Improving the safety of Ukrainian NPP to reach an internationally accepted level

International Nuclear Information System (INIS)

Bozhko, S.; Helske, J.; Janke, R.; Mayoral, C.

2013-01-01

This paper summarizes the safety status and the modernization progress of Ukrainian NPPs towards an internationally accepted level of safety. After a brief discussion of the concept of what is called an 'international accepted level' for new and operating NPPs, the status of Russian type WWER and in particular the Ukrainian NPPs is presented. Then, the performed investigations of the gaps between international accepted level and the original status of Ukrainian NPPs are presented. The safety objectives of the modernization programs, some examples of defence in depth improvements, and an overall view of the modernization programs of Ukrainian NPPs are produced. Then, few important safety improvements implemented at the oldest Ukrainian WWER-1000 South Ukraine-1 are given in more detail. Finally, a conclusion presents the current status on the way to fulfill the national safety targets and to reach an internationally accepted level for all the Ukrainian NPPs. The paper is followed by the slides of the presentation. (authors)

Research program on regulatory safety research

International Nuclear Information System (INIS)

Mailaender, R.

2010-02-01

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

Seismic safety programme at NPP Paks. Propositions for coordinated international activity in seismic safety of the WWER-440 V-213

International Nuclear Information System (INIS)

Katona, T.

1995-01-01

This paper presents the Paks NPP seismic safety program, highlighting the specifics of the WWER-440/213 type in operation, and the results of work obtained so far. It covers the following scope: establishment of the seismic safety program (original seismic design, current requirements, principles and structure of the seismic safety program); implementation of the seismic safety program (assessing the seismic hazard of the site, development of the new concept of seismic safety for the NPP, assessing the seismic resistance of the building and the technology); realization of the seismic safety of higher level (technical solutions, drawings, realization); ideas and propositions for coordinated international activity

Ukraine International cooperation in nuclear and radiation safety: public-administrative aspect

Directory of Open Access Journals (Sweden)

I. P. Krynychnay

2017-03-01

Full Text Available The article examines international cooperation of Ukraine with other States in the sphere of ensuring nuclear and radiation safety and highlights the main directions of development and improvement of nuclear and radiation safety in Ukraine based on international experience, with the aim of preventing the risks of accidents and contamination areas radiological substances. Illuminated that for more than half a century of experience in the use of nuclear energy by the international community under the auspices of the UN, IAEA and other international organizations initiated and monitored the implementation of key national and international programs on nuclear and radiation safety. Of the Convention in the field of nuclear safety and the related independent peer review, effective national regulatory infrastructures, current nuclear safety standards and policy documents, as well as mechanisms of evaluation in the framework of the IAEA constitute important prerequisites for the creation of a world community, the global regime of nuclear and radiation safety. For analysis of the state of international cooperation of Ukraine with other States in the sphere of nuclear and radiation safety, highlighted the legal substance of nuclear and radiation safety of Ukraine, which is enshrined in the domestic Law of Ukraine «On nuclear energy use and radiation safety». Considered the most relevant legal relations. It is established that, despite the current complex international instruments, existing domestic legislation on nuclear and radiation safety, partly there is a threat of emergency nuclear radiation nature, in connection with the failure of fixed rules and programs, lack of funding from the state is not always on time and in full allows you to perform fixed strategy for overcoming the consequences of radiation accidents, the prevention of the threat of environmental pollution. Found that to improve and further ensuring nuclear and radiation safety of

Fusion Safety Program annual report, fiscal year 1994

International Nuclear Information System (INIS)

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

1995-03-01

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

Fusion safety program annual report fiscal year 1997

International Nuclear Information System (INIS)

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

1998-01-01

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

Fusion safety program annual report fiscal year 1997

Energy Technology Data Exchange (ETDEWEB)

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

1998-01-01

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

Research and development program in reactor safety for NUCLEBRAS

International Nuclear Information System (INIS)

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

1984-01-01

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

Fusion Safety Program Annual Report, Fiscal Year 1996

International Nuclear Information System (INIS)

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

1996-12-01

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

International Symposium on Nuclear Safety

International Nuclear Information System (INIS)

