the Contracting Parties to the Convention on Nuclear Safety. This important meeting will be closely watched by the global nuclear community. I know you will make good use of this opportunity to consider further measures to strengthen nuclear safety throughout the world in the light of the lessons which we are still learning from the Fukushima Daiichi accident. One year after the adoption of the IAEA Action Plan on Nuclear Safety, significant progress has been made in several key areas. These include the assessment of safety vulnerabilities of nuclear power plants, strengthening IAEA peer review services, improving emergency preparedness and response capabilities and reviewing IAEA safety standards. Your work this week will address the request to Contracting Parties, expressed in the Action Plan, to explore mechanisms to enhance the effective implementation of Safety Conventions and to consider proposals to amend the Convention on Nuclear Safety. You will recall that last year's Ministerial Declaration stressed 'the importance of universal adherence to, and the effective implementation and continuous review of, the relevant international instruments on nuclear safety'. The Action Plan encouraged Member States to work cooperatively to maximize the lessons learned from the Fukushima Daiichi accident and to produce concrete results as soon as possible. The IAEA has reported periodically to Member States about its work to implement the Action Plan. We have also organised a number of international expert meetings to analyse technical aspects of the accident and ensure that the right lessons are learned. The results of this Extraordinary Meeting will provide an important input to future considerations of implementation of the Action Plan. Our Member States will review implementation at the Agency's 56th General Conference next month, while the Fukushima Ministerial Conference on Nuclear Safety in

  20. Proceedings of the international symposium on safety related measurements in PWRs: Topic of the first meeting: 'Temperature and level measurements'

    International Nuclear Information System (INIS)

    2001-09-01

    Numerous teams of experts from several countries deal with theme of measurement important for safety operation of WWER reactors. These special teams have a need to meet at various opportunities to change their experience. As an example I can mention meeting of experts from Russia , Germany, France and Slovakia at completion and reconstruction of Slovak NPP, at modernisation of Russian and Bulgarian NPP. Mentioned meetings have invoked an idea of participants to organise a common action aimed at measurement important for safety operation of WWER, that participants can change their experience from mentioned area at welcome environment of symposium. Therefore, at meeting of experts from Siemens, INCOR and VUJE at the end of the year 2000 participants agreed on realisation of such common action. Participants have taken orientation at all safety measurements for very deep topic. Therefore, they have decided in respect of this first meeting of symposium to give consideration to only some special measurements in particular to temperature and surface. In case of interest there is possible to take focus at other type of measurements. Slovakia has been chosen for the first meeting place on basis of economic reasons and also because a number of improvements of standard reactor temperature measuring procedures have been implemented here that over passed its frontiers. In addition the first fail-safe level measuring in reactor pressure vessel has been effectuated in Slovakia

  1. 78 FR 15680 - Information Sharing With Agency Stakeholders: Public Meeting

    Science.gov (United States)

    2013-03-12

    ...] Information Sharing With Agency Stakeholders: Public Meeting AGENCY: Animal and Plant Health Inspection... stakeholders regarding cross-Agency strategic priorities. We are also announcing that APHIS is hosting a public... opportunity for stakeholders to ask questions and share their perspective. DATES: The meeting will be held on...

  2. Information report on the nuclear safety and radiation protection of the Aube storage Centre - 2012

    International Nuclear Information System (INIS)

    2013-07-01

    This report first present the site of the Aube Storage Centre (CSA), its storage areas, its buildings and equipment, describes the water treatment process, proposes some exploitation data for 2012 (deliveries, storage, compacting), and indicates highlights and works performed in 2012. The next part reviews measures related to nuclear safety: recall of safety principles and objectives, technical arrangements to meet safety objectives, inspections by the ASN, quality audits. The third part reviews measures related to safety and radiation protection: principles for radiation protection, staff dosimetry practices and results, personnel safety, works performed in 2012. The fourth part addresses incidents and accidents (none occurred in 2012) and other minor events classified according to the INES scale. The fifth part addresses the control of the environment and the releases by the centre: measurement locations, measurement results (in the atmosphere, in rivers, in underground waters, radiological control, control of ecosystems, assessment of the radiological impact), physical-chemical control of a local river, actions undertaken for the protection of the environment, highlights for 2012. The next chapter addresses the management of the various wastes produced by the Centre (radioactive wastes, conventional wastes) and the last part reports actions regarding information and transparency. Recommendations of the CHSCT are reported

  3. 76 FR 40735 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-07-11

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

  4. 75 FR 10490 - Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-03-08

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

  5. Proceedings of the fourth information exchange meeting on nuclear production of hydrogen

    International Nuclear Information System (INIS)

    2010-01-01

    The use of hydrogen, both as feedstock for the industry (oil and chemical) and as an energy carrier, is expected to grow substantially during the coming decades. The current predominant method of producing hydrogen by steam-reforming methane (from natural gas) is not sustainable and has environmental drawbacks, including the emission of greenhouse gasses (GHGs). Nuclear energy offers a way to produce hydrogen from water without depleting natural gas, a valuable natural resource, and without the emission of GHGs. The OECD Nuclear Energy Agency (NEA) has conducted a number of information exchange meetings with the objective of stimulating progress in the development of nuclear production of hydrogen. These meetings, held in 2000 in Paris, France, in 2003 in Argonne, Illinois, USA, and in 2005 in Oarai, Japan, were well-attended and very successful. It is hoped that the information presented at fourth meeting and contained in these proceedings may be useful in advancing the objective of achieving economically viable, sustainable and emission-free production of hydrogen. The need for a sustainable supply of clean energy is one of the main problems facing the world. Among the various energy technologies which may be considered (including hydro, wind, solar, geo-thermal, wave and tidal), only nuclear - through the use of fast-neutron fission reactors - is capable of delivering the copious quantities of sustainable energy that will be required. In view of this, one of the means under consideration for achieving the objective of nuclear-produced hydrogen is enhanced international cooperation, including the establishment of one or more OECD/NEA joint projects. In this respect, it is worth noting that similar joint projects undertaken in the past (for example, the Dragon Project and the Halden Reactor Project) have been highly beneficial and have provided significant amounts of useful information to the sponsoring countries at shared costs. This report describes the

  6. Organizing safety: conditions for successful information assurance programs.

    Science.gov (United States)

    Collmann, Jeff; Coleman, Johnathan; Sostrom, Kristen; Wright, Willie

    2004-01-01

    Organizations must continuously seek safety. When considering computerized health information systems, "safety" includes protecting the integrity, confidentiality, and availability of information assets such as patient information, key components of the technical information system, and critical personnel. "High Reliability Theory" (HRT) argues that organizations with strong leadership support, continuous training, redundant safety mechanisms, and "cultures of high reliability" can deploy and safely manage complex, risky technologies such as nuclear weapons systems or computerized health information systems. In preparation for the Health Insurance Portability and Accountability Act (HIPAA) of 1996, the Office of the Assistant Secretary of Defense (Health Affairs), the Offices of the Surgeons General of the United States Army, Navy and Air Force, and the Telemedicine and Advanced Technology Research Center (TATRC), US Army Medical Research and Materiel Command sponsored organizational, doctrinal, and technical projects that individually and collectively promote conditions for a "culture of information assurance." These efforts include sponsoring the "P3 Working Group" (P3WG), an interdisciplinary, tri-service taskforce that reviewed all relevant Department of Defense (DoD), Miliary Health System (MHS), Army, Navy and Air Force policies for compliance with the HIPAA medical privacy and data security regulations; supporting development, training, and deployment of OCTAVE(sm), a self-directed information security risk assessment process; and sponsoring development of the Risk Information Management Resource (RIMR), a Web-enabled enterprise portal about health information assurance.

  7. Application of life-cycle information for advancement in safety of nuclear fuel cycle facilities. Application of safety information to advanced safety management support system

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Ishida, Michihiko

    2005-08-01

    Risk management is major concern to nuclear energy reprocessing plants to improve plant and process reliability and ensure their safety. This is because we are required to predict potential risks before any accident or disaster occurs. The advancement of safety design and safety systems technologies showed large amount of useful safety-related knowledge that can be of great importance to plant operation to reduce operation risks and ensure safety. This research proposes safety knowledge modeling framework on the basis of ontology technologies to systematically construct plant knowledge model, which includes plant structure, operation, and the associated behaviors. In such plant knowledge model safety related information is defined and linked to the different elements of plant knowledge model. Ontology editor is employed to define the basic concepts and their inter-relations, which are used to capture and construct plant safety knowledge. In order to provide detailed safety knowledgebase, HAZOP results are analyzed and structured so that safety-related knowledge are identified and structured within the plant knowledgebase. The target safety knowledgebase includes: failures, deviations, causes, consequences, and fault propagation as mapped to plant knowledge. The proposed ontology-based safety framework is applied on case study nuclear plant to structure failures, causes, consequences, and fault propagation, which are used to support plant operation. (author)

  8. 78 FR 2677 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-01-14

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

  9. 76 FR 59143 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-09-23

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

  10. AMFIE Information meetings

    CERN Multimedia

    2012-01-01

    Meetings open to all members of personnel (users, staff, etc) as well as retired staff.   Public presentation with question/answer session Wednesday 18 April 2012 From 12:00 to 13:00 In room 40-2-A01 Private consultations on appointment Wednesday 18 April 2012 From 10:00 to 11:30 and from 14:00 to 17:30 In room 5-5-028 AMFIE is a cooperative society open exclusively to international civil servants. It is managed by a group of active and retired international civil servants. Created in 1990 as a fully licensed financial institution, it is subject to the laws and regulations which govern the activities of Luxembourg's financial sector. The Cooperative offers its members a broad range of financial services and products at little or no cost in the six currencies available to account holders (EUR, CHF, GBP, USD, CAD, AUD). More information here. HR Department Tel. 74125

  11. 75 FR 53733 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2010-09-01

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0246] Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous... liquefied natural gas, hazardous liquid, and gas transmission pipeline systems operated by a company. The...

  12. Food safety: correct information for pregnant women

    Directory of Open Access Journals (Sweden)

    Bartolomeo Griglio

    2013-04-01

    Full Text Available This study was aimed at investigating the knowledge of pregnant women on food safety with particular attention to the effectiveness of the informative material (pamphlet and poster prepared in a previous study. To this scope, a questionnaire composed by 8 questions (Likert scaled was used except for one which was a Y/N question. Themes of the questionnaire were: level of concerns on food safety, and knowledge on foodborne diseases (salomonellosis, toxoplasmosis and listeriosis, risk factors and preventive measures. Results indicate that knowledge increased in respect to that of the previous study, but in relation to informative material previously distributed.

  13. 78 FR 16271 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-03-14

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

  14. Implications of power uprates on safety margins of nuclear power plants. Report of a technical meeting

    International Nuclear Information System (INIS)

    2004-09-01

    The safety of nuclear power plants (NPPs) is based on the defence in depth concept, which relies on successive physical barriers (fuel matrix, cladding, primary system pressure boundary and containment) and other provisions to control radioactive materials and on multiple levels of protection against damage to these barriers. Deterministic safety analysis is an important tool for conforming the adequacy and efficiency of provisions within the defence in depth concept and is used to predict the response of an NPP in predetermined operational states. This type of safety analysis applies a specific set of rules and specific acceptance criteria. Deterministic analysis is typically focused on neutronic, thermohydraulic, radiological and structural aspects, which are often analysed with different computational tools. The advanced computational tools developed for deterministic safety analysis are used for better establishment and utilization of licensing margins or safety margins in consideration of analysis results. At the same time, the existence of such margins ensures that NPPs operate safely in all modes of operation and at all times. To properly assess and address the existing margins and to be able to take advantage of unnecessary conservatisms, state of the art analytical tools intended for safety assessment have been developed. Progress made in the development and application of modern codes for safety analysis and better understanding of phenomena involved in plant design and operation enable the analysts to determine safety margins in consideration of analysis results (licensing margins) with higher precision. There is a general tendency for utilities to take advantage of unnecessarily large conservatisms in safety analyses and to utilize them for reactor power uprates, better utilization of nuclear fuel, higher operational flexibility and for justification of lifetime extension. The present publication sets forth the results of a Technical Meeting on the

  15. Meeting The Information Needs Of The Rural Dwellers Through ...

    African Journals Online (AJOL)

    Meeting The Information Needs Of The Rural Dwellers Through Public Library Services. ... majority of the population who are rural dwellers. And suggested that, the public library should repackage its services in order to reach this group of users in the future. Key words: information need, rural dwellers, public library services ...

  16. Meeting of specialists on 'Operational Safety of Sodium Circuits', Risley, UK, March 17-19, 1971. Summary report

    International Nuclear Information System (INIS)

    1971-01-01

    The meeting was attended by 20 delegates fyom Belgium, France, West Germany, Italy, Japan, the Netherlands, and the United Kingdom. Discussion took place in the following 5 Sessions: Safety Aspects of Design and Construction; Operational Practices; Sodium Leakage Phenomena; Emergency Procedures; Case Histories of Incidents. The formal papers tabled by the delegates at the meeting are reproduced in Appendix 2 of this report. At the final session of the meeting, the delegates agreed on the following report. The case histories of incidents as presented by various delegates are included in Appendix 2 of this report

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

    International Nuclear Information System (INIS)

    1996-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

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

  19. Atomic Information Technology Safety and Economy of Nuclear Power Plants

    CERN Document Server

    Woo, Taeho

    2012-01-01

    Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

  20. Global Complexity: Information, Chaos, and Control at ASIS 1996 Annual Meeting.

    Science.gov (United States)

    Jacob, M. E. L.

    1996-01-01

    Discusses proceedings of the 1996 ASIS (American Society for Information Science) annual meeting in Baltimore (Maryland), including chaos theory; electronic universities; distance education; intellectual property, including information privacy on the Internet; the need for leadership in libraries and information centers; information warfare and…

  1. 77 FR 6825 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting.

    Science.gov (United States)

    2012-02-09

    ...; Information Technology Infrastructure Committee; Meeting. AGENCY: National Aeronautics and Space... Information Technology Infrastructure Committee of the NASA Advisory Council. DATES: Wednesday, March 7, 2012... CONTACT: Ms. Karen Harper, Executive Secretary for the Information Technology Infrastructure Committee...

  2. Geothermal Energy and the Eastern US: Fifth technical information interchange meeting, Minutes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    The technical interchange meeting documented here is the fifth meeting where people interested in geothermal energy in the Eastern US have met to interchange technical information. These meetings are intended to assist all in the difficult task of balancing time and effort in doing their assigned jobs and keeping track of what others are doing in similar or related tasks. All of the aforementioned meetings have served their intended purpose and further regional and national meetings are sure to follow.

  3. 78 FR 42553 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting

    Science.gov (United States)

    2013-07-16

    ...; Information Technology Infrastructure Committee; Meeting AGENCY: National Aeronautics and Space Administration... Information Technology Infrastructure Committee (ITIC) of the NASA Advisory Council (NAC). This Committee..., DC 20546. FOR FURTHER INFORMATION CONTACT: Ms. Deborah Diaz, ITIC Executive Secretariat, NASA...

  4. 78 FR 72718 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting

    Science.gov (United States)

    2013-12-03

    ...; Information Technology Infrastructure Committee; Meeting AGENCY: National Aeronautics and Space Administration... Information Technology Infrastructure Committee (ITIC) of the NASA Advisory Council (NAC). DATES: Tuesday... Chief Information Officer Space Launch System Kennedy Space Center Operations and Technology Issues...

  5. Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

    International Nuclear Information System (INIS)

    Stritar, A.; Jencic, I.

    1996-01-01

    Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information

  6. Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Stritar, A; Jencic, I [Nuclear Society of Slovenia (Slovenia); eds.

    1996-07-01

    Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information.

  7. NASA System Safety Handbook. Volume 2: System Safety Concepts, Guidelines, and Implementation Examples

    Science.gov (United States)

    Dezfuli, Homayoon; Benjamin, Allan; Everett, Christopher; Feather, Martin; Rutledge, Peter; Sen, Dev; Youngblood, Robert

    2015-01-01

    This is the second of two volumes that collectively comprise the NASA System Safety Handbook. Volume 1 (NASASP-210-580) was prepared for the purpose of presenting the overall framework for System Safety and for providing the general concepts needed to implement the framework. Volume 2 provides guidance for implementing these concepts as an integral part of systems engineering and risk management. This guidance addresses the following functional areas: 1.The development of objectives that collectively define adequate safety for a system, and the safety requirements derived from these objectives that are levied on the system. 2.The conduct of system safety activities, performed to meet the safety requirements, with specific emphasis on the conduct of integrated safety analysis (ISA) as a fundamental means by which systems engineering and risk management decisions are risk-informed. 3.The development of a risk-informed safety case (RISC) at major milestone reviews to argue that the systems safety objectives are satisfied (and therefore that the system is adequately safe). 4.The evaluation of the RISC (including supporting evidence) using a defined set of evaluation criteria, to assess the veracity of the claims made therein in order to support risk acceptance decisions.

  8. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    International Nuclear Information System (INIS)

    2013-01-01

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  9. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  10. 76 FR 64386 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting

    Science.gov (United States)

    2011-10-18

    ..., Executive Secretary for the Information Technology Infrastructure Committee, National Aeronautics and Space... they are attending the NASA Advisory Council, Information Technology Infrastructure Committee meeting in Building 34, Room W305. All U.S. citizens desiring to attend the Information Technology...