2013-03-01

Nuclear Regulatory Authority of the Slovak Republic and the Embassy of Japan in the Slovak Republic, under the auspices of the Deputy Prime Minister and Minister of Foreign and European Affairs Mr Lajcak organized International Symposium on Nuclear Safety on 14 and 15 March 2013. The symposium took place almost exactly two years after the occurrence of accidents at the Japanese nuclear power plant Fukushima Daichi. The main mission of the symposium was an attempt to contribute to the improvement of nuclear safety by sharing information and lessons presented by Japanese experts with experts from the region, the International Atomic Energy Agency (IAEA) and the European Commission. The aim of the symposium, unlike many other events organized in connection with the events in Fukushima Daichi NPP, was a summary of the results of stress tests and measures update adopted by the international community, especially within Europe. Panel discussion was included to the program of the symposium for this aim was, mainly focused on the current state of implementation of the National Action Plan of the Slovak Republic, the Czech Republic, Poland, Ukraine and Switzerland and the IAEA Action Plan.

Canadian hydrogen safety program

International Nuclear Information System (INIS)

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

2007-01-01

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

The International Criticality Safety Benchmark Evaluation Project on the Internet

International Nuclear Information System (INIS)

Briggs, J.B.; Brennan, S.A.; Scott, L.

2000-01-01

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in October 1992 by the US Department of Energy's (DOE's) defense programs and is documented in the Transactions of numerous American Nuclear Society and International Criticality Safety Conferences. The work of the ICSBEP is documented as an Organization for Economic Cooperation and Development (OECD) handbook, International Handbook of Evaluated Criticality Safety Benchmark Experiments. The ICSBEP Internet site was established in 1996 and its address is http://icsbep.inel.gov/icsbep. A copy of the ICSBEP home page is shown in Fig. 1. The ICSBEP Internet site contains the five primary links. Internal sublinks to other relevant sites are also provided within the ICSBEP Internet site. A brief description of each of the five primary ICSBEP Internet site links is given

OPG waterways public safety program

Energy Technology Data Exchange (ETDEWEB)

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

2009-07-01

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

Safety assessment guidance in the International Atomic Energy Agency RADWASS Program

Energy Technology Data Exchange (ETDEWEB)

Vovk, I.F.; Seitz, R.R.

1995-12-31

The IAEA RADWASS programme is aimed at establishing a coherent and comprehensive set of principles and standards for the safe management of waste and formulating the guidelines necessary for their application. A large portion of this programme has been devoted to safety assessments for various waste management activities. Five Safety Guides are planned to be developed to provide general guidance to enable operators and regulators to develop necessary framework for safety assessment process in accordance with international recommendations. They cover predisposal, near surface disposal, geological disposal, uranium/thorium mining and milling waste, and decommissioning and environmental restoration. The Guide on safety assessment for near surface disposal is at the most advanced stage of preparation. This draft Safety Guide contains guidance on description of the disposal system, development of a conceptual model, identification and description of relevant scenarios and pathways, consequence analysis, presentation of results and confidence building. The set of RADWASS publications is currently undergoing in-depth review to ensure a harmonized approach throughout the Safety Series.

Fusion Safety Program annual report, fiscal year 1992

International Nuclear Information System (INIS)

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

1993-01-01

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

An international nuclear safety regime

International Nuclear Information System (INIS)

Rosen, M.

1995-01-01

For all the parties involved with safe use of nuclear energy, the opening for signature of the 'Convention on Nuclear Safety' (signed by 60 countries) and the ongoing work to prepare a 'Convention on Radioactive Waste Safety' are particularly important milestones. 'Convention on Nuclear Safety' is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The two conventions are only one facet of international cooperation to enhance safety. A review of some cooperative efforts of the past decades, and some key provisions of the new safety conventions, presented in this paper, show how international cooperation is increasing nuclear safety worldwide. The safety philosophy and practices involved with legal framework for the safe use of nuclear power will foster a collective international involvement and commitment. It will be a positive step towards increasing public confidence in nuclear power

Radiation safety: New international standards

International Nuclear Information System (INIS)

Gonzalez, A.J.

1994-01-01

This article highlights an important result of this work for the international harmonization of radiation safety: specifically, it present an overview of the forthcoming International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources - the so-called BSS. They have been jointly developed by six organizations - the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (NEA/OECD), the Pan American Health Organization (PAHO), and the World Health Organization (WHO)

International cooperation in nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1991-01-01

The mechanisms of international co-operations, co-ordinated by International Atomic Energy Agency, are presented. These co-operations are related to international safety standards, to the safety of the four hundred existing reactors in operation, to quick help and information in case of emergency, and to the already valid international conventions. The relation between atomic energy and environmental protection is also discussed briefly. (K.A.)

Research program on regulatory safety research - Synthesis report 2008

International Nuclear Information System (INIS)

Mailaender, R

2009-06-01

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

International nuclear safety

International Nuclear Information System (INIS)

Wolff, P.H.W.

1978-01-01

The background to the development of internationally agreed safety principles and practices is discussed. The activities of the IAEA and the scope, structure, and organisation of its programme of Reactor Safety Codes and Guides are described. Attention is drawn to certain areas needing further considerations. (UK)

Thermonuclear generation program: risks and safety

International Nuclear Information System (INIS)

Goes, Alexandre Gromann de Araujo

1999-01-01

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

Fusion Safety Program annual report, Fiscal Year 1993

International Nuclear Information System (INIS)

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

1993-12-01

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

Economic approaches to measuring the significance of food safety in international trade.

Science.gov (United States)

Caswell, J A

2000-12-20

International trade in food products has expanded rapidly in recent years. This paper presents economic approaches for analyzing the effects on trade in food products of the food safety requirements of governments and private buyers. Important economic incentives for companies to provide improved food safety arise from (1) public incentives such as ex ante requirements for sale of a product with sufficient quality and ex post penalties (liability) for sale of products with deficient quality, and (2) private incentives for producing quality such as internal performance goals (self-regulation) and the external (certification) requirements of buyers. The World Trade Organization's Sanitary Phytosanitary Agreement facilitates scrutiny of the benefits and costs of country-level regulatory programs and encourages regulatory rapprochement on food safety issues. Economists can help guide risk management decisions by providing estimates of the benefits and costs of programs to improve food safety and by analyzing their effect on trade in food products.

Evaluating the Effectiveness of an Educational Intervention to Improve the Patient Safety Attitudes of Intern Pharmacists.

Science.gov (United States)

Walpola, Ramesh L; Fois, Romano A; McLachlan, Andrew J; Chen, Timothy F

2017-02-25

Objective. To evaluate the effectiveness of a face-to-face educational intervention in improving the patient safety attitudes of intern pharmacists. Methods. A patient safety education program was delivered to intern pharmacists undertaking The University of Sydney Intern Training Program in 2014. Their patient safety attitudes were evaluated immediately prior to, immediately after, and three-months post-intervention. Underlying attitudinal factors were identified using exploratory factor analysis. Changes in factor scores were examined using analysis of variance. Results. Of the 120 interns enrolled, 95 (78.7%) completed all three surveys. Four underlying attitudinal factors were identified: attitudes towards addressing errors, questioning behaviors, blaming individuals, and reporting errors. Improvements in all attitudinal factors were evident immediately after the intervention. However, only improvements in attitudes towards blaming individuals involved in errors were sustained at three months post-intervention. Conclusion. The educational intervention was associated with short-term improvements in pharmacist interns' patient safety attitudes. However, other factors likely influenced their attitudes in the longer term.

Commercial Crew Program Crew Safety Strategy

Science.gov (United States)

Vassberg, Nathan; Stover, Billy

2015-01-01

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

Highway Safety Program Manual: Volume 3: Motorcycle Safety.

Science.gov (United States)

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

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

Tank waste remediation system nuclear criticality safety program management review

International Nuclear Information System (INIS)

BRADY RAAP, M.C.

1999-01-01

This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

Internal Dosimetry for Nuclear Power Program

International Nuclear Information System (INIS)

Wo, Y.M.