  11. Safety related design and economic aspects of HTGRs. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-04-01

    The purpose of the Technical Committee Meeting (TCM) was to provide the opportunity to review the status of design and development activities associated with safety related and economic aspects of HTGRs, and to identify pathways which may provide the opportunity for international cooperation in addressing these issues. The HTGR, as a nuclear heat source for the safe, economic and efficient production of electricity and high temperature industrial processes has, within the past few years, become a significantly increasing influence in the future of nuclear power. Nuclear test facilities with the capability of achieving core outlet temperatures to 950 deg. C are presently under construction in China and Japan. These plants will be utilized to support HTGR research and development activities, including electricity generation via the gas turbine and validation of high temperature process heat applications. Also, major development programmes focusing on the generation of electricity through the direct cycle gas turbine are in progress by ESKOM, the state electric utility of South Africa, and by a consortium of organizations from the Russian Federation, USA, France and Japan. Other national programmes focusing on research and development of the HTGR are underway including the Netherlands, where an evaluation is being completed on a heat and power co-generation plant utilizing a small direct cycle HTR; in Germany, where the primary focus is centered on basic issues of reactor safety and innovative reactor technology; in Indonesia with the evaluation of process heat applications such as coal liquefaction, hydrogen production and high temperature reforming of methane; and in the USA with the recent re-introduction of national support for the HTGR specifically directed to the burning of weapons plutonium. The status information presented in several of the papers is as of the time of drafting. Thus other later material should be referenced for more current status information

  12. Safety related design and economic aspects of HTGRs. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-04-01

    The purpose of the Technical Committee Meeting (TCM) was to provide the opportunity to review the status of design and development activities associated with safety related and economic aspects of HTGRs, and to identify pathways which may provide the opportunity for international cooperation in addressing these issues. The HTGR, as a nuclear heat source for the safe, economic and efficient production of electricity and high temperature industrial processes has, within the past few years, become a significantly increasing influence in the future of nuclear power. Nuclear test facilities with the capability of achieving core outlet temperatures to 950 deg. C are presently under construction in China and Japan. These plants will be utilized to support HTGR research and development activities, including electricity generation via the gas turbine and validation of high temperature process heat applications. Also, major development programmes focusing on the generation of electricity through the direct cycle gas turbine are in progress by ESKOM, the state electric utility of South Africa, and by a consortium of organizations from the Russian Federation, USA, France and Japan. Other national programmes focusing on research and development of the HTGR are underway including the Netherlands, where an evaluation is being completed on a heat and power co-generation plant utilizing a small direct cycle HTR; in Germany, where the primary focus is centered on basic issues of reactor safety and innovative reactor technology; in Indonesia with the evaluation of process heat applications such as coal liquefaction, hydrogen production and high temperature reforming of methane; and in the USA with the recent re-introduction of national support for the HTGR specifically directed to the burning of weapons plutonium. The status information presented in several of the papers is as of the time of drafting. Thus other later material should be referenced for more current status information

  13. Report on the environmental safety evaluation sub-committee meetings in fiscal 1987; 1987 nendo kankyo anzensei hyoka bukai hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-03-01

    The environmental safety evaluation sub-committee has held two meeting in the current fiscal year as described below. The first sub-committee meeting (August 25, 1987) was held for the agenda of the summary of future test plans, the result of overseas surveys in fiscal 1986, the results of tests in fiscal 1986, and the summary of the test plan for fiscal 1987. The major agendum of the second sub-committee meeting (February 23) was the interim reports on the overseas survey results and the safety tests in fiscal 1987. NEDO intends to ensure the labor hygiene for workers in coal liquefying plants, the effect of liquefied oil on users' health, and social acceptability of liquefied oil. Therefore, a safety test for liquefied oil in the primary hydrogenation process was performed provisionally on brown coal PP in the initial stage of operation, in addition to bituminous coal liquefied oil at the existing 1-t/d PDU. The main contents of the test performed by NEDO are based on the labor safety and hygiene law and the law related to regulation on the deliberation and manufacture of chemical materials. Different tests using guinea pigs were carried out on the total fraction mixed at the 1-t/d PDU, and each fraction of light and heavy oils, where the liquefied oil was verified to have minor degree of toxicity. (NEDO)

  14. Supply chain management - safety aspects

    Directory of Open Access Journals (Sweden)

    2010-12-01

    Full Text Available Developing economy, growing customer requirements and competition make the service level higher. Delivery safety - as the highest priority - has to be maintained at the same time. Customers more and more often require transport to be very flexible, fast, and complex in terms of carrying every quantity of goods of different sizes, from and to different countries, through customs clearance, storing and distribution of shipments. Meeting these requirements depends on complex information on transport processes and their safety. The article presents safety foundations and institution Authorized Economic Operator - AEO in supply chains.

  15. Passive safety features in current and future water cooled reactors

    International Nuclear Information System (INIS)

    1990-11-01

    Better understanding of the passive safety systems and components in current and future water-cooled reactors may enhance the safety of present reactors, to the extend passive features are backfitted. This better understanding should also improve the safety of future reactors, which can incorporate more of these features. Passive safety systems and components may help to prevent accidents, core damage, or release radionuclides to the environment. The Technical Committee Meeting which was hosted by the USSR State Committee for Utilization of Nuclear Energy was attended by about 80 experts from 16 IAEA Member States and the NEA-OECD. A total of 21 papers were presented during the meeting. The objective of the meeting was to review and discuss passive safety systems and features of current and future water cooled reactor designs and to exchange information in this area of activity. A separate abstract was prepared for each of the 21 papers published in this proceedings. Refs, figs and tabs

  16. Evolving information systems: meeting the ever-changing environment

    NARCIS (Netherlands)

    Oei, J.L.H.; Proper, H.A.; Falkenberg, E.D.

    1994-01-01

    To meet the demands of organizations and their ever-changing environment, information systems are required which are able to evolve to the same extent as organizations do. Such a system has to support changes in all time-and application-dependent aspects. In this paper, requirements and a conceptual

  17. Innovative nuclear reactor - Indian approach to meet user requirements for safety

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2002-01-01

    Full text: For sustainable development of nuclear energy, a number of key issues are to be addressed. It should be economically competitive; it must address the issues related to nuclear safety, proliferation resistance, environmental impact, waste disposal and cross cutting issues like social and infra-structural aspects. To compete successfully in the long term, in the highly competitive energy market and to overcome other challenges, it is necessary to introduce innovative reactor and fuel cycle concepts. Indian Advanced Heavy Water Reactor (AHWR) is one such innovative reactor. To guide the research and development activities related to innovative concepts, user requirements are to be formulated. User requirements covering various aspects of sustainable development are being formulated at both national and international levels. One such international project involved in the formulation of user requirements is the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). This paper deals with INPRO user requirements for safety and Indian approach to meet these requirements through AHWR

  18. Safety Psychology Applicating on Coal Mine Safety Management Based on Information System

    Science.gov (United States)

    Hou, Baoyue; Chen, Fei

    In recent years, with the increase of intensity of coal mining, a great number of major accidents happen frequently, the reason mostly due to human factors, but human's unsafely behavior are affected by insecurity mental control. In order to reduce accidents, and to improve safety management, with the help of application security psychology, we analyse the cause of insecurity psychological factors from human perception, from personality development, from motivation incentive, from reward and punishment mechanism, and from security aspects of mental training , and put forward countermeasures to promote coal mine safety production,and to provide information for coal mining to improve the level of safety management.

  19. Development of methodologies for optimization of surveillance testing and maintenance of safety related equipment at NPPs. Report of a research coordination meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This report summarizes the results of the first meeting of the Coordinated Research Programme (CRP) on Development of Methodologies for Optimization of Surveillance Testing and Maintenance of Safety Related Equipment at NPPs, held at the Agency Headquarters in Vienna, from 16 to 20 December 1996. The purpose of this Research Coordination Meeting (RCM) was that all Chief Scientific Investigators of the groups participating in the CRP presented an outline of their proposed research projects. Additionally, the participants discussed the objective, scope, work plan and information channels of the CRP in detail. Based on these presentations and discussions, the entire project plan was updated, completed and included in this report. This report represents a common agreed project work plan for the CRP. Refs, figs, tabs.

  20. A participatory model for improving occupational health and safety: improving informal sector working conditions in Thailand.

    Science.gov (United States)

    Manothum, Aniruth; Rukijkanpanich, Jittra; Thawesaengskulthai, Damrong; Thampitakkul, Boonwa; Chaikittiporn, Chalermchai; Arphorn, Sara

    2009-01-01

    The purpose of this study was to evaluate the implementation of an Occupational Health and Safety Management Model for informal sector workers in Thailand. The studied model was characterized by participatory approaches to preliminary assessment, observation of informal business practices, group discussion and participation, and the use of environmental measurements and samples. This model consisted of four processes: capacity building, risk analysis, problem solving, and monitoring and control. The participants consisted of four local labor groups from different regions, including wood carving, hand-weaving, artificial flower making, and batik processing workers. The results demonstrated that, as a result of applying the model, the working conditions of the informal sector workers had improved to meet necessary standards. This model encouraged the use of local networks, which led to cooperation within the groups to create appropriate technologies to solve their problems. The authors suggest that this model could effectively be applied elsewhere to improve informal sector working conditions on a broader scale.

  1. Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. [National report from Norway, fourth review meeting, 14-23 May 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This report contains the national report from Norway to the fourth review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14 to 23 May 2012. (Author)

  2. FAST FLUX TEST FACILITY DRIVER FUEL MEETING

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1966-06-01

    The Pacific Northwest Laboratory has convened this meeting to enlist the best talents of our laboratories and industry in soliciting factual, technical information pertinent to the Pacific Northwest's Laboratory's evaluation of the potential fuel systems for the Fast Flux Test Facility. The particular factors emphasized for these fuel systems are those associated with safety, ability to meet testing objectives, and economics. The proceedings includes twenty-three presentations, along with a transcript of the discussion following each, as well as a summary discussion.

  3. Commissions as information organizations: Meeting the information needs of an electronic society

    Energy Technology Data Exchange (ETDEWEB)

    Sevel, F.

    1997-11-01

    This paper describes how commission-sponsored web sites can effectively meet electronic information needs. Demographics of internet users are presented and analyzed. Online activities and user access data are also described. The implications of the characteristics of internet users for commission-sponsored web sites are discussed, and guidelines for determining marketing objectives are presented.

  4. The use of information and communication technology to meet chronically ill patients' needs when living at home.

    Science.gov (United States)

    Skär, Lisa; Söderberg, Siv

    2011-01-01

    The aim of the study was to describe influences, benefits, and limitations in using information and communication technology to meet chronically ill patients' needs when living at home. The study is a descriptive, exploratory designed pilot study and the intervention was performed using an electronic communication program enabling communication between ill persons and the district nurse in real time by web cam pictures and sound. The participant used the programme once or twice a week from February to August 2008. Data were collected by means of repeated interviews and logbook notes, and were subjected to qualitative content analysis. The results showed that all participants appreciated being able to communicate regardless of time and place and their experiences of using information and communication technology revealed that it created feelings of safety and security. The information and communication technology became a tool in their communication and improved nursing care among seriously chronically ill persons living at home.

  5. 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 ...

  6. OECD/CSNI specialist meeting on nuclear aerosols in reactor safety - Summary and Conclusions

    International Nuclear Information System (INIS)

    Allelein, Hans-Josef; Boulaud, Denis; Guentay, Salih; Dehbi, Abdelouahab; Hontanon, Esther; Jokiniemi, Jorma; Jones, Alan V.; Koroll, Grant W.; Tinkler, Charles G.; Schaperow, J.; Royen, Jacques

    1999-01-01

    The Third OECD Specialist Meeting on Nuclear Aerosols in Reactor Safety was organised in Cologne, Germany, from 15-18 June 1998, in collaboration with the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. It was attended by sixty-five specialists representing thirteen OECD Member countries and the Commission of the European Communities. Thirty-nine papers were presented, in eight sessions. The meeting was concluded by a general discussion devoted to the following topics: - What has been solved up to the level of plant applications and accident management? - Where is more work needed for plant applications? Over the last eight years significant progress has been made in source term modelling and code development. Results have been consolidated in codes which are being used for plant calculations to address safety issues. For example, two countries used their source term codes last year to assess the impact of heating from deposited fission products on the potential for steam generator tube rupture. Also, another source term code was used to assess the need of sprays for fission product removal in the proposed design of a new type of reactor. Over the next few years, experiments and model development will continue, with more emphasis on application to risk-important severe accident scenarios

  7. The Aube Storage Centre. Information report on nuclear safety and radiation protection for 2014 - Annual report 2014

    International Nuclear Information System (INIS)

    2014-06-01

    After a presentation of the installations of CSA (Aube Storage Centre), its equipment, its exploitation (deliveries, storage, compacting unit, injection unit, storage works), works performed and highlights in 2014, and perspectives of evolution for 2015 and 2016, this report presents the measures regarding nuclear safety: safety principles, technical measures to meet objectives, inspections performed by the Nuclear Safety Authority (ASN), and quality management. The next part presents measures regarding measures for radiation protection and safety: staff dosimetry (measurements results and evolutions), safety exercise. It outlines that no important incident occurred, and described three minor events which have been declared to the ASN. The next part addresses actions related to the control of the environment and of releases: water management, presentation and discussion of the main results of radiological measurements (rainfalls, air, brook waters, sediments, underground waters, radiation at the edge of the centre, ground vegetal, food chain, aquatic ecosystems), physical-chemical control of waters, actions for the protection of the environment. The report then gives an overview of the management of radioactive and conventional wastes produced by the Centre. The last part indicates and comments actions related to transparency and information (they may concern the public, local authorities, institutions, or media): visits, conferences, exhibitions, animations, partnerships, publications

  8. 75 FR 13134 - Notice of Meeting

    Science.gov (United States)

    2010-03-18

    ...)(6). Grant applications for the Medical Liability and Safety Innovation Projects (R21) applications... disclosure under the above- cited statutes. SEP Meeting on: Medical Liability and Safety Innovation Projects... meeting) Place: Doubletree Bethesda Hotel & Executive Meeting Center, 8120 Wisconsin Avenue, Conference...

  9. RBMK safety issues

    International Nuclear Information System (INIS)

    Weber, J.P.; Reichenbach, D.; Tscherkashow, J.M.

    1995-01-01

    On the basis of information and documents from the RBMK operation countries, the Western consortium mainly examined the two most modern plants, Ignalin-2 and Smolensk-3. The identification of numerous shortcomings, some of which had already been recongized by the participating Eastern organizations, resulted in some 300 specific recommendations to reactor designers, operators and licensing authorities. These recommendations are to be acted upon at once; only a small number did not meet with the approval of the Eastern partners. The safety review provided the Western consotrium with a profound insight into the design and safety of third-generation RBMK reactors; the Eastern partners were able to accumulate experience in working with Western safety philosophy. (orig.) [de

  10. 75 FR 12718 - Hazard Communication; Meetings Notice

    Science.gov (United States)

    2010-03-17

    ... 1926 [Docket No. OSHA-H022K-2006-0062, (formerly OSHA Docket No. H022K] RIN 1218-AC20 Hazard Communication; Meetings Notice AGENCY: Occupational Safety and Health Administration (OSHA), Department of Labor..., 2009, OSHA announced that it would hold informal public hearings on its proposal to revise the Hazard...

  11. Managing knowledge and information on nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2005-01-01

    Described is the management of nuclear safety knowledge through education networks, knowledge pool, sharing, archiving and distributing the knowledge information. Demonstrated is the system used at Gesellschaft fuer Anlagen-und Reaktorsicherheit

  12. 75 FR 13135 - Notice of Meeting

    Science.gov (United States)

    2010-03-18

    ...). Grant applications for the Medical Liability and Safety Demonstration Projects (R18) applications are to... disclosure under the above-cited statutes. SEP Meeting on: Medical Liability and Safety Demonstration... remainder of the meeting). Place: Doubletree Bethesda Hotel & Executive Meeting Center, 8120 Wisconsin...

  13. Mochovce NPP safety improvement and completion

    International Nuclear Information System (INIS)

    1997-01-01

    6th Nuclear society information meeting dealt with the completion of the Mochovce NPP with regard to implementation of safety measures. It was aimed to next problems: I. 'Survey' presentation on the situation of the nuclear power industry in partner countries; II. Basic technical presentations; III. Presentations of operators of the other VVER 440/213 NPPs on their activities in the field of safety improvement in relation to IAEA recommendations; IV. Technical solutions of safety improvements ranked with IAEA degree 3 (Report SC 108 VVER); V: Technical solutions of selected Safety Measures ranked with IAEA degree 2 and 1 (Report SC 108 VVER)

  14. A qualitative exploration of patients' attitudes towards the 'Participate Inform Notice Know' (PINK) patient safety video.

    Science.gov (United States)

    Pinto, Anna; Vincent, Charles; Darzi, Ara; Davis, Rachel

    2013-02-01

    To explore patients' attitudes towards the PINK video, a patient education video aimed at encouraging hospital patients' involvement in safety-relevant behaviours. Qualitative semi-structured interviews. Detailed field notes were taken during the interviews which were analysed using content analysis. One National Health System (NHS) teaching hospital based in London, UK. Thirty-six in-patients aged between 20 and 79 years, 18 of them males. The PINK video is a short animated educational video aimed at encouraging patients to be involved in the safety of their care during hospitalization. Patients' perceptions of how informative, relevant and acceptable the video is; attitudes towards participating in the recommended safety-related behaviours and; potential negative side effects of watching the video. Overall the video was received favourably among the interviewees. Commonly cited benefits included raising awareness and facilitating patients to be involved in their care during their hospital stay. More variability was found in participants' views with regard to the video's role as a patient safety enhancement tool. A number of suggestions for improvement of the video were provided relating to tailoring its content and design to meet the needs of individual patients and their circumstances. Educational videos such as PINK have significant potential to empower patients in the safety and quality of their care. However, efforts to implement patient safety educational videos in practice need to consider different patient groups' needs and characteristics instead of trying to adopt 'a one size fits all' approach.

  15. Special Issue. 5th Meeting on Technology and Safety

    International Nuclear Information System (INIS)

    Kusakabe, Masashi; Kumagaya, Tadafusa; Minohara, Shinichi

    2010-01-01

    The documents in this Special Issue are the representative reports of achievements presented in the National Institute of Radiological Sciences (NIRS) 5th Meeting on Technology and Safety held on March 17, 2010. Personnel and investigators of NIRS and related companies gave their achievements by 19 oral and 31 poster presentations in fields of [IAR] irradiation (2 topics), accelerator/radiometry (9 topics), [EA] experimental animals (25 topics), [SM] safety management of facilities (5 topics), computer network system (4 topics), experimental instrument (1 topic), molecular imaging (2 topics) and others (2 topics). The Issue contains, as well as introductory and ending remarks, following 12 topics: [IAR] Working report of patient positioning system for radiotherapy with use of X-ray flat panel detector; Status of maintenance and management of facilities and equipments in Research center for Radiation Emergency Medicine; [EA] Past, present and future of mouse breeding in NIRS; Breeding of marmoset in NIRS/How can we have a bouncing marmoset baby?; Establishment of a genotyping method of transformed genes in transgenic mouse/genome walking method; Genetic monitoring system of mice by micro-satellite marker and its application in NIRS; Verification of sorting precision of FACSAria (Becton Dickinson and Co.), a highly sensitive, rapid sorting apparatus of cells/for precise sorting; Proposal of a task-solution workflow to determine the animal features for molecular imaging studies; [SM] Toward the introduction of Occupational Safety and Health Management System in NIRS; Use of unsealed radioisotopes less than the lower limit outside the legal control area; Arrangement of managing and supporting system for clinical studies; and Rearrangement of working system of personnel affairs. (T.T.)

  16. Development of digital safety system logic and control

    International Nuclear Information System (INIS)

    Nishikawa, H.; Sakamoto, H.

    1995-01-01

    Advanced-BWR (ABWR) uses total digital control and instrumentation (C and I) system. In particular, ABWR adopts a newly developed safety system using advanced digital technology. In the presentation the digital safety system design, manufacturing and factory validation test method are shortly overviewed. The digital safety system consists of micro-processor based digital controllers, data and information transmission by optical fibers and human-machine interface using color flat displays. This new developed safety system meet the nuclear safety requirements such as high reliability, independence of divisions, operability and maintainability. (2 refs., 4 figs., 1 tab.)

  17. Radiation safety research information database

    International Nuclear Information System (INIS)

    Yukawa, Masae; Miyamoto, Kiriko; Takeda, Hiroshi; Kuroda, Noriko; Yamamoto, Kazuhiko

    2004-01-01

    National Institute of Radiological Sciences in Japan began to construct Radiation Safety Research Information Database' in 2001. The research information database is of great service to evaluate the effects of radiation on people by estimating exposure dose by determining radiation and radioactive matters in the environment. The above database (DB) consists of seven DB such as Nirs Air Borne Dust Survey DB, Nirs Environmental Tritium Survey DB, Nirs Environmental Carbon Survey DB, Environmental Radiation Levels, Abe, Metabolic Database for Assessment of Internal Dose, Graphs of Predicted Monitoring Data, and Nirs nuclear installation environment water tritium survey DB. Outline of DB and each DB are explained. (S.Y.)

  18. Safety Assessment for Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum

  19. Information about the control of nuclear safety in France

    International Nuclear Information System (INIS)

    Gerster, D.

    1994-01-01

    The permanent objective of the French Nuclear Safety Authority is the public information about technical controls performed in French nuclear installations. Three publications from the DSIN (Direction of Nuclear Installations Safety) are devoted to this effort: the MAGNUC Minitel magazine, the annual activity report and the CONTROLE magazine. Details about the content of these publications are given. A large part of the information about control of nuclear safety concerns the incidents and accidents and their importance level. A seriousness scale was created in France at the beginning of 1988 and replaced in April 1994 by the very similar International Nuclear Event Scale (INES). Explanation of this scale is given and illustrated with examples of real events and accidents. However, international comparison between incidents and accidents remains delicate because the detailed content of safety reports can change significantly from one country to another. (J.S.). 1 fig

  20. An Adaptive Information Quantity-Based Broadcast Protocol for Safety Services in VANET

    Directory of Open Access Journals (Sweden)

    Wenjie Wang

    2016-01-01

    Full Text Available Vehicle-to-vehicle communication plays a significantly important role in implementing safe and efficient road traffic. When disseminating safety messages in the network, the information quantity on safety packets changes over time and space. However, most of existing protocols view each packet the same to disseminate, preventing vehicles from collecting more recent and precise safety information. Hence, an information quantity-based broadcast protocol is proposed in this paper to ensure the efficiency of safety messages dissemination. In particular, we propose the concept of emergency-degree to evaluate packets’ information quantity. Then we present EDCast, an emergency-degree-based broadcast protocol. EDCast differentiates each packet’s priority for accessing the channel based on its emergency-degree so as to provide vehicles with more safety information timely and accurately. In addition, an adaptive scheme is presented to ensure fast dissemination of messages in different network condition. We compare the performance of EDCast with those of three other representative protocols in a typical highway scenario. Simulation results indicate that EDCast achieves higher broadcast efficiency and less redundancy with less delivery delay. What we found demonstrates that it is feasible and necessary for incorporating information quantity of messages in designing an efficient safety message broadcast protocol.

  1. France - Convention on nuclear safety. Fourth national report established in view of the 2008 examination meeting

    International Nuclear Information System (INIS)

    2007-07-01

    This report is the fourth one established in compliance with the article 5 of the international Convention on nuclear safety, and presents measures implemented by France to meet each of the Convention requirements. It addresses electro-nuclear reactors as well as research reactors. After an overview of the main evolutions since the third French report, and a general presentation of the French national nuclear policy, the report addresses the different articles of the Convention. These articles deal with general arrangements (application arrangements, presentation of reports, existing nuclear installations with their safety assessments and main safety improvements brought to the different nuclear reactors), law and regulation (legal and regulatory framework, regulation bodies, responsibility of an authorization holder), general safety considerations (priority for safety, human and financial resources, human factors, quality insurance, safety assessment and verification, radiation protection, organisation in case of emergency), and installation safety (site selection, design and construction, exploitation, activities planned to improve safety). Appendices propose a list and locations of French nuclear reactors, a list of the main legal and regulatory texts, presentations of nuclear reactor operators (EDF, CEA, ILL), and an overview of practices of control of the environment

  2. Proceedings of the international meeting on reduced enrichment for research and test reactors

    Energy Technology Data Exchange (ETDEWEB)

    Tsuchihashi, Keichiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1984-05-01

    The purpose of the Meeting was to exchange and discuss the most up-to-date information on the progress of various programs related to research and test reactor core conversion from high enriched uranium to lower enriched uranium. The papers presented during the Meeting were divided into 9 sessions and one round able discussion which concluded the Meeting. The Sessions were: Program, Fuel Development, Fuel Fabrication, Irradiation testing, Safety Analysis, Special Reactor Conversion, Reactor Design, Critical Experiments, and Reprocessing and Spent Fuel Storage. Thus, topics of this Meeting were of a very wide range that was expected to result in information exchange valuable for all the participants in the RERTR program.

  3. Proceedings of the international meeting on reduced enrichment for research and test reactors

    International Nuclear Information System (INIS)

    Tsuchihashi, Keichiro

    1984-05-01

    The purpose of the Meeting was to exchange and discuss the most up-to-date information on the progress of various programs related to research and test reactor core conversion from high enriched uranium to lower enriched uranium. The papers presented during the Meeting were divided into 9 sessions and one round able discussion which concluded the Meeting. The Sessions were: Program, Fuel Development, Fuel Fabrication, Irradiation testing, Safety Analysis, Special Reactor Conversion, Reactor Design, Critical Experiments, and Reprocessing and Spent Fuel Storage. Thus, topics of this Meeting were of a very wide range that was expected to result in information exchange valuable for all the participants in the RERTR program

  4. Annual technical meeting of the NRC cooperative severe accident research program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1993-01-01

    This brief report summarizes the 1992 annual technical meeting of the NRC Cooperative Severe Accident Research Program (CSARP-92) held at the Hyatt Regency Hotel in Bethesda, Maryland, May 4-8, 1992. The report is taken mainly from coverage of the meeting published in the June 5, 1992, issue of Atomic Energy Clearinghouse. Results of this meeting are formalized at the Water Reactor Safety Information Meetings (WRSIM) that are held annually in October. Nuclear Safety summarizes the annual WRSIM meetings and provides a list of the presentations that were given. Interested readers are encouraged to review listed topics to identify specific topic areas in severe accident research. Sessions were held on in-vessel core melt progression; fuel-coolant interactions; fission-product behavior; direct containment heating; and severe accident code development, assessment, and validation. Summaries of the individual technical sessions and the current state of the art in these areas were given by the chairmen

  5. Proceedings of the specialist meeting on the safety of water reactors fuel elements

    International Nuclear Information System (INIS)

    1973-01-01

    This specialist meeting on the safety of water reactors fuel elements was held in Saclay (France) in October 1973, and was organized by CSNI and CEA. It attracted specialists from 14 countries. Session I was devoted to normal operating conditions (coolant-cladding and fuel-cladding interactions, fission product release, effects of cladding deformation on fuel element performances and reactor operating limits); Session II was devoted to operating reactor accidents and failures, anomalous transients and handling accidents; Session III was devoted to modifications to be applied to fuel elements in order to enhance their safety and reliability; Session IV was devoted to Loss-of-Coolant Accidents (LOCA)(cladding behaviour during the accident, assembly behaviour during the accident, criteria to be considered for the study of fuel element behaviour during a LOCA)

  6. Reliability of computerized safety systems at nuclear power plants. Report of a technical committee meeting held in Vienna, 21-25 June 1993

    International Nuclear Information System (INIS)

    1995-03-01

    Computer based technology is increasingly used in order to perform safety functions. In some recently designed nuclear power plants the whole safety system is computerized. In older plants replacement of conventional technology based system is seen to be of benefit. If the new technology is to be used, it must meet at least the same level of quality and reliability requirements as specified for conventional technology. However, there is a potential for enhancing the safety of nuclear power plants if the full power of computer technology is applied correctly through well designed, engineered and tested systems which are properly installed and maintained. It is essential that areas where reliability and quality can be improved are identified and that methods for assessing and assuring reliability are developed. The results of the Technical Committee Meeting on Reliability of Computerized Safety Systems at Nuclear Power Plants presented in this report are a step on the road to this goal of improved nuclear safety. Refs, figs and tabs

  7. Maintenance of radiation safety information system

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ho Sun [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Moon Il; Chung, Chong Kyu; Lim, Bock Soo; Kim, Hyung Uk; Chang, Kwang Il; Nam, Kwan Hyun; Cho, Hye Ryan [AD center incubation LAB, Taejon (Korea, Republic of)

    2001-12-15

    The objectives of radiation safety information system maintenance are to maintain the requirement of users, change of job process and upgrade of the system performance stably and effectively while system maintenance. We conduct the code of conduct recommended by IAEA, management of radioisotope inventory database systematically using analysis for the state of inventory database integrated in this system. This system and database will be support the regulatory guidance, rule making and information to the MOST, KINS, other regulatory related organization and general public optimizationally.

  8. 78 FR 25476 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2013-05-01

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

  9. 49 CFR 575.301 - Vehicle Labeling of Safety Rating Information.

    Science.gov (United States)

    2010-10-01

    ... providing them with safety rating information developed by NHTSA in its New Car Assessment Program (NCAP..., as specified at 15 U.S.C. 1231-1233. (2) Safety rating label means the label with NCAP safety rating... has approved an optional NCAP test that will cover that category, the manufacturer may depict vehicles...

  10. Integrated care: an Information Model for Patient Safety and Vigilance Reporting Systems.

    Science.gov (United States)

    Rodrigues, Jean-Marie; Schulz, Stefan; Souvignet, Julien

    2015-01-01

    Quality management information systems for safety as a whole or for specific vigilances share the same information types but are not interoperable. An international initiative tries to develop an integrated information model for patient safety and vigilance reporting to support a global approach of heath care quality.

  11. Design Information from the PSA for Digital Safety-Critical Systems

    International Nuclear Information System (INIS)

    Kang, Hyun Gook; Jang, Seung Cheol

    2005-01-01

    Many safety-critical applications such as nuclear field application usually adopt a similar design strategy for digital safety-critical systems. Their differences from the normal design for the non-safety-critical applications could be summarized as: multiple-redundancy, highly reliable components, strengthened monitoring mechanism, verified software, and automated test procedure. These items are focusing on maintaining the capability to perform the given safety function when it is requested. For the past several decades, probabilistic safety assessment (PSA) techniques are used in the nuclear industry to assess the relative effects of contributing events on plant risk and system reliability. They provide a unifying means of assessing physical faults, recovery processes, contributing effects, human actions, and other events that have a high degree of uncertainty. The applications of PSA provide not only the analysis results of already installed system but also the useful information for the system under design. The information could be derived from the PSA experience of the various safety-critical systems. Thanks to the design flexibility, the digital system is one of the most suitable candidates for risk-informed design (RID). In this article, we will describe the feedbacks for system design and try to develop a procedure for RID. Even though the procedure is not sophisticated enough now, it could be the start point of the further investigation for developing more complete and practical methodology

  12. Report by the parliamentary mission of nuclear safety, the place and future of the sector - Intermediary report: the nuclear safety

    International Nuclear Information System (INIS)

    2011-01-01

    Notably based on visits, meetings and auditions, this report first discusses the management of nuclear safety in France and stresses how rigorous it is. It comments how the different types of risks (natural, industrial, human) are taken into account, how safety is physically present (protection barriers, warehousing, operator training) and monitored, how this organisation is always improved as far as monitoring, information and preparedness to crisis are concerned. Then, the authors present the main orientations for the strengthening of safety: by taking new major risks into account, by anticipating possible situations (for installations, for matters of civil security, for population information and sensitization), and by investing on the issue of safety (in a financial way as well as in an organisational way, or by investing on research)

  13. Proceedings of the meeting on uranium exploration, mining and extraction

    International Nuclear Information System (INIS)

    1996-01-01

    Meeting on uranium exploration, mining, and extraction is aimed to expedite information exchange among researchers from the National Atomic Energy Agency (BATAN), their international colleagues, the higher education institutions,and other interested scientific communities on the latest development on Kalan uranium minerals exploration, mining, and extraction. Nuclear Minerals Development Centre (PPBGN) roles in nuclear energy provision, the theme of the meeting, reflect current advancements of the Centre in fulfilling its major tasks and responsibilities. In order to assist PPBGN better to assume its roles and responsibilities, the meeting is expected to bring forth essential solutions for problems and difficulties relevant to PPBGN's activities. Hence, the scope of the meeting will be limited to discussion on the status of nuclear minerals exploration, mining, and extraction technologies in Indonesia as well as the related environmental and workplace safeties in uranium mining and milling. Ten technical papers were presented in meeting, including four topics on exploration status and technology, three subject matter on mining, two presentations on milling, and one paper on environmental and workplace safeties

  14. Meeting information

    Science.gov (United States)

    The 1986 Ocean Sciences Meeting of the American Geophysical Union and the American Society of Limnology and Oceanography (ASLO) will be held January 13-17, 1986, in New Orleans, La., at the Fairmont Hotel. Co-sponsoring societies are the Acoustical Society of America (ASA), the American Meteorological Society (AMS), the Marine Technology Society (MTS), and the Institute of Electrical and Electronics Engineers, Oceanic Engineering Society (OES).

  15. Compatibility of Safety Properties and Possibilistic Information Flow Security in MAKS

    OpenAIRE

    Bauereiss , Thomas; Hutter , Dieter

    2014-01-01

    Part 6: Information Flow Control; International audience; Motivated by typical security requirements of workflow management systems, we consider the integrated verification of both safety properties (e.g. separation of duty) and information flow security predicates of the MAKS framework (e.g. modeling confidentiality requirements). Due to the refinement paradox, enforcement of safety properties might violate possibilistic information flow properties of a system. We present an approach where s...

  16. 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.)

  17. 'What do patients want?' Tailoring medicines information to meet patients' needs.

    Science.gov (United States)

    Young, Amber; Tordoff, June; Smith, Alesha

    2017-11-01

    Medicines information leaflets can equip patients to be in control of their own healthcare and support the safe and effective use of medicines. The design and content of leaflets influences patients' willingness to read them, and poor examples can cause patient confusion and anxiety. Researchers examined the literature over the past 8 years to determine the content and design of medicine information leaflets that patients prefer in order to read, understand, and use them effectively. It was found that existing leaflets do not meet patients' needs and appear ineffective. Leaflets lack the information patients seek and may contain non-essential material, affecting patients' perception of, and willingness to read them. Additionally, the acceptable leaflet length varies between patients. Application of good design principles improves readability, comprehension, and ability to locate information. Medicine information leaflets must meet patients' needs and be well designed. Tailoring information leaflets to patient characteristics and requirements would enhance effectiveness. Passive provision of pre-printed leaflets is outdated, unvalued and ineffective. Using automated computer systems for leaflet tailoring with the ability to further adapt patients' information might be the best way forward. Copyright © 2016 Elsevier Inc. All rights reserved.

  18. The International Technical Safety Forum

    CERN Multimedia

    CERN Bulletin

    2010-01-01

    The International Technical Safety Forum is a meeting of safety experts from several physics labs in Europe and the US. Since 1998 participants have been meeting every couple of years to discuss common challenges in safety matters. The Forum helps them define best practices and learn from the important lessons learned by others.   The Forum's participants in front of building 40. This year, the meeting took place at CERN from 12 to 16 April. “This year's meeting covered subjects ranging from communication and training in matters of safety, to cryogenic safety, emergency preparedness and risk analysis”, explains Ralf Trant, head of the CERN Safety Commission and organiser of this year’s Forum. Radiation protection issues are not discussed at the meeting since they involve different expertise. The goal of the Forum is to allow participants to share experience, learn lessons and acquire specific knowledge in a very open way. Round-table discussions, dedicated time for ...