2011-01-01

Internal dosimetry which refers to dosage estimation from internal part of an individual body is an important and compulsory component in order to ensure the safety of the personnel involved in operational of a Nuclear Power Program. Radionuclides particle may deposit in the human being through several pathways and release wave and/or particle radiation to irradiate that person and give dose to body until it been excreted or completely decayed from the body. Type of radionuclides of concerning, monitoring program, equipment's and technique used to measure the concentration level of such radionuclides and dose calculation will be discussed in this article along with the role and capability of Malaysian Nuclear Agency. (author)

The international dimensions of nuclear safety standards

International Nuclear Information System (INIS)

Reed, J.M.

1992-01-01

The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

The nuclear power safety programme of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Rosen, M.

1981-01-01

The expanded role of the IAEA in the field of nuclear power safety will be discussed. Emphasis will be given to the NUSS program (the letters being an acronym for Nuclear Safety Standards) to establish internationally accepted safety codes and guides for nuclear power plants dealing with governmental regulatory organizations, siting, design, operation and quality assurance. Other activities discussed will be advisory services, exchange of information and training, emergency accident assistance, and technical assistance. (orig./RW)

Research program on nuclear technology and nuclear safety

International Nuclear Information System (INIS)

Dreier, J.

2010-04-01

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

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

International Nuclear Information System (INIS)

Steinberg, N.

1999-01-01

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

ORNL results for Test Case 1 of the International Atomic Energy Agency's research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities

International Nuclear Information System (INIS)

Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A.; Roemer, E.K.

1993-01-01

The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled '''The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.'' The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault

FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

Energy Technology Data Exchange (ETDEWEB)

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

2004-04-13

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

Utilizing the Fast Flux Test Facility for international passive safety testing

International Nuclear Information System (INIS)

Shen, P.K.; Padilla, A.; Lucoff, D.M.; Waltar, A.E.

1991-01-01

A two-phased approach has been undertaken in the Fast Flux Test Facility (FFTF) to conduct passive safety testing. Phase I (1986 to 1987) was structured to obtain an initial understanding of the reactivity feedback components. The planned Phase II (1992 to 1993) international program will extend the testing to include static and dynamic feedback measurements, transient and demonstration tests, and gas expansion module (GEM) reactivity tests. The primary objective is to meet the needs for safety analysis code validation, with particular emphasis on reducing the uncertainties associated with structure reactivity feedback. Program scope and predicted FFTF responses are discussed and illustrated. (author)

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

International Nuclear Information System (INIS)

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

2013-01-01

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

International consensus on safety principles

International Nuclear Information System (INIS)

Warnecke, E.

1993-01-01

The International Atomic Energy Agency (IAEA) has been regularly requested by its Member States to provide evidence that radioactive waste can be managed safely and to help demonstrate a harmonization of approach at the international level by providing safety documents. In response, IAEA established a special series of safety documents devoted to radioactive waste management. These documents will be elaborated within the Radioactive Waste Safety Standards (RADWASS) programme [1,2] which covers all aspects of radioactive waste management. The RADWASS programme develops a series of international consensus documents on all parts of the safe management of radioactive waste, including disposal. The purpose of the RADWASS programme is to (i) document existing international consensus in the approaches and methodologies for safe radioactive waste management, (ii) create a mechanism to establish consensus where it does not exist and (iii) provide Member States with a comprehensive series of internationally agreed upon documents to complement national standards and criteria. This paper describes the RADWASS programme, and covers the structure, implementation plans and status of documents under preparation

Guidance for implementing an environmental, safety, and health assurance program. Volume 10. Model guidlines for line organization environmental, safety and health audits and appraisals

International Nuclear Information System (INIS)

Ellingson, A.C.

1981-10-01

This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. The Standard specifies that the operational level of an institution must have an internal assurance function, and this document provides guidance for the audit/appraisal portion of the operational level's ES and H program. The appendixes include an ES and H audit checklist, a sample element rating guide, and a sample audit plan for working level line organization internal audits

Safety performance indicators program

International Nuclear Information System (INIS)

Vidal, Patricia G.

2004-01-01

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

International Code Assessment and Applications Program: Annual report

International Nuclear Information System (INIS)

Ting, P.; Hanson, R.; Jenks, R.