  19. Scientific Information Policy Board 90th Meeting

    CERN Multimedia

    AUTHOR|(CDS)2051371

    2017-01-01

    Gigi Rolandi, sitting in the middle, chairing his last meeting of the Scientific Information Policy Board before his retirement. Rolandi was the chairman of the board from March 2006 until April 2017, a period that has seen lots of dynamics within the field of authoring, publishing and librarianship - both at CERN and beyond. In the first row from left to right: Eckhard Elsen (Director of Research), Jens Vigen (Head Librarian) Gigi Rolandi (SIPB Chair), Anita Hollier (Archivist) and Urs Wiedemann (Theory). In the second row from left to right: Nikos Kasioumis (Invited speaker), Alexander Kohls (Invited speaker), Stella Christodoulaki (Invited speaker), Nick Ellis (Chair CREB), Clara Troncon (ACCU), Annette Holtkamp (Scientific Information Service), Tim Smith (IT) Brigitte Bloch-Devaux (non-LHC experiments), Constantinos Loizides (ALICE), Thierry Stora (Engineering), John Jowett (Beams), Arjan Verweij (Technology), Anne Gentil-Beccot (Scientific Information Service), Fergus Wilson (LHCb), Ludmila Marian (Invit...

  20. Safety and Security Interface Technology Initiative

    International Nuclear Information System (INIS)

    Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

    2007-01-01

    Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. ''Supporting Excellence in Operations Through Safety Analysis'', (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is ''Safeguards/Security Integration with Safety''. This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis/Security Documentation Integration, Configuration Control, and development of a shared ''tool box'' of information/successes. Specific Benefits. The expectation or end state resulting from the topical report and associated

  1. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2

    International Nuclear Information System (INIS)

    1996-08-01

    Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

  2. The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

    1999-01-01

    The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper

  3. Thermal analysis and safety information for metal nanopowders by DSC

    Energy Technology Data Exchange (ETDEWEB)

    Tseng, J.M.; Huang, S.T. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Duh, Y.S.; Hsieh, T.Y.; Sun, Y.Y. [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China); Lin, J.Z. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Wu, H.C. [Institute of Occupational Safety and Health, Council of Labor Affairs, Taipei, Taiwan, ROC (China); Kao, C.S., E-mail: jcsk@nuu.edu.tw [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China)

    2013-08-20

    Highlights: • Metal nanopowders are common and frequently employed in industry. • Nano iron powder experimental results of T{sub o} were 140–150 °C. • Safety information can benefit relevant metal powders industries. - Abstract: Metal nanopowders are common and frequently employed in industry. Iron is mostly applied in high-performance magnetic materials and pollutants treatment for groundwater. Zinc is widely used in brass, bronze, die casting metal, alloys, rubber, and paints, etc. Nonetheless, some disasters induced by metal powders are due to the lack of related safety information. In this study, we applied differential scanning calorimetry (DSC) and used thermal analysis software to evaluate the related thermal safety information, such as exothermic onset temperature (T{sub o}), peak of temperature (T{sub p}), and heat of reaction (ΔH). The nano iron powder experimental results of T{sub o} were 140–150 °C, 148–158 °C, and 141–149 °C for 15 nm, 35 nm, and 65 nm, respectively. The ΔH was larger than 3900 J/g, 5000 J/g, and 3900 J/g for 15 nm, 35 nm, and 65 nm, respectively. Safety information can benefit the relevant metal powders industries for preventing accidents from occurring.

  4. Health and safety in the nuclear age

    International Nuclear Information System (INIS)

    1988-01-01

    In their Communication to the Council on the development of Community measures for the application of Chapter III of the Euratom Treaty - Health and safety (COM(86) 434 final) the Commission of the European Communities announced their intention to initiate a 'Standing Conference on Health and Safety in the Nuclear Age' in order to contribute to an increase of information on nuclear activities. Following this proposition, the Commission (Directorate-General for Employment, Social Affairs and Education, Health and Safety Directorate) organized the first meeting of this Standing Conference in Luxembourg on 5, 6 and 7 October 1987 with the theme 'Information for the public and the media on health protection and safety with regard to nuclear activities'. About 120 participants representing scientific experts, the media, the bodies concerned with environmental or consumer protection, the social partners and interested national and international organizations, took part in this conference. It was the first time at European Community level that a meeting allowed an exchange of positions on the health problems related to ionizing radiation by all the parties interested in this subject. The Commission was asked to pursue this dialogue in order to improve the perception of citizens of the Community of the potential risks and the methods of protection brought into force in the nuclear field

  5. 78 FR 83 - Codex Alimentarius Commission: Meeting of the Codex Committee on Food Import and Export...

    Science.gov (United States)

    2013-01-02

    ...The Office of the Under Secretary for Food Safety, U.S. Department of Agriculture (USDA), Food Safety and Inspection Service (FSIS), is sponsoring a public meeting on January 24, 2013. The objective of the public meeting is to provide information and receive public comments on agenda items and draft United States (U.S.) positions that will be discussed at the 20th Session of the Codex Committee on Food Import and Export Inspection and Certification Systems (CCFICS) of the Codex Alimentarius Commission (Codex), which will be held in Chiang Mai, Thailand, February 18-22, 2013. The Under Secretary for Food Safety recognizes the importance of providing interested parties the opportunity to obtain background information on the 20th Session of the CCFICS and to address items on the agenda.

  6. Sports injuries, drowning and exposure to radiation concern Canada Safety Council meeting

    International Nuclear Information System (INIS)

    Oliver, Caroline.

    1979-01-01

    Hazards associated with surface sports, aquatic sports and exposure to radiation were considered at a meeting of the Canada Safety Council in late 1979. The session on radiation noted that 6 of 20000 radiation workers wearing dosimeters were exposed to a dose in excess of 5 rem, the annual limit set by the Atomic Energy Control Board. Radiographers were in the job classification receiving the highest doses of ionizing radiation. Concern was expressed for the emission of damaging radiation from broken mercury vapour lamps. Increased regulation rather than training was seen as the most effective solution. (T.I.)

  7. Safety challenges after the Fukushima accident. ANCCLI-IRSN work meeting

    International Nuclear Information System (INIS)

    Demet, Michel; Lheureux, Yves; Sene, Monique; Sene, Raymond; Eimer, Michel; Lachaume, Jean-Luc; Majnoni, Sophia; Marignac, Yves; Revol, Henri; Gilles, Compagnat; Baumont, David; Huet, Cyril; Rebour, Vincent; Besnus, Francois; Le Bars, Igor; Lizot, Marie-Therese; Carre, Christine; Dupuy, Patricia; Jorel, Martial; Lavarenne, Caroline; Rousseau, Jean-Marie; Charron, Sylvie; Gilli, Ludivine

    2011-11-01

    After a synthetic report of the meeting, this document contains Power Point presentations proposed by the different contributors. These presentations proposed: an overview on additional safety assessments (ECS) and an assessment of 'post-Fukushima' inspections performed in basic nuclear installations; the CLI's opinion on the Gravelines ECS report; an analysis and a discussion of ECS reports of nuclear installations in the perspective of the Fukushima accident; the IRSN analysis of ECS as they are performed by operators; a presentation of the IRSN analysis approach to ECS; contributions of different post-Fukushima ECS permanent groups within the IRSN (these work groups address installation condition, external flooding, and seismic risk); a presentation of the 'fusion prevention' aspects of the management of accidental situations in EDF reactors

  8. 75 FR 57102 - Occupational Information Development Advisory Panel Meeting; Correction

    Science.gov (United States)

    2010-09-17

    ... SOCIAL SECURITY ADMINISTRATION [Docket No. SSA-2010-0058] Occupational Information Development Advisory Panel Meeting; Correction AGENCY: Social Security Administration. ACTION: Notice; correction. SUMMARY: The Social Security Administration published a document in the Federal Register of September 13...

  9. Health and safety information program for hazardous materials

    International Nuclear Information System (INIS)

    O'Brien, M.P.; Fallon, N.J.; Kuehner, A.V.

    1979-01-01

    The system is used as a management tool in several safety and health programs. It is used to: trace the use of hazardous materials and to determine monitoring needs; inform the occupational physician of the potential health problems associated with materials ordered by a given individual; inform the fire and rescue group of hazardous materials in a given building; provide waste disposal recommendations to the hazardous waste management group; assist the hazardous materials shipping coordinator in identifying materials which are regulated by the Department of Transportation; and guide management decisions in the area of recognizing and rectifying unsafe conditions. The information system has been expanded from a manual effort to provide a brief description of health hazards of chemicals used at the lab to a computerized health and safety information system which serves the needs of all personnel who may encounter the material in the course of their work. The system has been designed to provide information needed to control the potential problems associated with a hazardous material up to the time that it is consumed in a given operation or is sent to the waste disposal facility

  10. Opportunities for Using Building Information Modeling to Improve Worker Safety Performance

    Directory of Open Access Journals (Sweden)

    Kasim Alomari

    2017-02-01

    Full Text Available Building information modelling (BIM enables the creation of a digital representation of a designed facility combined with additional information about the project attributes, performance criteria, and construction process. Users of BIM tools point to the ability to visualize the final design along with the construction process as a beneficial feature of using BIM. Knowing the construction process in relationship to a facility’s design benefits both safety professionals when planning worker safety measures for a project and designers when creating a project’s design. Success in using BIM to enhance safety partly depends on the familiarity of project personnel with BIM tools and the extent to which the tools can be used to identify and eliminate safety hazards. In a separate, ongoing study, the authors investigated the connection between BIM and safety to document the opportunities, barriers, and impacts. Utilizing an on-line survey of project engineers who work for construction firms together with a comprehensive literature review, the study found those who use BIM feel that it aids in communication of project information and project delivery, both of which have been found to have positive impacts on construction site safety. Further, utilizing the survey results, the authors apply the binary logistic regression econometric framework to better understand the factors that lead to safety professionals believing that BIM increases safety in the work place. In addition, according to the survey results, a large percentage of the engineers who use BIM feel that ultimately it helps to eliminate safety hazards and improve worker safety. The study findings suggest that improvements in safety performance across the construction industry may be due in part to increased use of BIM in the construction industry.

  11. The challenge of effectively communicating patient safety information.

    Science.gov (United States)

    Hugman, Bruce; Edwards, I Ralph

    2006-07-01

    Rational use of drugs and patient safety are seriously compromised by a lack of good information, education and effective communication at all stages of drug development and use. From animal trials through to dispensing, there are misconceptions and opportunities for error which current methods of drug information communication do not adequately address: they do not provide those responsible for prescribing and dispensing drugs with the data and information they need to pass on complex and often changing messages to patients and the public. The incidence of adverse reactions due to the way drugs are used; the variable impact of regulatory guidelines and warnings on prescribing behaviour; drug scares and crises suggest a great gap between the ideals of the safe use of medicines and the reality in homes, clinics and hospitals around the world. To address these challenges, the authors review the several levels at which safety information is generated and communicated, and examine how, at each stage, the content and its significance, and the method of communication can be improved.

  12. Safety culture in nuclear installations. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Carnino, A [ed.; International Atomic Energy Agency, Vienna (Austria); Weimann, G [ed.; Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria)

    1995-04-01

    These proceedings of the International Topical Meeting on Safety Culture in Nuclear Installations held in Vienna, Austria from 24 to 28 April 1995 provide a wide forum of information exchange and discussions on the topic safety culture in nuclear power plants. Safety culture deals with human factors since it deals with attitudes, organization and management. It then means that it has a natural component in it which is linked to the national culture and education. There are about 95 contributions, some of them presented by title and abstract only. All of them are in the subject scope of INIS. (Botek).

  13. Safety culture in nuclear installations. Proceedings

    International Nuclear Information System (INIS)

    Carnino, A.; Weimann, G.

    1995-04-01

    These proceedings of the International Topical Meeting on Safety Culture in Nuclear Installations held in Vienna, Austria from 24 to 28 April 1995 provide a wide forum of information exchange and discussions on the topic safety culture in nuclear power plants. Safety culture deals with human factors since it deals with attitudes, organization and management. It then means that it has a natural component in it which is linked to the national culture and education. There are about 95 contributions, some of them presented by title and abstract only. All of them are in the subject scope of INIS. (Botek)

  14. Information need about the safety of the final disposal of nuclear waste. Information receiver's views in Eurajoki, Kuhmo and Aeaenekoski municipalities

    International Nuclear Information System (INIS)

    Hautakangas, H.

    1997-03-01

    The study analyses the public's information need about the safety issues related to the final disposal of spent nuclear fuel generated by the Finnish nuclear power stations. Locals in three municipalities that are studied as possible sites for final disposal were interviewed for the study. Earlier studies made in Finland had indicated that the public's knowledge about safety issues related to the final disposal was almost opposite to the findings of the natural sciences. Also, the public had expressed a wish to receive more information from the safety authority, the Finnish Centre for Radiation and Nuclear Safety (STUK). This study therefore had two basic objectives: To find out what kind of safety information the locals need and what the safety authority's role could be in providing information. The main results show interest and need especially for information concerning the disposal phases taking place on the ground level, such as nuclear waste transportation and encapsulation. Also, the interviews show a clear need and desire for an impartial actor such as STUK in the information and communication process. (author) (107 refs.)

  15. High committee for transparency and information on nuclear safety: meeting of September 10, 2010

    International Nuclear Information System (INIS)

    2010-01-01

    After the approval of its rules of procedure and the designation of the High committee office, the members of the committee discuss the following topics: the High committee communication rules, various issues regarding radioactive wastes (activity of the low level waste work group, recent decisions made by the government on the process of selection of a low level waste storage site, perspectives and modalities of a public hearing organised by the committee according to the mission defined in the waste bill). Then, they discuss the environmental monitoring issue: organisation and strategy of radioactivity control in France by the French nuclear safety authority (ASN) and by the French institute for radiation protection and nuclear safety (IRSN), assessment of the radio-ecological status at the vicinity of basic nuclear installations

  16. Exchange of information between nuclear safety authorities: Policy of the French regulator

    International Nuclear Information System (INIS)

    Asty, Michel

    2000-01-01

    Full text: The decree setting up the Nuclear Safety Authority in 1973 entrusted it with international assignments whose objectives are still valid: - develop exchanges of information with foreign counterparts on regulatory systems and practices, on problems encountered in the nuclear safety field and on provisions made, with a view to enhancing its approach, and - becoming better acquainted with the actual operating practice of these Safety Authorities from which lessons could be learned for its own working procedures; - improving its position in the technical discussions with the French operators, since its arguments would be strengthened by practical knowledge of conditions abroad; - make known and explain the French approach and practices in the nuclear safety field and provide information on measures taken to deal with the problems encountered. This approach has several objectives: - promote the circulation of information on French positions on certain issues, such as very low level waste, for instance; - assist some countries wishing to create or modify their Nuclear Safety Authority, such as countries of the former USSR, the Central and Eastern European countries, and emerging countries on other continents; - help, when requested, foreign Safety Authorities required to issue permits for nuclear equipment of French origin; - provide the countries concerned with all relevant information on French nuclear installations located near their frontiers. Examples are given on the way the French Nuclear Safety Authority implements these objectives. (author)

  17. Impediments for the application of risk-informed decision making in nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2001-01-01

    A broad application of risk-informed decision making in the regulation of safety of nuclear power plants is hindered by the lack of quantitative risk and safety standards as well as of precise instruments to demonstrate an appropriate safety. An additional severe problem is associated with the difficulty to harmonize deterministic design requirements and probabilistic safety assessment. The problem is strengthened by the vulnerability of PSA for subjective influences and the potential of misuse. Beside this scepticism the nuclear community is encouraged to intensify the efforts to improve the quality standards for probabilistic safety assessments and their quality assurance. A prerequisite for reliable risk-informed decision making processes is also a well-defined and transparent relationship between deterministic and probabilistic safety approaches. (author)

  18. Proceeding of the Eighth Scientific Presentation on Nuclear Safety Technology

    International Nuclear Information System (INIS)

    Geni Rina Sunaryo; Sony Tjahjani, D.T.; Anhar Riza Antariksawan; Sudarno; Djoko Hari Nugroho; Roziq Himawan; Ari Satmoko; Histori; Sumijanto

    2003-02-01

    The Proceeding of Scientific Meeting and Presentation is routine activity that held in National Nuclear Energy Agency (BATAN) by Centre for Development of Nuclear Safety Technology for monitoring the research activity which was achieved in BATAN. The aims of the proceeding to able to information and reference for nuclear safety technology. There are 30 papers which separated index. (PPIN)

  19. Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

  20. 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.)

  1. 75 FR 39919 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-07-13

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, July 28 Public...

  2. 75 FR 64258 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-10-19

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, November 3 Public...

  3. 78 FR 63162 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-23

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, November 6...

  4. 78 FR 42753 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-17

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, July 31...

  5. 76 FR 64895 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-10-19

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, November 2 Public...

  6. 76 FR 39845 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-07-07

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, July 27 Public...

  7. Information meeting on the AD leaflets of the HP series

    International Nuclear Information System (INIS)

    1976-05-01

    The present brochure contains discussions and summaries of papers from an information meeting on new leaflets issued by the Arbeitsgemeinschaft Druckbehaelter, Reihe Herstellung und Pruefung (task group pressure vessels, production and testing section), organized by the TUEV of Bavaria. (RW) [de

  8. Selenide isotope generator for the Galileo Mission: safety test plan

    International Nuclear Information System (INIS)

    1979-01-01

    The intent of this safety test plan is to outline particular kinds of safety tests designed to produce information which would be useful in the safety analysis process. The program deals primarily with the response of the RTG to accident environments; accordingly two criteria were established: (1) safety tests should be performed for environments which are the most critical in terms of risk contribution; and (2) tests should be formulated to determine failure conditions for critical heat source components rather than observe heat source response in reference accident environments. To satisfy criterion 1. results of a recent safety study were used to rank various accidents in terms of expected source terms. Six kinds of tests were then proposed which would provide information meeting the second criterion

  9. DOE standard: Firearms safety

    International Nuclear Information System (INIS)

    1996-02-01

    Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements

  10. DOE standard: Firearms safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements.

  11. 78 FR 1198 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-08

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... to information systems equipment and technology. Wednesday, January 23 Open Session 1. Welcome and...

  12. 77 FR 37652 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-06-22

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... that affect the level of export controls applicable to information systems equipment and technology...