1987-03-01

This is the first annual report of the International Code Assessment and Applications Program (ICAP). The ICAP was organized by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission (USNRC) in 1985. The ICAP is an international cooperative reactor safety research program planned to continue over a period of approximately five years. To date, eleven European and Asian countries/organizations have joined the program through bilateral agreements with the USNRC. Seven proposed agreements are currently under negotiation. The primary mission of the ICAP is to provide independent assessment of the three major advanced computer codes (RELAP5, TRAC-PWR, and TRAC-BWR) developed by the USNRC. However, program activities can be expected to enhance the assessment process throughout member countries. The codes were developed to calculate the reactor plant response to transients and loss-of-coolant accidents. Accurate prediction of normal and abnormal plant response using the codes enhances procedures and regulations used for the safe operation of the plant and also provides technical basis for assessing the safety margin of future reactor plant designs. The ICAP is providing required assessment data that will contribute to quantification of the code uncertainty for each code. The first annual report is devoted to coverage of program activities and accomplishments during the period between April 1985 and March 1987

Radiation safety program in a high dose rate brachytherapy facility

International Nuclear Information System (INIS)

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

2001-01-01

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

International cooperation for operating safety

International Nuclear Information System (INIS)

Dupuis, M.C.

1989-03-01

The international-cooperation organization in nuclear safety domain is discussed. The nuclear energy Direction Committee is helped by the Security Committee for Nuclear Power Plants in the cooperation between security organizations of member countries and in the safety and nuclear activity regulations. The importance of the cooperation between experts in human being and engine problems is underlined. The applied methods, exchange activities and activity analysis, and the cooperation of the Nuclear Energy Agency and international organizations is analysed [fr

Standards: An international framework for nuclear safety

International Nuclear Information System (INIS)

Versteeg, J.

2000-01-01

The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

The Role of Nuclear Power in Slovak Republic; Safety Upgrading Program for WWER Reactors

International Nuclear Information System (INIS)

Toth, A.

1998-01-01

Implementation of Slovenske elektrarne Production Base Development Program, where all these safety upgrading projects of nuclear power sources at Slovak Republic are included will ensure first of all safety of nuclear power sources on internationally acceptable level, operational reliability of nuclear power units, balanced consumption and production of electric energy in Slovakia and decrease of long term ecological impact in according with international commitments of Slovakia

System program information of internal occupational radiation exposure in Syria (SORIES)

International Nuclear Information System (INIS)

Bitar, A.; Moghrabi, M.

2014-01-01

The present work describes personal-computer-based software, SORIES, which enables users to estimate intake activity and the resulting internal doses for all radionuclides existing in ICRP /78/ and IAEA Safety Reports Series No.37. The program forms a useful tool to get a database containing all the information related to occupational internal monitoring program. Furthermore, SORIES offers the possibility to obtain different reports of results. The SORIES program was built to be easy-to-use and user friendly. The program is based on Microsoft FoxPro database program and runs on Microsoft Windows 97-XP. SORIES software is distributed by Atomic Energy Commission in Syria.(author)

Year-End Clinic Handoffs: A National Survey of Academic Internal Medicine Programs.

Science.gov (United States)

Phillips, Erica; Harris, Christina; Lee, Wei Wei; Pincavage, Amber T; Ouchida, Karin; Miller, Rachel K; Chaudhry, Saima; Arora, Vineet M

2017-06-01

While there has been increasing emphasis and innovation nationwide in training residents in inpatient handoffs, very little is known about the practice and preparation for year-end clinic handoffs of residency outpatient continuity practices. Thus, the latter remains an identified, yet nationally unaddressed, patient safety concern. The 2014 annual Association of Program Directors in Internal Medicine (APDIM) survey included seven items for assessing the current year-end clinic handoff practices of internal medicine residency programs throughout the country. Nationwide survey. All internal medicine program directors registered with APDIM. Descriptive statistics of programs and tools used to formulate a year-end handoff in the ambulatory setting, methods for evaluating the process, patient safety and quality measures incorporated within the process, and barriers to conducting year-end handoffs. Of the 361 APDIM member programs, 214 (59%) completed the Transitions of Care Year-End Clinic Handoffs section of the survey. Only 34% of respondent programs reported having a year-end ambulatory handoff system, and 4% reported assessing residents for competency in this area. The top three barriers to developing a year-end handoff system were insufficient overlap between graduating and incoming residents, inability to schedule patients with new residents in advance, and time constraints for residents, attendings, and support staff. Most internal medicine programs do not have a year-end clinic handoff system in place. Greater attention to clinic handoffs and resident assessment of this care transition is needed.