  13. 77 FR 1666 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-11

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... information systems equipment and technology. Wednesday, January 25 Open Session 1. Welcome and Introductions...

  14. Meeting the maglev system's safety requirements

    Energy Technology Data Exchange (ETDEWEB)

    Pierick, K

    1983-12-01

    The author shows how the safety requirements of the maglev track system derive from the general legal conditions for the safety of tracked transport. It is described how their compliance beyond the so-called ''development-accompanying'' and ''acceptance-preparatory'' safety work can be assured for the Transrapid test layout (TVE) now building in Emsland and also for later application as public transport system in Germany within the meaning of the General Railway Act.

  15. 78 FR 72063 - Open Meeting of the Information Security and Privacy Advisory Board

    Science.gov (United States)

    2013-12-02

    ... NIST on information security and privacy issues pertaining to federal computer systems. Details... Information Security and Privacy Advisory Board AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice. SUMMARY: The Information Security and Privacy Advisory Board (ISPAB) will meet...

  16. 78 FR 24160 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-24

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... controls applicable to information systems equipment and technology. Tuesday, May 7 Open Session 1. Welcome...

  17. 77 FR 24178 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-04-23

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... controls applicable to information systems equipment and technology. Tuesday, May 8 Open Session 1. Welcome...

  18. Use of computational fluid dynamics codes for safety analysis of nuclear reactor systems, including containment. Summary report of a technical meeting

    International Nuclear Information System (INIS)

    2003-11-01

    Safety analysis is an important tool for justifying the safety of nuclear power plants. Typically, this type of analysis is performed by means of system computer codes with one dimensional approximation for modelling real plant systems. However, in the nuclear area there are issues for which traditional treatment using one dimensional system codes is considered inadequate for modelling local flow and heat transfer phenomena. There is therefore increasing interest in the application of three dimensional computational fluid dynamics (CFD) codes as a supplement to or in combination with system codes. There are a number of both commercial (general purpose) CFD codes as well as special codes for nuclear safety applications available. With further progress in safety analysis techniques, the increasing use of CFD codes for nuclear applications is expected. At present, the main objective with respect to CFD codes is generally to improve confidence in the available analysis tools and to achieve a more reliable approach to safety relevant issues. An exchange of views and experience can facilitate and speed up progress in the implementation of this objective. Both the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) believed that it would be advantageous to provide a forum for such an exchange. Therefore, within the framework of the Working Group on the Analysis and Management of Accidents of the NEA's Committee on the Safety of Nuclear Installations, the IAEA and the NEA agreed to jointly organize the Technical Meeting on the Use of Computational Fluid Dynamics Codes for Safety Analysis of Reactor Systems, including Containment. The meeting was held in Pisa, Italy, from 11 to 14 November 2002. The publication constitutes the report of the Technical Meeting. It includes short summaries of the presentations that were made and of the discussions as well as conclusions and

  19. Feedback from incident reporting: information and action to improve patient safety.

    Science.gov (United States)

    Benn, J; Koutantji, M; Wallace, L; Spurgeon, P; Rejman, M; Healey, A; Vincent, C

    2009-02-01

    Effective feedback from incident reporting systems in healthcare is essential if organisations are to learn from failures in the delivery of care. Despite the wide-scale development and implementation of incident reporting in healthcare, studies in the UK suggest that information concerning system vulnerabilities could be better applied to improve operational safety within organisations. In this article, the findings and implications of research to identify forms of effective feedback from incident reporting are discussed, to promote best practices in this area. The research comprised a mixed methods review to investigate mechanisms of effective feedback for healthcare, drawing upon experience within established reporting programmes in high-risk industry and transport domains. Systematic searches of published literature were undertaken, and 23 case studies describing incident reporting programmes with feedback were identified for analysis from the international healthcare literature. Semistructured interviews were undertaken with 19 subject matter experts across a range of domains, including: civil aviation, maritime, energy, rail, offshore production and healthcare. In analysis, qualitative information from several sources was synthesised into practical requirements for developing effective feedback in healthcare. Both action and information feedback mechanisms were identified, serving safety awareness, improvement and motivational functions. The provision of actionable feedback that visibly improved systems was highlighted as important in promoting future reporting. Fifteen requirements for the design of effective feedback systems were identified, concerning: the role of leadership, the credibility and content of information, effective dissemination channels, the capacity for rapid action and the need for feedback at all levels of the organisation, among others. Above all, the safety-feedback cycle must be closed by ensuring that reporting, analysis and

  20. 'BeSAFE', effect-evaluation of internet-based, tailored safety information combined with personal counselling on parents' child safety behaviours: study design of a randomized controlled trial

    Directory of Open Access Journals (Sweden)

    van Beeck Eduard F

    2010-08-01

    Full Text Available Abstract Background Injuries in or around the home are the most important cause of death among children aged 0-4 years old. It is also a major source of morbidity and loss of quality of life. In order to reduce the number of injuries, the Consumer Safety Institute introduced the use of Safety Information Leaflets in the Netherlands to provide safety education to parents of children aged 0-4 years. Despite current safety education, necessary safety behaviours are still not taken by a large number of parents, causing unnecessary risk of injury among young children. In an earlier study an E-health module with internet-based, tailored safety information was developed and applied. It concerns an advice for parents on safety behaviours in their homes regarding their child. The aim of this study is to evaluate the effect of this safety information combined with personal counselling on parents' child safety behaviours. Methods/Design Parents who are eligible for the regular well-child visit with their child at child age 5-8 months are invited to participate in this study. Participating parents are randomized into one of two groups: 1 internet-based, tailored safety information combined with personal counselling (intervention group, or 2 personal counselling using the Safety Information Leaflets of the Consumer Safety Institute in the Netherlands for children aged 12 to 24 months (control group. All parents receive safety information on safety topics regarding the prevention of falling, poisoning, drowning and burning. Parents of the intervention group will access the internet-based, tailored safety information module when their child is approximately 10 months old. After completion of the assessment questions, the program compiles a tailored safety advice. The parents are asked to devise and inscribe a personal implementation intention. During the next well-child visit, the Child Health Clinic professional will discuss this tailored safety information

  1. Use of risk information to safety regulation. Fabrication facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of ISA (Integrated Safety Analysis) for uranium fuel fabrication/enrichment facilities has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. There are two major activities in the year. First one is a study on ISA procedure for external events such as earthquakes. Second one is that for chemical consequences such as UF6 and HF. Other than the activities a fundamental study on a policy of utilizing risk information was conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  2. Quantifying Safety Margin Using the Risk-Informed Safety Margin Characterization (RISMC)

    Energy Technology Data Exchange (ETDEWEB)

    Grabaskas, David; Bucknor, Matthew; Brunett, Acacia; Nakayama, Marvin

    2015-04-26

    The Risk-Informed Safety Margin Characterization (RISMC), developed by Idaho National Laboratory as part of the Light-Water Reactor Sustainability Project, utilizes a probabilistic safety margin comparison between a load and capacity distribution, rather than a deterministic comparison between two values, as is usually done in best-estimate plus uncertainty analyses. The goal is to determine the failure probability, or in other words, the probability of the system load equaling or exceeding the system capacity. While this method has been used in pilot studies, there has been little work conducted investigating the statistical significance of the resulting failure probability. In particular, it is difficult to determine how many simulations are necessary to properly characterize the failure probability. This work uses classical (frequentist) statistics and confidence intervals to examine the impact in statistical accuracy when the number of simulations is varied. Two methods are proposed to establish confidence intervals related to the failure probability established using a RISMC analysis. The confidence interval provides information about the statistical accuracy of the method utilized to explore the uncertainty space, and offers a quantitative method to gauge the increase in statistical accuracy due to performing additional simulations.

  3. Probabilistic safety criteria at the safety function/system level

    International Nuclear Information System (INIS)

    1989-09-01

    A Technical Committee Meeting was held in Vienna, Austria, from 26-30 January 1987. The objectives of the meeting were: to review the national developments of PSC at the level of safety functions/systems including future trends; to analyse basic principles, assumptions, and objectives; to compare numerical values and the rationale for choosing them; to compile the experience with use of such PSC; to analyse the role of uncertainties in particular regarding procedures for showing compliance. The general objective of establishing PSC at the level of safety functions/systems is to provide a pragmatic tool to evaluate plant safety which is placing emphasis on the prevention principle. Such criteria could thus lead to a better understanding of the importance to safety of the various functions which have to be performed to ensure the safety of the plant, and the engineering means of performing these functions. They would reflect the state-of-the-art in modern PSAs and could contribute to a balance in system design. This report, prepared by the participants of the meeting, reviews the current status and future trends in the field and should assist Member States in developing their national approaches. The draft of this document was also submitted to INSAG to be considered in its work to prepare a document on safety principles for nuclear power plants. Five papers presented at the meeting are also included in this publication. A separate abstract was prepared for each of these papers. Refs, figs and tabs

  4. Use of information technologies to contribute for optimizing the safety radiation management in Cuba

    International Nuclear Information System (INIS)

    Valdes Ramos, M.; Prendes Alonso, M.; Hernandez Saiz, A.; Manzano de Armas, J.

    2013-01-01

    This paper presents the results achieved in Cuba, with the development of a group of information management tools to implement radiation safety systemic and proactive approaches to safety and ICT supported. These tools were designed for different organisms with responsibility for the security at the country level, to the regulatory authority, for user entities, for individual monitoring services and other radiation protection services. It describes the philosophy of information management model used, the characteristics of the developed tools and their integration, the work performed for the homogenization of information available and the ability to capture and deliver data at different levels in decision making. The tools developed are based on the use of variables and indicators of importance to the safety and the systemic approach adopted allows to facilitate the optimization process for supervision of safety practices as well as contribute to the management of knowledge in radiation safety, through a synergistic combination of process data, information, information management systems, and the creative and innovative radiation safety experts

  5. THE FORMATION OF THE CONTOUR OF THE DOCUMENTED AND REAL FLIGHT SAFETY IN THE SYSTEM OF THE INFORMATION PROVISION OF SAFETY OF FLIGHTS

    Directory of Open Access Journals (Sweden)

    B. I. Bachkalo

    2015-01-01

    Full Text Available The article discusses the principles and mechanisms of formation of the contour of the real safety of flights and contour of the documented safety, allowing us to obtain information to control fligh safety. The proposed approach can be used in the algorithms of active on-board flight safety management system for the implementation of information support to the crew in flight and automatic control of flight safety.

  6. 77 FR 19278 - Informational Meeting on Nuclear Fuel Cycle Options

    Science.gov (United States)

    2012-03-30

    ... DEPARTMENT OF ENERGY Informational Meeting on Nuclear Fuel Cycle Options AGENCY: Office of Fuel... activities leading to a comprehensive evaluation and screening of nuclear fuel cycle options in 2013. At this... fuel cycle options developed for the evaluation and screening provides a comprehensive representation...

  7. 75 FR 42440 - Total Coliform Rule Revisions-Notice of Public Information Meetings

    Science.gov (United States)

    2010-07-21

    ... will be discussed include the cost and benefit information of the proposed rule and the planned... ENVIRONMENTAL PROTECTION AGENCY [FRL-9177-6] Total Coliform Rule Revisions--Notice of Public... Protection Agency (EPA) is hosting public information meetings on the proposed Revised Total Coliform Rule...

  8. 75 FR 36615 - Pipeline Safety: Information Collection Gas Distribution Annual Report Form

    Science.gov (United States)

    2010-06-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket No. PHMSA-RSPA-2004-19854] Pipeline Safety: Information Collection Gas Distribution Annual Report Form AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Request...

  9. Patient-Reported Safety Information: A Renaissance of Pharmacovigilance?

    Science.gov (United States)

    Härmark, Linda; Raine, June; Leufkens, Hubert; Edwards, I Ralph; Moretti, Ugo; Sarinic, Viola Macolic; Kant, Agnes

    2016-10-01

    The role of patients as key contributors in pharmacovigilance was acknowledged in the new EU pharmacovigilance legislation. This contains several efforts to increase the involvement of the general public, including making patient adverse drug reaction (ADR) reporting systems mandatory. Three years have passed since the legislation was introduced and the key question is: does pharmacovigilance yet make optimal use of patient-reported safety information? Independent research has shown beyond doubt that patients make an important contribution to pharmacovigilance signal detection. Patient reports provide first-hand information about the suspected ADR and the circumstances under which it occurred, including medication errors, quality failures, and 'near misses'. Patient-reported safety information leads to a better understanding of the patient's experiences of the ADR. Patients are better at explaining the nature, personal significance and consequences of ADRs than healthcare professionals' reports on similar associations and they give more detailed information regarding quality of life including psychological effects and effects on everyday tasks. Current methods used in pharmacovigilance need to optimise use of the information reported from patients. To make the most of information from patients, the systems we use for collecting, coding and recording patient-reported information and the methodologies applied for signal detection and assessment need to be further developed, such as a patient-specific form, development of a severity grading and evolution of the database structure and the signal detection methods applied. It is time for a renaissance of pharmacovigilance.

  10. Report on probabilistic safety assessment (PSA) quality assurance in utilization of risk information

    International Nuclear Information System (INIS)

    2006-12-01

    Recently in Japan, introduction of nuclear safety regulations using risk information such as probabilistic safety assessment (PSA) has been considered and utilization of risk information in the rational and practical measures on safety assurance has made a progress to start with the operation or inspection area. The report compiled results of investigation and studies of PSA quality assurance in risk-informed activities in the USA. Relevant regulatory guide and standard review plan as well as issues and recommendations were reviewed for technical adequacy and advancement of probabilistic risk assessment technology in risk-informed decision making. Useful and important information to be referred as issues in PSA quality assurance was identified. (T. Tanaka)

  11. JANNAF 28th Propellant Development and Characterization Subcommittee and 17th Safety and Environmental Protection Subcommittee Joint Meeting. Volume 1

    Science.gov (United States)

    Cocchiaro, James E. (Editor); Mulder, Edwin J. (Editor); Gomez-Knight, Sylvia J. (Editor)

    1999-01-01

    This volume contains 37 unclassified/unlimited-distribution technical papers that were presented at the JANNAF 28th Propellant Development & Characterization Subcommittee (PDCS) and 17th Safety & Environmental Protection Subcommittee (S&EPS) Joint Meeting, held 26-30 April 1999 at the Town & Country Hotel and the Naval Submarine Base, San Diego, California. Volume II contains 29 unclassified/limited-distribution papers that were presented at the 28th PDCS and 17th S&EPS Joint Meeting. Volume III contains a classified paper that was presented at the 28th PDCS Meeting on 27 April 1999. Topics covered in PDCS sessions include: solid propellant rheology; solid propellant surveillance and aging; propellant process engineering; new solid propellant ingredients and formulation development; reduced toxicity liquid propellants; characterization of hypergolic propellants; and solid propellant chemical analysis methods. Topics covered in S&EPS sessions include: space launch range safety; liquid propellant hazards; vapor detection methods for toxic propellant vapors and other hazardous gases; toxicity of propellants, ingredients, and propellant combustion products; personal protective equipment for toxic liquid propellants; and demilitarization/treatment of energetic material wastes.

  12. Risk-informed decision making a keystone in advanced safety assessment

    International Nuclear Information System (INIS)

    Reinhart, M.

    2007-01-01

    Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

  13. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE); Baumann, Erik [AREVA GmbH, Erlangen (Germany). Radiation Protection

    2016-12-15

    Summary report on the Key Topic 'Enhanced Safety and Operation Excellence' Focus Session 'Radiation Protection' of the 47{sup th} Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  14. 10 CFR 52.157 - Contents of applications; technical information in final safety analysis report.

    Science.gov (United States)

    2010-01-01

    ...; technical information in final safety analysis report. The application must contain a final safety analysis... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.157 Section 52.157 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

  15. 10 CFR 52.79 - Contents of applications; technical information in final safety analysis report.

    Science.gov (United States)

    2010-01-01

    ...; technical information in final safety analysis report. (a) The application must contain a final safety... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.79 Section 52.79 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

  16. Risk-informed approaches to assess ecological safety of facilities with radioactive waste

    International Nuclear Information System (INIS)

    Vashchenko, V.N.; Zlochevskij, V.V.; Skalozubov, V.I.

    2011-01-01

    Ingenious risk-informed methods to assess ecological safety of facilities with radioactive waste are proposed in the paper. Probabilistic norms on lethal outcomes and reliability of safety barriers are used as safety criteria. Based on the probability measures, it is established that ecological safety conditions are met for the standard criterion of lethal outcomes

  17. Factors shaping effective utilization of health information technology in urban safety-net clinics.

    Science.gov (United States)

    George, Sheba; Garth, Belinda; Fish, Allison; Baker, Richard

    2013-09-01

    Urban safety-net clinics are considered prime targets for the adoption of health information technology innovations; however, little is known about their utilization in such safety-net settings. Current scholarship provides limited guidance on the implementation of health information technology into safety-net settings as it typically assumes that adopting institutions have sufficient basic resources. This study addresses this gap by exploring the unique challenges urban resource-poor safety-net clinics must consider when adopting and utilizing health information technology. In-depth interviews (N = 15) were used with key stakeholders (clinic chief executive officers, medical directors, nursing directors, chief financial officers, and information technology directors) from staff at four clinics to explore (a) nonhealth information technology-related clinic needs, (b) how health information technology may provide solutions, and (c) perceptions of and experiences with health information technology. Participants identified several challenges, some of which appear amenable to health information technology solutions. Also identified were requirements for effective utilization of health information technology including physical infrastructural improvements, funding for equipment/training, creation of user groups to share health information technology knowledge/experiences, and specially tailored electronic billing guidelines. We found that despite the potential benefit that can be derived from health information technologies, the unplanned and uninformed introduction of these tools into these settings might actually create more problems than are solved. From these data, we were able to identify a set of factors that should be considered when integrating health information technology into the existing workflows of low-resourced urban safety-net clinics in order to maximize their utilization and enhance the quality of health care in such settings.