Electronuclear's safety culture assessment and enhancement program

International Nuclear Information System (INIS)

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

2002-01-01

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

International Nuclear Safety Center (INSC) database

International Nuclear Information System (INIS)

Sofu, T.; Ley, H.; Turski, R.B.

1997-01-01

As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

Towards an international regime on radiation and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, A.J.

2000-01-01

The 1990s have seen the de facto emergence of what might be called an 'international regime on nuclear and radiation safety'. It may be construed to encompass three key elements: legally binding international undertakings among States; globally agreed international safety standards; and provisions for facilitating the application of those standards. While nuclear and radiation safety are national responsibilities, governments have long been interested in formulating harmonised approaches to radiation and nuclear safety. A principal mechanism for achieving harmonisation has been the establishment of internationally agreed safety standards and the promotion of their global application. The development of nuclear and radiation safety standards is a statutory function of the IAEA, which is unique in the United Nations system. The IAEA Statute expressly authorises the Agency 'to establish standards of safety' and 'to provide for the application of these standards'. As the following articles and supplement in this edition of the IAEA Bulletin point out, facilitating international conventions; developing safety standards; and providing mechanisms for their application are high priorities for the IAEA. (author)

Establishment of an international nuclear safety body

International Nuclear Information System (INIS)

Rosen, M.

1983-01-01

During the past year there has been increasing interest in the establishment of new international mechanisms for developing a more uniform approach to nuclear safety. The tasks, organizational nature and affiliation, composition and structure, and financial support of an international nuclear safety body are discussed in the article

Source-book of International Activities Related to the Development of Safety Cases for Deep Geological Repositories

International Nuclear Information System (INIS)

2017-01-01

All national radioactive waste management authorities recognise today that a robust safety case is essential in developing disposal facilities for radioactive waste. To improve the robustness of the safety case for the development of a deep geological repository, a wide variety of activities have been carried out by national programs and international organisations over the past years. The Nuclear Energy Agency, since first introducing the modern concept of the 'safety case', has continued to monitor major developments in safety case activities at the international level. This Source-book summarises the activities being undertaken by the Nuclear Energy Agency, the European Commission and the International Atomic Energy Agency concerning the safety case for the operational and post-closure phases of geological repositories for radioactive waste that ranges from low-level to high-level waste and for spent fuel. In doing so, it highlights important differences in focus among the three organisations

Elements of a nuclear criticality safety program

International Nuclear Information System (INIS)

Hopper, C.M.

1995-01-01

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

2011 Annual Criticality Safety Program Performance Summary

Energy Technology Data Exchange (ETDEWEB)

Andrea Hoffman

2011-12-01

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

EUMENES, a computer software for managing the radiation safety program information at an institutional level

International Nuclear Information System (INIS)

Hernandez Saiz, Alejandro; Cornejo Diaz, Nestor; Valdes Ramos, Maryzury; Martinez Gonzalez, Alina; Gonzalez Rodriguez, Niurka; Vergara Gil, Alex

2008-01-01

The correct application of national and international regulations in the field of Radiological Safety requires the implementation of Radiation Safety Programs appropriate to the developed practice. These Programs demand the preparation and keeping of an important number of records and data, the compliance with working schedules, systematic quality controls, audits, delivery of information to the Regulatory Authority, the execution of radiological assessments, etc. Therefore, it is unquestionable the necessity and importance of having a computer tool to support the management of the information related to the Radiation Safety Program in any institution. The present work describes a computer program that allows the efficient management of these data. Its design was based on the IAEA International Basic Safety Standards recommendations and on the requirements of the Cuban national standards, with the objective of being flexible enough to be applied in most of the institutions using ionizing radiations. The most important records of Radiation Safety Programs were incorporated and reports can be generated by the users. An additional tools-module allows the user to access to a radionuclide data library, and to carry out different calculations of interest in radiological protection. The program has been developed in Borland Delphi and manages Microsoft Access databases. It is a user friendly code that aims to support the optimization of Radiation Safety Programs. The program contributes to save resources and time, as the generated information is electronically kept and transmitted. The code has different security access levels according to the user responsibility at the institution and also provides for the analysis of the introduced data, in a quick and efficient way, as well as to notice deadlines, the exceeding of reference levels and situations that require attention. (author)