  18. National Waste Terminal Storage Program information meeting, December 7-8, 1976

    International Nuclear Information System (INIS)

    1976-01-01

    Volume II of the report comprises copies of the slides from the talks presented at the second session of the National Waste Terminal Storage Program information meeting. This session was devoted to geologic studies

  19. Information Management of Health and Safety at the Tarkwa Mine of ...

    African Journals Online (AJOL)

    Michael

    2016-06-01

    Jun 1, 2016 ... Information Management of Health and Safety at the Tarkwa ... heap leach technology. ... the quality of information was assessed using the content of information ..... managing library users' expectations; and reference service.

  20. Communications on nuclear, radiation, transport and waste safety: a practical handbook

    International Nuclear Information System (INIS)

    1999-04-01

    Basic requirements to be met by national infrastructures for radiation protection and safety are stated in the International basic safety Standards for Protection against Ionizing radiation and for safety of radiation Sources. These include a requirement 'to set up appropriate means of informing the public, its representatives and the information media about the health and safety aspects of activities involving exposure to radiation and about regulatory processes.' This publication is intended for national regulatory authorities, to provide them with guidance on the principles and methods that can be applied in communicating nuclear safety to different audiences under different circumstances. This report presumes the existence of adequate national infrastructure including an independent regulatory authority with sufficient powers and resources to meet its responsibilities

  1. Meeting Report: 2013 PDA Virus & TSE Safety Forum.

    Science.gov (United States)

    Willkommen, Hannelore; Blümel, Johannes; Brorson, Kurt; Chen, Dayue; Chen, Qi; Gröner, Albrecht; Hubbard, Brian R; Kreil, Thomas R; Ruffing, Michel; Ruiz, Sol; Scott, Dorothy; Silvester, Glenda

    2014-01-01

    The report provides a summary of the presentations and discussions at the Virus & TSE Safety Forum 2013 organized by the Parenteral Drug Association (PDA) and held in Berlin, Germany, from June 4 to 6, 2013. The conference was accompanied by a workshop, "Virus Spike Preparations and Virus Removal by Filtration: New Trends and Developments". The presentations and the discussion at the workshop are summarized in a separate report that will be published in this issue of the journal as well. As with previous conferences of this series, the PDA Virus & TSE Safety Forum 2013 provided again an excellent opportunity to exchange information and opinions between the industry, research organizations, and regulatory bodies. Updates on regulatory considerations related to virus and transmissible spongiform encephalopathy (TSE) safety of biopharmaceuticals were provided by agencies of the European Union (EU), the United States (US), and Singapore. The epidemiology and detection methods of new emerging pathogens like hepatitis E virus and parvovirus (PARV 4) were exemplified, and the risk of contamination of animal-derived raw materials like trypsin was considered in particular. The benefit of using new sequence-based virus detection methods was discussed. Events of bioreactor contaminations in the past drew the attention to root cause investigations and preventive actions, which were illustrated by several examples. Virus clearance data of specific unit operations were provided; the discussion focused on the mechanism of virus clearance and on the strategic concept of viral clearance integration. As in previous years, the virus safety section was followed by a TSE section that covered recent scientific findings that may influence the risk assessment of blood and cell substrates. These included the realization that interspecies transmission of TSE by blood components in sheep is greater than predicted by assays in transgenic mice. Also, the pathogenesis and possibility of

  2. Extrabudgetary programme on the safety of nuclear installations in South East Asia Pacific and Far East countries. Report of the consultative meeting

    International Nuclear Information System (INIS)

    1997-07-01

    Based on the good experience with the rapid expansion of nuclear utilization in Japan and South Korea, China is planning to significantly expand its nuclear programme, and other countries in the region are likely to follow this example in order to meet their expected high electricity demand growth. The building of NPPs is being considered in Indonesia, Malaysia, the Philippines, Thailand, and Vietnam. It is however recognized that countries in the region are in different stages of nuclear power programme, and that their needs for assistance in nuclear safety will be substantially different. In this situation it would be advantageous for all countries to establish regional co-operation on nuclear safety to learn from each other, use the experience accumulated in the world, and to commonly assess the progress made in nuclear safety matters. The objective of this Consultative Meeting was to discuss co-operation and the needs for assistance by Member States in South-East Asia, Pacific and Far East to strengthen the safety of their nuclear installations. Refs, figs, tabs

  3. Proceedings of the fourth annual participants' information meeting, DOE Low-Level Waste Management Program

    International Nuclear Information System (INIS)

    Large, D.E.; Mezga, L.J.; Stratton, L.E.; Rose, R.R.

    1982-10-01

    The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base

  4. 75 FR 13258 - Announcing a Meeting of the Information Security and Privacy Advisory Board

    Science.gov (United States)

    2010-03-19

    ... Director of OMB on information security and privacy issues pertaining to Federal government information... Information Security and Privacy Advisory Board AGENCY: National Institute of Standards and Technology... hereby given that the Information Security and Privacy Advisory Board (ISPAB) will meet Wednesday, April...

  5. Convention on nuclear safety. Final act

    International Nuclear Information System (INIS)

    1994-01-01

    The Diplomatic Conference, which was convened by the International Atomic Energy Agency at its Headquarters from 14 to 17 June 1994, adopted the Convention on Nuclear Safety reproduced in document INFCIRC/449 and the Final Act of the Conference. The text of the Final Act of the Conference, including an annexed document entitled ''Some clarification with respect to procedural and financial arrangements, national reports, and the conduct of review meetings, envisaged in the Convention on Nuclear Safety'', is reproduced in the Attachment hereto for the information of all Member States

  6. Measuring and improving patient safety through health information technology: The Health IT Safety Framework.

    Science.gov (United States)

    Singh, Hardeep; Sittig, Dean F

    2016-04-01

    Health information technology (health IT) has potential to improve patient safety but its implementation and use has led to unintended consequences and new safety concerns. A key challenge to improving safety in health IT-enabled healthcare systems is to develop valid, feasible strategies to measure safety concerns at the intersection of health IT and patient safety. In response to the fundamental conceptual and methodological gaps related to both defining and measuring health IT-related patient safety, we propose a new framework, the Health IT Safety (HITS) measurement framework, to provide a conceptual foundation for health IT-related patient safety measurement, monitoring, and improvement. The HITS framework follows both Continuous Quality Improvement (CQI) and sociotechnical approaches and calls for new measures and measurement activities to address safety concerns in three related domains: 1) concerns that are unique and specific to technology (e.g., to address unsafe health IT related to unavailable or malfunctioning hardware or software); 2) concerns created by the failure to use health IT appropriately or by misuse of health IT (e.g. to reduce nuisance alerts in the electronic health record (EHR)), and 3) the use of health IT to monitor risks, health care processes and outcomes and identify potential safety concerns before they can harm patients (e.g. use EHR-based algorithms to identify patients at risk for medication errors or care delays). The framework proposes to integrate both retrospective and prospective measurement of HIT safety with an organization's existing clinical risk management and safety programs. It aims to facilitate organizational learning, comprehensive 360 degree assessment of HIT safety that includes vendor involvement, refinement of measurement tools and strategies, and shared responsibility to identify problems and implement solutions. A long term framework goal is to enable rigorous measurement that helps achieve the safety

  7. 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...

  8. Topical session proceedings of the 6. IGSC Meeting. The role of monitoring in a safety case

    International Nuclear Information System (INIS)

    2005-01-01

    This report summarises the outcomes of a topical session focused on the role of monitoring in a safety case. It was held as part of the 6. plenary meeting of the IGSC. It was attended by 39 participants, representing waste management organisations and regulatory authorities from 15 NEA member countries, the IAEA and the European Commission. The main purpose of this topical session was to create a platform for exchanging views on the key monitoring issues of interest to build confidence in a safety case e.g. relationship with the post-closure phase, functions, requirements, and to determine to what extent the main actions are to be addressed by the IGSC on its ongoing activities on defining the elements of a safety case. The topical session was indeed mainly aimed at exchanging information on: - National strategies or programmes in NEA members' countries. Member countries have organisations planning their own strategy, but some are already, to some extend engaged in implementing monitoring activities, e.g. Posiva Oy, US-DOE-YM, Andra. - Feedback from international projects, e.g. the EC Thematic Network on 'The role of Monitoring in a Phased Approach to Geological Disposal of Radioactive Waste', and the IAEA programme of work. - The expectations of regulators, e.g. SKI. Part A of this document summarises the material orally presented and provides the main lessons drawn from the presentations and the discussions that followed them. The overheads presented are compiled without any further elaboration by the NEA Secretariat as Part B of the document. Part C gives the list of participants. The document as a whole provides a synthesis of current issues in monitoring of a deep geological disposal facility

  9. 15. Experts' meeting on monitoring environmental radioactivity. Data - models - information. Proceedings

    International Nuclear Information System (INIS)

    2014-01-01

    The proceedings of the 15. Experts' meeting on monitoring environmental radioactivity include contributions o the following topics: environmental monitoring in Germany; developments in emergency protection and environmental monitoring; implementation of model and information systems; measuring programs during events and exercises; public information during local and global events; fast and (new) analytical methods; measures of the quality management systems; European and international environmental monitoring harmonization.

  10. Safety and Security Interface Technology Initiative

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

    2007-05-01

    Safety and Security Interface Technology Initiative Mr. Kevin J. Carroll Dr. Robert Lowrie, Dr. Micheal Lehto BWXT Y12 NSC Oak Ridge, TN 37831 865-576-2289/865-241-2772 carrollkj@y12.doe.gov Work Objective. Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. “Supporting Excellence in Operations Through Safety Analysis,” (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is “Safeguards/Security Integration with Safety.” This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis

  11. Technical Meeting on Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    2015-01-01

    A major focus of the design of modern fast reactor systems is on inherent and passive safety. Specific systems to improve reactor safety performance during accidental transients have been developed in nearly all fast reactor programs, and a large number of proposed systems have reached various stages of maturity. This Technical Meeting on Passive Shutdown Systems for Fast Reactors, which was recommended by the Technical Working Group on Fast Reactors (TWG-FR), addressed Member States’ expressed need for information exchange on projects and programs in the field, as well as for the identification of priorities based on the analysis of technology gaps to be covered through R&D activities. This meeting was limited to shutdown systems only, and did not include other passive features such as natural circulation decay heat removal systems etc.; however the meeting catered to passive shutdown safety devices applicable to all types of fast neutron systems. It was agreed to initiate a new study and produce a Nuclear Energy Series (NES) Technical Report to collect information about the existing operational systems as well as innovative concepts under development. This will be a useful source for member states interested in gaining technical expertise to develop passive shutdown systems as well as to highlight the importance and development in this area

  12. Gas-cooled reactor safety and accident analysis

    International Nuclear Information System (INIS)

    1985-12-01

    The Specialists' Meeting on Gas-Cooled Reactor Safety and Accident Analysis was convened by the International Atomic Energy Agency in Oak Ridge on the invitation of the Department of Energy in Washington, USA. The meeting was hosted by the Oak Ridge National Laboratory. The purpose of the meeting was to provide an opportunity to compare and discuss results of safety and accident analysis of gas-cooled reactors under development, construction or in operation, to review their lay-out, design, and their operational performance, and to identify areas in which additional research and development are needed. The meeting emphasized the high safety margins of gas-cooled reactors and gave particular attention to the inherent safety features of small reactor units. The meeting was subdivided into four technical sessions: Safety and Related Experience with Operating Gas-Cooled Reactors (4 papers); Risk and Safety Analysis (11 papers); Accident Analysis (9 papers); Miscellaneous Related Topics (5 papers). A separate abstract was prepared for each of these papers

  13. 75 FR 55616 - NASA Advisory Council; Information Technology Infrastructure Committee; Meeting

    Science.gov (United States)

    2010-09-13

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: (10-110)] NASA Advisory Council...-463, as amended, the National Aeronautics and Space Administration (NASA) announce a meeting for the Information Technology Infrastructure Committee of the NASA Advisory Council (NAC). DATES: Tuesday, September...

  14. 78 FR 54454 - Open Meeting of the Information Security and Privacy Advisory Board

    Science.gov (United States)

    2013-09-04

    ... security and privacy issues pertaining to federal computer systems. Details regarding the ISPAB's... Information Security and Privacy Advisory Board AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice. SUMMARY: The Information Security and Privacy Advisory Board (ISPAB) will meet...

  15. Patterns of patient safety culture: a complexity and arts-informed project of knowledge translation.

    Science.gov (United States)

    Mitchell, Gail J; Tregunno, Deborah; Gray, Julia; Ginsberg, Liane

    2011-01-01

    The purpose of this paper is to describe patterns of patient safety culture that emerged from an innovative collaboration among health services researchers and fine arts colleagues. The group engaged in an arts-informed knowledge translation project to produce a dramatic expression of patient safety culture research for inclusion in a symposium. Scholars have called for a deeper understanding of the complex interrelationships among structure, process and outcomes relating to patient safety. Four patterns of patient safety culture--blinding familiarity, unyielding determination, illusion of control and dismissive urgency--are described with respect to how they informed creation of an arts-informed project for knowledge translation.

  16. 77 FR 38319 - Open Meeting of the Advisory Committee on Water Information

    Science.gov (United States)

    2012-06-27

    ... Data Portal; a report on the Hydrologic Frequency Analysis Work Group's progress on revising Bulletin... technical societies. For more information on the ACWI, its membership, subgroups, meetings and activities...

  17. Health Information Technology in Healthcare Quality and Patient Safety: Literature Review.

    Science.gov (United States)

    Feldman, Sue S; Buchalter, Scott; Hayes, Leslie W

    2018-06-04

    The area of healthcare quality and patient safety is starting to use health information technology to prevent reportable events, identify them before they become issues, and act on events that are thought to be unavoidable. As healthcare organizations begin to explore the use of health information technology in this realm, it is often unclear where fiscal and human efforts should be focused. The purpose of this study was to provide a foundation for understanding where to focus health information technology fiscal and human resources as well as expectations for the use of health information technology in healthcare quality and patient safety. A literature review was conducted to identify peer-reviewed publications reporting on the actual use of health information technology in healthcare quality and patient safety. Inductive thematic analysis with open coding was used to categorize a total of 41 studies. Three pre-set categories were used: prevention, identification, and action. Three additional categories were formed through coding: challenges, outcomes, and location. This study identifies five main categories across seven study settings. A majority of the studies used health IT for identification and prevention of healthcare quality and patient safety issues. In this realm, alerts, clinical decision support, and customized health IT solutions were most often implemented. Implementation, interface design, and culture were most often noted as challenges. This study provides valuable information as organizations determine where they stand to get the most "bang for their buck" relative to health IT for quality and patient safety. Knowing what implementations are being effectivity used by other organizations helps with fiscal and human resource planning as well as managing expectations relative to cost, scope, and outcomes. The findings from this scan of the literature suggest that having organizational champion leaders that can shepherd implementation, impact culture

  18. Russia power engineering and power safety

    International Nuclear Information System (INIS)

    D'yakov, A.F.

    1995-01-01

    Results of work of the International consultative meeting: Russian-Europe: strategy of energy safety is described. The purpose of the meeting consisted in discussion of energy situation in Russia and Europe, prospects for provision of reliability, efficiency and safety of fuel and power supply in Russia and the role of the Russian fuel and power resonances in energy supply of Europe. The reporters at the meeting dealt with various aspects related to energy safety

  19. Information security as part of the nuclear safety culture

    Energy Technology Data Exchange (ETDEWEB)

    Sitnica, A., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Co., 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2016-09-15

    No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

  20. Information security as part of the nuclear safety culture

    International Nuclear Information System (INIS)

    Sitnica, A.

    2016-09-01

    No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

  1. Undergraduate Organic Chemistry Laboratory Safety

    Science.gov (United States)

    Luckenbaugh, Raymond W.

    1996-11-01

    Each organic chemistry student should become familiar with the educational and governmental laboratory safety requirements. One method for teaching laboratory safety is to assign each student to locate safety resources for a specific class laboratory experiment. The student should obtain toxicity and hazardous information for all chemicals used or produced during the assigned experiment. For example, what is the LD50 or LC50 for each chemical? Are there any specific hazards for these chemicals, carcinogen, mutagen, teratogen, neurotixin, chronic toxin, corrosive, flammable, or explosive agent? The school's "Chemical Hygiene Plan", "Prudent Practices for Handling Hazardous Chemicals in the Laboratory" (National Academy Press), and "Laboratory Standards, Part 1910 - Occupational Safety and Health Standards" (Fed. Register 1/31/90, 55, 3227-3335) should be reviewed for laboratory safety requirements for the assigned experiment. For example, what are the procedures for safe handling of vacuum systems, if a vacuum distillation is used in the assigned experiment? The literature survey must be submitted to the laboratory instructor one week prior to the laboratory session for review and approval. The student should then give a short presentation to the class on the chemicals' toxicity and hazards and describe the safety precautions that must be followed. This procedure gives the student first-hand knowledge on how to find and evaluate information to meet laboartory safety requirements.

  2. Establishing management information system to solve the information management problem of nuclear safety related personnel's qualification management

    International Nuclear Information System (INIS)

    Sun Haipeng; Liu Zhijun; Li Tianshu

    2013-01-01

    With the rapid progress of nuclear energy and nuclear technology utilization, nuclear safety related personnel play an increasingly important role in ensuring nuclear safety. NNSA personnel qualification management information system conducts a multi-faceted, effective, real-time monitoring and information collection for nuclear safety staff practice unit management, knowledge management, license application, appraisal management or supervision, training management or supervision and certified staff management, and also is a milestone for NNSA to build the state department with 'five-feature' (learning-oriented, service-oriented, economical, innovative, clean-type). (authors)

  3. Jefferson Lab IEC 61508/61511 Safety PLC Based Safety System

    International Nuclear Information System (INIS)

    Mahoney, Kelly; Robertson, Henry

    2009-01-01

    This paper describes the design of the new 12 GeV Upgrade Personnel Safety System (PSS) at the Thomas Jefferson National Accelerator Facility (TJNAF). The new PSS design is based on the implementation of systems designed to meet international standards IEC61508 and IEC 61511 for programmable safety systems. In order to meet the IEC standards, TJNAF engineers evaluated several SIL 3 Safety PLCs before deciding on an optimal architecture. In addition to hardware considerations, software quality standards and practices must also be considered. Finally, we will discuss R and D that may lead to both high safety reliability and high machine availability that may be applicable to future accelerators such as the ILC.

  4. Proceedings of the seventh annual participants' information meeting. DOE Low-Level Waste Management Program

    International Nuclear Information System (INIS)

    1986-02-01

    The Seventh Annual Department of Energy (DOE) Low-Level Waste Management Program (LLWMP) Participants' Information Meeting was held September 10-13, 1985 in Las Vegas, Nevada. The purpose of the meeting was to provide a forum for exchange of information on low-level radioactive waste management activities, requirements, and plans. Attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, interim operations offices and their contractor operators; representatives from the US Nuclear Regulatory Commission, US Environmental Protection Agency, US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of Great Britain, France, and Canada; representatives of utilities, private contractors, and parties concerned with low-level waste management issues. The meeting was organized by topical areas to allow for the exchange of information and the promotion of discussion on specific aspects of low-level waste management. Plenary sessions were held at the start and conclusion of the meeting while seven concurrent topical sessions were held during the intervening day and a half. Session chairmen from each of these concurrent sessions presented a summary of the discussion and conclusions resulting from their respective sessions at the final plenary session

  5. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  6. National nuclear safety report 1998. Convention on nuclear safety

    International Nuclear Information System (INIS)

    1998-01-01

    The Argentine Republic subscribed the Convention on Nuclear Safety, approved by a Diplomatic Conference in Vienna, Austria, in June 17th, 1994. According to the provisions in Section 5th of the Convention, each Contracting Party shall submit for its examination a National Nuclear Safety Report about the measures adopted to comply with the corresponding obligations. This Report describes the actions that the Argentine Republic is carrying on since the beginning of its nuclear activities, showing that it complies with the obligations derived from the Convention, in accordance with the provisions of its Article 4. The analysis of the compliance with such obligations is based on the legislation in force, the applicable regulatory standards and procedures, the issued licenses, and other regulatory decisions. The corresponding information is described in the analysis of each of the Convention Articles constituting this Report. The present National Report has been performed in order to comply with Article 5 of the Convention on Nuclear Safety, and has been prepared as much as possible following the Guidelines Regarding National Reports under the Convention on Nuclear Safety, approved in the Preparatory Meeting of the Contracting Parties, held in Vienna in April 1997. This means that the Report has been ordered according to the Articles of the Convention on Nuclear Safety and the contents indicated in the guidelines. The information contained in the articles, which are part of the Report shows the compliance of the Argentine Republic, as a contracting party of such Convention, with the obligations assumed

  7. Food Safety and Nutrition Information for Kids and Teens

    Science.gov (United States)

    ... Vaccines, Blood & Biologics Animal & Veterinary Cosmetics Tobacco Products Food Home Food Resources for You Consumers Kids & Teens ... More sharing options Linkedin Pin it Email Print Food Safety & Nutrition Information for Kids and Teens Fun & ...

  8. 76 FR 14896 - Multi-Agency Informational Meeting Concerning Compliance With the Federal Select Agent Program...

    Science.gov (United States)

    2011-03-18

    ... specific regulatory guidance and information on standards concerning biosafety and biosecurity issues... assessments, biosafety requirements, and security measures. DATES: The meeting will be held on May 10, 2011... meeting to address questions and concerns. Entity registration, security risk assessments, biosafety...

  9. The accident at Chernobyl and its implications for the safety of CANDU reactors

    International Nuclear Information System (INIS)

    1987-05-01

    In August 1986, a delegation of Canadians, including two members of the staff of the AECB (Atomic Energy Control Board), attended a post-accident review meeting in Vienna, at which Soviet representatives described the accident and its causes and consequences. On the basis of the information presented at that meeting, AECB staff conducted a study of the accident to ascertain its implications for the safety of CANDU nuclear reactors and for the regulatory process in Canada. The conclusion of this review is that the accident at Chernobyl has not revealed any important new information which would have an effect on the safety requirements for CANDU reactors as presently applied by the AECB. All important aspects of the accident and its causes have been considered by the AECB in the licensing process for currently licensed reactors. However a number of recommendations are made with respect to aspects of reactor safety which should be re-examined in order to reinforce this conclusion

  10. Proceedings of the fourth annual participants' information meeting, DOE Low-Level Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Large, D.E.: Mezga, L.J.; Stratton, L.E.; Rose, R.R. (comps.)

    1982-10-01

    The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base.

  11. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Byun, Jaehyung; Seo, Jonghwan [Dong-A Univ., Busan (Korea, Republic of)

    2013-05-15

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  12. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    International Nuclear Information System (INIS)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina; Byun, Jaehyung; Seo, Jonghwan

    2013-01-01

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  13. Safety Requirements and Modern Technical Requirements in Human Information Systems in Amman Hotels

    OpenAIRE

    Farouq Ahmad Alazzam; Sattam Rakan Allahawiah; Mohammad Nayef Alsarayreh; Kafa Hmoud Abdallah al Nawaiseh

    2015-01-01

    This study aimed to demonstrate the availability of Safety requirements and modern technical requirements in human information systems in Amman hotels. an the most important results of this study is the availability of security and safety requirements in human information systems In Amman hotels and The adequacy of the information that it provided .and show that all departments are not connected by appropriate and effective communication networks in adequate form . Also sophisticated operatin...

  14. Riding on air: critical safety information for you and your tires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This booklet is issued for public distribution by Transport Canada. It provides a few simple tips concerning automobile tire safety which, if followed, is expected to result in increased personal and vehicle safety, improved fuel economy, prolonged tire life, energy savings and reduced environmental pollution. The information provided include tips about tire pressure, tire inspection for damage and wear, rotation of tires for more even wear, replacing worn tires, the advantages of using snow tires in winter and an explanation of the meaning of the information found on the tire sidewall.

  15. A risk-informed perspective on deterministic safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Wan, P.T.

    2009-01-01

    In this work, the deterministic safety analysis (DSA) approach to nuclear safety is examined from a risk-informed perspective. One objective of safety analysis of a nuclear power plant is to demonstrate via analysis that the risks to the public from events or accidents that are within the design basis of the power plant are within acceptable levels with a high degree of assurance. This nuclear safety analysis objective can be translated into two requirements on the risk estimates of design basis events or accidents: the nominal risk estimate to the public must be shown to be within acceptable levels, and the uncertainty in the risk estimates must be shown to be small on an absolute or relative basis. The DSA approach combined with the defense-in-depth (DID) principle is a simplified safety analysis approach that attempts to achieve the above safety analysis objective in the face of potentially large uncertainties in the risk estimates of a nuclear power plant by treating the various uncertainty contributors using a stylized conservative binary (yes-no) approach, and applying multiple overlapping physical barriers and defense levels to protect against the release of radioactivity from the reactor. It is shown that by focusing on the consequence aspect of risk, the previous two nuclear safety analysis requirements on risk can be satisfied with the DSA-DID approach to nuclear safety. It is also shown the use of multiple overlapping physical barriers and defense levels in the traditional DSA-DID approach to nuclear safety is risk-informed in the sense that it provides a consistently high level of confidence in the validity of the safety analysis results for various design basis events or accidents with a wide range of frequency of occurrence. It is hoped that by providing a linkage between the consequence analysis approach in DSA with a risk-informed perspective, greater understanding of the limitation and capability of the DSA approach is obtained. (author)

  16. Preliminary safety information document for the standard MHTGR. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-01-01

    This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)

  17. HANFORD SAFETY ANALYSIS & RISK ASSESSMENT HANDBOOK (SARAH)

    Energy Technology Data Exchange (ETDEWEB)

    EVANS, C B

    2004-12-21

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

  18. Evaluating and Predicting Patient Safety for Medical Devices With Integral Information Technology

    Science.gov (United States)

    2005-01-01

    323 Evaluating and Predicting Patient Safety for Medical Devices with Integral Information Technology Jiajie Zhang, Vimla L. Patel, Todd R...errors are due to inappropriate designs for user interactions, rather than mechanical failures. Evaluating and predicting patient safety in medical ...the users on the identified trouble spots in the devices. We developed two methods for evaluating and predicting patient safety in medical devices

  19. HANFORD SAFETY ANALYSIS and RISK ASSESSMENT HANDBOOK (SARAH)

    International Nuclear Information System (INIS)

    EVANS, C.B.

    2004-01-01

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S and M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard

  20. An approach for risk informed safety culture assessment for Canadian nuclear power stations

    International Nuclear Information System (INIS)

    Nelson, W.R.

    2010-01-01

    One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

  1. Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

  2. Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

    International Nuclear Information System (INIS)

    Song, Tae Young

    2007-01-01

    At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

  3. Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

    Energy Technology Data Exchange (ETDEWEB)

    Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

    2007-07-01

    At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

  4. Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G. (comps.)

    1981-12-01

    The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base.

  5. Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program

    International Nuclear Information System (INIS)

    Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G.

    1981-12-01

    The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base

  6. NASA Aviation Safety Program Weather Accident Prevention/weather Information Communications (WINCOMM)

    Science.gov (United States)

    Feinberg, Arthur; Tauss, James; Chomos, Gerald (Technical Monitor)

    2002-01-01

    Weather is a contributing factor in approximately 25-30 percent of general aviation accidents. The lack of timely, accurate and usable weather information to the general aviation pilot in the cockpit to enhance pilot situational awareness and improve pilot judgment remains a major impediment to improving aviation safety. NASA Glenn Research Center commissioned this 120 day weather datalink market survey to assess the technologies, infrastructure, products, and services of commercial avionics systems being marketed to the general aviation community to address these longstanding safety concerns. A market survey of companies providing or proposing to provide graphical weather information to the general aviation cockpit was conducted. Fifteen commercial companies were surveyed. These systems are characterized and evaluated in this report by availability, end-user pricing/cost, system constraints/limits and technical specifications. An analysis of market survey results and an evaluation of product offerings were made. In addition, recommendations to NASA for additional research and technology development investment have been made as a result of this survey to accelerate deployment of cockpit weather information systems for enhancing aviation safety.

  7. Memorandum on the use of information technology to improve medication safety.

    Science.gov (United States)

    Ammenwerth, E; Aly, A-F; Bürkle, T; Christ, P; Dormann, H; Friesdorf, W; Haas, C; Haefeli, W E; Jeske, M; Kaltschmidt, J; Menges, K; Möller, H; Neubert, A; Rascher, W; Reichert, H; Schuler, J; Schreier, G; Schulz, S; Seidling, H M; Stühlinger, W; Criegee-Rieck, M

    2014-01-01

    Information technology in health care has a clear potential to improve the quality and efficiency of health care, especially in the area of medication processes. On the other hand, existing studies show possible adverse effects on patient safety when IT for medication-related processes is developed, introduced or used inappropriately. To summarize definitions and observations on IT usage in pharmacotherapy and to derive recommendations and future research priorities for decision makers and domain experts. This memorandum was developed in a consensus-based iterative process that included workshops and e-mail discussions among 21 experts coordinated by the Drug Information Systems Working Group of the German Society for Medical Informatics, Biometry and Epidemiology (GMDS). The recommendations address, among other things, a stepwise and comprehensive strategy for IT usage in medication processes, the integration of contextual information for alert generation, the involvement of patients, the semantic integration of information resources, usability and adaptability of IT solutions, and the need for their continuous evaluation. Information technology can help to improve medication safety. However, challenges remain regarding access to information, quality of information, and measurable benefits.

  8. NCIS: a nuclear criticality information system

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1984-01-01

    The NCIS is one of the developments carried out to meet the requirements in the field of criticality safety information. Its primary goal is to enhance nuclear criticality safety by dissemination of data, standards, and training material. This paper presents the ''NCIS'' progess since 1950: computer-searching, database management, nuclear critical experiments bibliography. American Nuclear Society transactions criticality safety publications compilation, edition of a personnel directory representing over 140 organizations located in 16 countries and showing a wide range of specialists involved in the field of nuclear criticality safety. The NCIS uses the information management and communication resources of TIS (Technology Information System): automated access procedures; creation of program-dependent information systems; communications. The NCIS is still in a growing, formative stage; it has concentrated first on collecting and organizing the nuclear criticality literature; nuclear critical data, calculational tools, standards, and training materials will follow. Finally the planned and contemplated resources are dealt with: expansion of bibliographic compilations; news database; fundamental criticality safety reference; criticality benchmarck database; user community; training resources; related resources; criticality accident database; dynamic databook; dynamic textbook; expert knowledge system; and, extraction of intelligence

  9. Development of Necessary Technology for Safety Grade I and C System

    International Nuclear Information System (INIS)

    Lee, Dong Young; Jang, Tong Il; Kim, Jung Tack

    2010-08-01

    Through KNICS and Nu-Tech 2012, a MMIS(Man-Machine Interface System) package for nuclear plants was localized and is expected to be applied to SUN 1,2 plants. This study is aimed to support the application of the MMIS package including the following technologies that meet strengthened regulation requirements and enhanced utility's performance requirements to nuclear plants. - Dedication to safety-grade computers - The broadband communication network for safety information - Application of the automatic test for safety systems - Application of programmable logic controllers to nuclear plant

  10. Trade associations and labor organizations as intermediaries for disseminating workplace safety and health information.

    Science.gov (United States)

    Okun, Andrea H; Watkins, Janice P; Schulte, Paul A

    2017-09-01

    There has not been a systematic study of the nature and extent to which business and professional trade associations and labor organizations obtain and communicate workplace safety and health information to their members. These organizations can serve as important intermediaries and play a central role in transferring this information to their members. A sample of 2294 business and professional trade associations and labor organizations in eight industrial sectors identified by the National Occupational Research Agenda was surveyed via telephone. A small percent of these organizations (40.9% of labor organizations, 15.6% of business associations, and 9.6% of professional associations) were shown to distribute workplace safety and health information to their members. Large differences were also observed between industrial sectors with construction having the highest total percent of organizations disseminating workplace safety and health information. There appears to be significant potential to utilize trade and labor organizations as intermediaries for transferring workplace safety and health information to their members. Government agencies have a unique opportunity to partner with these organizations and to utilize their existing communication channels to address high risk workplace safety and health concerns. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

  11. A quantitative approach for risk-informed safety significance categorization in option-2

    International Nuclear Information System (INIS)

    Ha, Jun Su; Seong, Poong Hyun

    2004-01-01

    OPTION-2 recommends that Structures, Systems, or Components (SSCs) of Nuclear Power Plants (NPPs) should be categorized into four groups according to their safety significance as well as whether they are safety-related or not. With changes to the scope of SSCs covered by 10 CFR 50, safety-related components which categorized into low safety significant SSC (RISC-3 SSC) can be exempted from the existing conservative burden (or requirements). As OPTION-2 paradigm is applied, a lot of SSCs may be categorized into RISC-3 SSCs. Changes in treatment of the RISC-3 SSCs will be recommended and then finally the recommended changes shall be evaluated. Consequently, before recommending the changes in treatment, probable candidate SSCs for the changes in treatment need to be identified for efficient risk-informed regulation and application (RIRA). Hence, in this work, a validation focused on the RISC-3 SSCs is proposed to identify probable candidate SSCs. Burden to Importance Ratio (BIR) is utilized as a quantitative measure for the validation. BIR is a measure representing the extent of resources or requirements imposed on a SSC with respect to the value of the importance measure of the SSC. Therefore SSCs having high BIR can be considered as probable candidate SSCs for the changes in treatment. In addition, the final decision whether RISC-3 SSCs can be considered as probable candidate SSCs or not should be made by an expert panel. For the effective decision making, a structured mathematical decision-making process is constructed based on Belief Networks (BBN) to overcome demerits of conventional group meeting based on unstructured discussion for decision-making. To demonstrate the usefulness of the proposed approach, the approach is applied to 22 components selected from 512 In-Service Test (IST) components of Ulchin unit 3. The results of the application show that the proposed approach can identify probable candidate SSCs for changes in treatment. The identification of the

  12. Safety recommendation component of mobile information assistant of the tourist

    Science.gov (United States)

    Savchuk, Valeriya V.; Kunanec, Natalia E.; Pasichnyk, Volodymyr V.; Popiel, Piotr; Weryńska-Bieniasz, RóŻa; Kashaganova, Gulzhamal; Kalizhanova, Aliya

    2017-08-01

    The goal of article is to introduce and justify the need for the safety system components of Mobile Information of the tourist (MIAT). One of the objectives of the system is to determine the level of risk in a particular tourist destination on the basis of available information in the knowledge base.

  13. Proceedings of the Second NASA Aviation Safety Program Weather Accident Prevention Review

    Science.gov (United States)

    Martzaklis, K. Gus (Compiler)

    2003-01-01

    The Second NASA Aviation Safety Program (AvSP) Weather Accident Prevention (WxAP) Annual Project Review held June 5-7, 2001, in Cleveland, Ohio, presented the NASA technical plans and accomplishments to the aviation community. NASA-developed technologies presented included an Aviation Weather Information System with associated digital communications links, electronic atmospheric reporting technologies, forward-looking turbulence warning systems, and turbulence mitigation procedures. The meeting provided feedback and insight from the aviation community of diverse backgrounds and assisted NASA in steering its plans in the direction needed to meet the national safety goal of 80-percent reduction of aircraft accidents by 2007. The proceedings of the review are enclosed.

  14. State Traffic Safety Information - 2010-2015 FARS Accident File data

    Data.gov (United States)

    Department of Transportation — The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic...