Nuclear power performance and safety. V.3. Safety and international co-operation

International Nuclear Information System (INIS)

1988-01-01

The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. This objective was accomplished through presentation and discussion of about 200 papers at the Conference. Almost 500 participants and observers from 40 countries and 12 organizations discussed three major questions which were posed as the focus of this Conference: (1) What are the current trends and major issues with regard to performance and safety of nuclear power, the nuclear fuel cycle and radioactive waste management? (2) What steps are being taken or need to be taken to resolve outstanding issues in order to improve the performance of nuclear power with assured safety? (3) What performance objectives and achievements can be anticipated for the 1990s? All presentations of this Conference were divided into six volumes. This is Volume 3 which is devoted to the problems of safety and international cooperation. All presentations of Volume 3 were divided into four sessions as follows: the need for safety in nuclear power programmes (4 papers); international cooperation in nuclear safety (6 papers); technical aspects in plant safety (7 papers); approaches to safety (3 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

2007-08-01

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

International Nuclear Information System (INIS)

Kisner, Roger A.; Mullens, James Allen; Wilson, Thomas L.; Wood, Richard Thomas; Korsah, Kofi; Qualls, A.L.; Muhlheim, Michael David; Holcomb, David Eugene; Loebl, Andy

2007-01-01

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented

A Laboratory Safety Program at Delaware.

Science.gov (United States)

Whitmyre, George; Sandler, Stanley I.

1986-01-01

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

77 FR 70409 - System Safety Program

Science.gov (United States)

2012-11-26

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

National program for the fostering and development of safety culture in the nuclear activities in Cuba

International Nuclear Information System (INIS)

Ferro Fernandez, R.; Guillen Campos, A.

2002-01-01

Since its appearance, as a result of the investigations of the accident in the Chernobyl Nuclear Power Plant, the term Safety Culture has been considered a key element to achieve a high level of safety in the nuclear installations, becoming a basic safety principle, internationally. The Cuban regulatory authority understood from very early the importance of the promotion and development of attitudes and characteristics in the organizations and personnel involved in the nuclear sector, reflecting a high Safety Culture, in order to propitiate a higher involvement of all employees in safety, contributing this way to the prevention of accidents in the nuclear facilities. Although the Cuban Nuclear Program was significantly reduced in the 90's, the regulatory authority has continued working in this direction and assimilated all the international experience for its application in its strategies for the development of a Safety Culture in the nuclear activities in the country. The present work summarizes the Cuban experience in the establishment of a National Program for the fostering and development of a Safety Culture. (author)

Overview of international fusion technology programs

International Nuclear Information System (INIS)

Coffman, F.E.; Baublitz, J.E.; Beard, D.S.; Cohen, M.M.; Dalder, E.N.C.; Finfgeld, C.R.; Haas, G.M.; Head, C.R.; Murphy, M.R.; Nardella, G.R.

1979-01-01

World fusion technology programs, as well as current progress and future plans for the U.S., are discussed. Regarding conceptual design, the international INTOR tokamak study, the Garching Ignition Test Reactor Study, the U.S. Engineering Test Facility conceptual design, the Argonne National Laboratory Commercial Tokamak Study, mirror conceptual designs, and alternate concepts and applications studies are summarized. With regard to magnetics, progress to date in the large coil program and pulsed coil program is summarized. In the area of plasma heating and fueling and exhaust, work on a new positive ion source research and development program at Lawrence Berkeley Laboratory and Oak Ridge National Laboratory is described, as is negative ion work. Tradeoff considerations for radio-frequency heating alternatives are made, and a new 60-100 GHz electron cyclotron heating research and development program is discussed. Progress and plans for solid hydrogen pellet injector development are analyzed, as are plans for a divertor technology initiative. A brief review of the U.S. alternate applications and environment and safety program is included