  15. The safety relief valve handbook design and use of process safety valves to ASME and International codes and standards

    CERN Document Server

    Hellemans, Marc

    2009-01-01

    The Safety Valve Handbook is a professional reference for design, process, instrumentation, plant and maintenance engineers who work with fluid flow and transportation systems in the process industries, which covers the chemical, oil and gas, water, paper and pulp, food and bio products and energy sectors. It meets the need of engineers who have responsibilities for specifying, installing, inspecting or maintaining safety valves and flow control systems. It will also be an important reference for process safety and loss prevention engineers, environmental engineers, and plant and process designers who need to understand the operation of safety valves in a wider equipment or plant design context. . No other publication is dedicated to safety valves or to the extensive codes and standards that govern their installation and use. A single source means users save time in searching for specific information about safety valves. . The Safety Valve Handbook contains all of the vital technical and standards informat...

  16. Summary of informal meeting on ''facilities for atomic physics research with highly ionized atoms''

    International Nuclear Information System (INIS)

    Cocke, C.L.; Jones, K.W.

    1984-01-01

    An informal meeting to discuss ''Facilities for Atomic Physics Research with Highly Ionized Atoms'' was held during the APS DEAP meeting at the University of Connecticut on May 30, 1984. The meeting was motivated by the realization that the status of facilities for studies of highly ionized atoms is unsettled and that it might be desirable to take action to ensure adequate resources for research over the whole range of charge states and energies of interest. It was assumed that the science to be done with these beams has been amply documented in the literature

  17. The Research on Safety Management Information System of Railway Passenger Based on Risk Management Theory

    Science.gov (United States)

    Zhu, Wenmin; Jia, Yuanhua

    2018-01-01

    Based on the risk management theory and the PDCA cycle model, requirements of the railway passenger transport safety production is analyzed, and the establishment of the security risk assessment team is proposed to manage risk by FTA with Delphi from both qualitative and quantitative aspects. The safety production committee is also established to accomplish performance appraisal, which is for further ensuring the correctness of risk management results, optimizing the safety management business processes and improving risk management capabilities. The basic framework and risk information database of risk management information system of railway passenger transport safety are designed by Ajax, Web Services and SQL technologies. The system realizes functions about risk management, performance appraisal and data management, and provides an efficient and convenient information management platform for railway passenger safety manager.

  18. Role of courtyard counselling meeting in improving household food safety knowledge and practices in Munshiganj district of Bangladesh.

    Science.gov (United States)

    Riaz, Baizid Khoorshid; Alim, Md Abdul; Islam, Anm Shamsul; Amin, Km Bayzid; Sarker, Mohammad Abul Bashar; Hasan, Khaled; Ashad-Uz-Zaman, Md Noor; Selim, Shahjada; Quaiyum, Salman; Haque, Emdadul; Monir Hossain, Shah; Ryder, John; Khanam, Rokeya

    2016-12-01

    Unsafe food is linked to the deaths of an estimated two million people annually. Food containing harmful agents is responsible for more than 200 diseases ranging from diarrhoea to cancers. A one-sample pilot intervention study was conducted to evaluate the role of courtyard counselling meetings as the means of intervention for improving food safety knowledge and practices among household food handlers in a district of Bangladesh. The study was conducted in three phases: a baseline survey, the intervention and an end-line survey between April and November 2015 where 194 food handlers took part. Data were collected through observations and face-to-face interviews. The mean age of the respondents was 38.8 (±12.4) years, all of whom were females. Hand washing before eating, and washing utensils with soap were significantly improved at the end-line in comparison to the baseline (57% vs. 40% and 83% vs. 69%, respectively). Hand washing with soap was increased by 4%. The mean score of food handling practices was significantly increased after the intervention (20.5 vs. 22.1; Pfood and the necessity of thorough cooking were significantly increased after the intervention (88% from 64% and 34% from 21%, respectively). Mean scores of knowledge and practice on food safety were significantly increased by 1.9 and 1.6, respectively after the one month intervention. Thus this food safety education in rural communities should be scaled up and, indeed, strengthened using the courtyard counselling meetings in Bangladesh.

  19. Proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management 2005 Kyoto

    International Nuclear Information System (INIS)

    2005-01-01

    This is the program and the proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management held from November 23rd through the 25th of 2005. The sessions held were: (1) Medical Exposure, (2) Environmental Measurement and Radiation Source Handling, (3) Radiation Measurement and Influence of Electromagnetic Waves, (4) Utilization of Irradiation, (5) Countermeasures against Contamination and Inspection of Contamination, (6) Imaging Plate, (7) Controlled Measurement and Dose Evaluation, (8) Working Environment Measurement 1, (9) Working Environment Measurement 2, (10) Establishment of Software and System, (11) Radiation Education 1, (12) Radiation Education 2, and (13) Exposure Reduction and Safety Control. The poster sessions held were: (1) Exposure Reduction and Radiation Evaluation, (2) Radiation Measurement and Influence of Electromagnetic Waves, (3) Education Training, (4) Safety Control, (5) Software, Data Handling, and Shielding Calculation, and (6) Environmental Radioactivity. The keynote lectures held were: (1) 'Situation of Medical Exposure' and (2) 'Cosmic Radiation While Boarding on Airplanes'. The symposia held were: (1) 'Food Irradiation' and (2) 'Life Science'. (S.K.)

  20. 78 FR 23545 - Proposed Extension of Approval of Information Collection; Comment Request: Third Party Conformity...

    Science.gov (United States)

    2013-04-19

    ... Information Collection; Comment Request: Third Party Conformity Assessment Body Registration Form AGENCY... evaluate whether third party conformity assessment bodies meet the requirements to test for compliance to specified children's product safety rules. Third party conformity assessment bodies found to meet the...

  1. Risk-informed regulation: handling uncertainty for a rational management of safety

    International Nuclear Information System (INIS)

    Zio, Enrico

    2008-01-01

    A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated

  2. Proceedings of the 1982 National Waste Terminal Storage Program information meeting

    International Nuclear Information System (INIS)

    1982-12-01

    The substantial progress made during fiscal year 1982 in the programmatic work directed toward providing the nation with at least one licensed, fully operational mined geologic repository as early as 1998 is given in these papers at the 1982 National Waste Terminal Storage (NWTS) information meeting. Individual papers are indexed. (DP)

  3. Quality and safety implications of emergency department information systems.

    Science.gov (United States)

    Farley, Heather L; Baumlin, Kevin M; Hamedani, Azita G; Cheung, Dickson S; Edwards, Michael R; Fuller, Drew C; Genes, Nicholas; Griffey, Richard T; Kelly, John J; McClay, James C; Nielson, Jeff; Phelan, Michael P; Shapiro, Jason S; Stone-Griffith, Suzanne; Pines, Jesse M

    2013-10-01

    The Health Information Technology for Economic and Clinical Health Act of 2009 and the Centers for Medicare & Medicaid Services "meaningful use" incentive programs, in tandem with the boundless additional requirements for detailed reporting of quality metrics, have galvanized hospital efforts to implement hospital-based electronic health records. As such, emergency department information systems (EDISs) are an important and unique component of most hospitals' electronic health records. System functionality varies greatly and affects physician decisionmaking, clinician workflow, communication, and, ultimately, the overall quality of care and patient safety. This article is a joint effort by members of the Quality Improvement and Patient Safety Section and the Informatics Section of the American College of Emergency Physicians. The aim of this effort is to examine the benefits and potential threats to quality and patient safety that could result from the choice of a particular EDIS, its implementation and optimization, and the hospital's or physician group's approach to continuous improvement of the EDIS. Specifically, we explored the following areas of potential EDIS safety concerns: communication failure, wrong order-wrong patient errors, poor data display, and alert fatigue. Case studies are presented that illustrate the potential harm that could befall patients from an inferior EDIS product or suboptimal execution of such a product in the clinical environment. The authors have developed 7 recommendations to improve patient safety with respect to the deployment of EDISs. These include ensuring that emergency providers actively participate in selection of the EDIS product, in the design of processes related to EDIS implementation and optimization, and in the monitoring of the system's ongoing success or failure. Our recommendations apply to emergency departments using any type of EDIS: custom-developed systems, best-of-breed vendor systems, or enterprise systems

  4. 78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

    Science.gov (United States)

    2013-06-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

  5. 76 FR 20051 - Advisory Committee for Computer and Information; Science and Engineering; Notice of Meeting

    Science.gov (United States)

    2011-04-11

    ... NATIONAL SCIENCE FOUNDATION Advisory Committee for Computer and Information; Science and... Committee for Computer and Information Science and Engineering--(1115). Date and Time: May 6, 2011 8:30 a.m... Meeting: Open. Contact Person: Carmen Whitson, Directorate for Computer and Information, Science and...

  6. A Survey of Pilots on the Dissemination of Safety Information

    National Research Council Canada - National Science Library

    Rakovan, Lori

    1999-01-01

    A survey was conducted to obtain information from the pilot population on erections of safety-related training currently being offered, its usefulness, and the process through which it might be better...

  7. Participatory approach to improving safety, health and working conditions in informal economy workplaces in Cambodia.

    Science.gov (United States)

    Kawakami, Tsuyoshi; Tong, Leng; Kannitha, Yi; Sophorn, Tun

    2011-01-01

    The present study aimed to improve safety and health in informal economy workplaces such as home workplaces, small construction sites, and rural farms in Cambodia by using "participatory" approach. The government, workers' and employers' organizations and NGOs jointly assisted informal economy workers in improving safety and health by using participatory training methodologies. The steps taken were: (1) to collect existing good practices in safety and health in Cambodia; (2) to develop new participatory training programmes for home workers and small construction sites referring to ILO's WISE training programme, and (3) to train government officers, workers, employers and NGOs as safety and health trainers. The participatory training programmes developed consisted of action-checklists associated with illustrations, good example photo sheets, and texts explaining practical, low-cost improvement measures. The established safety and health trainers reached many informal economy workers through their human networks, and trained them by using the developed participatory training programmes. More than 3,000 informal economy workers were trained and they implemented improvements by using low-cost methods. Participatory training methodologies and active cooperation between the government, workers, employers and NGOs made it possible to provide practical training for those involved in the informal economy workplaces.

  8. Metrics design for safety assessment

    NARCIS (Netherlands)

    Luo, Yaping; van den Brand, M.G.J.

    2016-01-01

    Context:In the safety domain, safety assessment is used to show that safety-critical systems meet the required safety objectives. This process is also referred to as safety assurance and certification. During this procedure, safety standards are used as development guidelines to keep the risk at an

  9. Nuclear Safety Review for 2015

    International Nuclear Information System (INIS)

    2015-06-01

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

  10. 76 FR 7818 - Announcing a Meeting of the Information Security and Privacy Advisory Board

    Science.gov (United States)

    2011-02-11

    ... advise the Secretary of Commerce and the Director of NIST on security and privacy issues pertaining to... Information Security and Privacy Advisory Board AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice. SUMMARY: The Information Security and Privacy Advisory Board (ISPAB) will meet...

  11. 75 FR 39920 - Announcing a Meeting of the Information Security and Privacy Advisory Board

    Science.gov (United States)

    2010-07-13

    ... advise the Secretary of Commerce and the Director of NIST on security and privacy issues pertaining to... Information Security and Privacy Advisory Board AGENCY: National Institute of Standards and Technology. ACTION: Notice. SUMMARY: The Information Security and Privacy Advisory Board (ISPAB) will meet Wednesday, August...

  12. Health record systems that meet clinical needs

    Directory of Open Access Journals (Sweden)

    Gabriella Negrini

    2012-10-01

    Full Text Available Introduction Increased attention has recently been focused on health record systems as a result of accreditation programs, a growing emphasis on patient safety, and the increase in lawsuits involving allegations of malpractice. Health-care professionals frequently express dissatisfaction with the health record systems and complain that the data included are neither informative nor useful for clinical decision making. This article reviews the main objectives of a hospital health record system, with emphasis on its roles in communication and exchange among clinicians, patient safety, and continuity of care, and asks whether current systems have responded to the recent changes in the Italian health-care system.Discussion If health records are to meet the expectations of all health professionals, the overall information need must be carefully analyzed, a common data set must be created, and essential specialist contributions must be defined. Working with health-care professionals, the hospital management should define how clinical information is to be displayed and organized, identify a functionally optimal layout, define the characteristics of ongoing patient assessment in terms of who will be responsible for these activities and how often they will be performed. Internet technology can facilitate data retrieval and meet the general requirements of a paper-based health record system, but it must also ensure focus on clinical information, business continuity, integrity, security, and privacy.Conclusions The current health records system needs to be thoroughly revised to increase its accessibility, streamline the work of health-care professionals who consult it, and render it more useful for clinical decision making—a challenging task that will require the active involvement of the many professional classes involved.

  13. 76 FR 24504 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2011-05-02

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

  14. Lessons learned in building a global information network on chemicals (GINC)

    International Nuclear Information System (INIS)

    Kaminuma, Tsuguchika

    2005-01-01

    The Global Information Network on Chemicals (GINC) was a project to construct a worldwide information network linking international, national, and other organizations working for the safe management of chemicals. Proposed in 1993, the project started the next year and lasted almost 10 years. It was begun as a joint project of World Health Organization (WHO), International Labor Organization (ILO), and United Nations Environment Program (UNEP), and later endorsed by the Intergovernmental Forum on Chemical Safety (IFCS). Asia, particularly East Asia and the Pacific islands, was chosen as the feasibility study region. The author's group then at the National Institute of Health Sciences (NIHS) of Japan led this initiative and hosted numerous meetings. At these meetings, tutorial sessions for communicating chemical safety expertise and emerging new information technologies relevant to the safe management of chemicals were offered. Our experience with this project, particularly the Web-based system and the tutorial sessions, may be of use to others involved with Web-based instruction and the training of chemical safety specialists from both developed and developing countries

  15. Information System Passive Safety at DaimlerChrysler: from vision to reality

    Energy Technology Data Exchange (ETDEWEB)

    Ruoff, H. [DaimlerChrysler AG, Sindelfingen (Germany)

    2001-07-01

    Today, short development times and an extensive model range are key factors when it comes to remaining a leading force in the highly competitive automobile market. Information technology plays a crucial role as an 'enabler' in keeping this competitive edge. It is only possible to make full use of existing potential by using 'state-of-the-art' information technology. In particular, this involves making knowledge that is distributed in various systems and 'heads' available quickly and transparently anytime and anywhere. The improved re-use of acquired expertise, efficient information searches, and standardized and seamless applications lead to a high level of performance. This often involves the transformation of a company culture from 'information hider' to 'information provider'. The vision of converting a gradually created, complex range of systems into a seamless sequence of distributed working processes with numerous participants is becoming reality in the Passive Safety area in Automobile/Vehicle Development at DaimlerChrysler. The INFOS Passive Safety information system provides all the data and information, which is required for, or results from, the entire crash test process. (orig.)

  16. Information dissemination and use: critical components in occupational safety and health.

    Science.gov (United States)

    Schulte, P A; Okun, A; Stephenson, C M; Colligan, M; Ahlers, H; Gjessing, C; Loos, G; Niemeier, R W; Sweeney, M H

    2003-11-01

    Information dissemination is a mandated, but understudied, requirement of occupational and environmental health laws and voluntary initiatives. Research is needed on the factors that enhance and limit the development, transfer, and use of occupational safety and health information (OSH). Contemporary changes in the workforce, workplaces, and the nature of work will require new emphasis on the dissemination of information to foster prevention. Legislative and regulatory requirements and voluntary initiatives for dissemination of OSH information were identified and assessed. Literature on information dissemination was reviewed to identify important issues and useful approaches. More than 20 sections of laws and regulations were identified that mandated dissemination of occupational and environmental safety and health information. A four-stage approach for tracking dissemination and considering the flow of information was delineated. Special areas of dissemination were identified: the information needs of the changing workforce, new and young workers; small businesses; and workers with difficulty in understanding or reading English. We offer a framework for dissemination of OSH information and underscore the need to focus on the extent to which decision-makers and others receive and use such information. More solid data are also needed on current investments in disseminating, diffusing and applying OSH information and on the utility of that information. Am. J. Ind. Med. 44:515-531, 2003. Published 2003 Wiley-Liss, Inc.

  17. An Anesthesia Preinduction Checklist to Improve Information Exchange, Knowledge of Critical Information, Perception of Safety, and Possibly Perception of Teamwork in Anesthesia Teams.

    Science.gov (United States)

    Tscholl, David W; Weiss, Mona; Kolbe, Michaela; Staender, Sven; Seifert, Burkhardt; Landert, Daniel; Grande, Bastian; Spahn, Donat R; Noethiger, Christoph B

    2015-10-01

    An anesthesia preinduction checklist (APIC) to be performed before anesthesia induction was introduced and evaluated with respect to 5 team-level outcomes, each being a surrogate end point for patient safety: information exchange (the percentage of checklist items exchanged by a team, out of 12 total items); knowledge of critical information (the percentage of critical information items out of 5 total items such as allergies, reported as known by the members of a team); team members' perceptions of safety (the median scores given by the members of a team on a continuous rating scale); their perception of teamwork (the median scores given by the members of a team on a continuous rating scale); and clinical performance (the percentage of completed items out of 14 required tasks, e.g., suction device checked). A prospective interventional study comparing anesthesia teams using the APIC with a control group not using the APIC was performed using a multimethod design. Trained observers rated information exchange and clinical performance during on-site observations of anesthesia inductions. After the observations, each team member indicated the critical information items they knew and their perceptions of safety and teamwork. One hundred five teams using the APIC were compared with 100 teams not doing so. The medians of the team-level outcome scores in the APIC group versus the control group were as follows: information exchange: 100% vs 33% (P safety: 91% vs 84% (P improves information exchange, knowledge of critical information, and perception of safety in anesthesia teams-all parameters contributing to patient safety. There was a trend indicating improved perception of teamwork.

  18. 77 FR 61736 - Codex Alimentarius Commission: Meeting of the Codex Committee on Food Hygiene

    Science.gov (United States)

    2012-10-11

    ... notices. Customers can add or delete subscriptions themselves, and have the option to password protect... meeting is to provide information, receive public comments on agenda items, and draft United States (U.S..., 2012. The Under Secretary for Food Safety and FDA recognize the importance of providing interested...

  19. Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-07-01

    At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989

  20. Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1990-01-01

    At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989