Krsko NPP Periodic Safety Review program

International Nuclear Information System (INIS)

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

2001-01-01

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

IAEA establishes International Seismic Safety Centre

International Nuclear Information System (INIS)

2008-01-01

Full text: The IAEA today officially inaugurated an international centre to coordinate efforts for protecting nuclear installations against the effects of earthquakes. The International Seismic Safety Centre (ISSC), which has been established within the IAEA's Department of Nuclear Safety and Security, will serve as a focal point on seismic safety for nuclear installations worldwide. ISSC will assist countries on the assessment of seismic hazards of nuclear facilities to mitigate the consequences of strong earthquakes. 'With safety as our first priority, it is vital that we pool all expert knowledge available worldwide to assist nuclear operators and regulators to be well prepared for coping with major seismic events,' said Antonio Godoy, Acting Head of the IAEA's Engineering Safety Section and leader of the ISSC. 'The creation of the ISSC represents the culmination of three decades of the IAEA's active and recognized involvement in this matter through the development of an updated set of safety standards and the assistance to Member States for their application.' To further seismic safety at nuclear installations worldwide, the ISSC will: - Promote knowledge sharing among the international community in order to avoid or mitigate the consequences of extreme seismic events on nuclear installations; - Support countries through advisory services and training courses; and - Enhance seismic safety by utilizing experience gained from previous seismic events in member states. The centre is supported by a scientific committee of high-level experts from academic, industrial and nuclear safety authorities that will advise the ISSC on implementation of its programme. Experts have been nominated from seven specialized areas, including geology and tectonics, seismology, seismic hazard, geotechnical engineering, structural engineering, equipment, and seismic risk. Japan and the United States have both contributed initial funds for creation of the centre, which will be based at

Aviation Safety/Automation Program Conference

Science.gov (United States)

Morello, Samuel A. (Compiler)

1990-01-01

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

AEC controlled area safety program

Energy Technology Data Exchange (ETDEWEB)

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

1969-07-01

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

AEC controlled area safety program

International Nuclear Information System (INIS)

Hendricks, D.W.

1969-01-01

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

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

Spanish Nuclear Safety Research under International Frameworks

Energy Technology Data Exchange (ETDEWEB)

Herranz, L. E.; Reventos, F.; Ahnert, C.; Jimenez, G.; Queral, C.; Verdu, G.; Miro, R.; Gallardo, S.

2013-10-01

The Nuclear Safety research requires a wide international collaboration of several involved groups. In this sense this paper pretends to show several examples of the Nuclear Safety research under international frameworks that is being performed in different Universities and Research Institutions like CIEMAT, Universitat Politecnica de Catalunya (UPC), Universidad Politecnica de Madrid (UPM) and Universitat Politenica de Valencia (UPV). (Author)

Fusion safety program plan

International Nuclear Information System (INIS)

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

1980-09-01

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

Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

International Nuclear Information System (INIS)

2010-01-01

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

Discussion on the Criterion for the Safety Certification Basis Compilation - Brazilian Space Program Case

Science.gov (United States)

Niwa, M.; Alves, N. C.; Caetano, A. O.; Andrade, N. S. O.

2012-01-01

The recent advent of the commercial launch and re- entry activities, for promoting the expansion of human access to space for tourism and hypersonic travel, in the already complex ambience of the global space activities, brought additional difficulties over the development of a harmonized framework of international safety rules. In the present work, with the purpose of providing some complementary elements for global safety rule development, the certification-related activities conducted in the Brazilian space program are depicted and discussed, focusing mainly on the criterion for certification basis compilation. The results suggest that the composition of a certification basis with the preferential use of internationally-recognized standards, as is the case of ISO standards, can be a first step toward the development of an international safety regulation for commercial space activities.

A proposal for an international convention on radiation safety

International Nuclear Information System (INIS)

Ahmed, J.U.

1998-01-01

One century has passed since harmful effects of radiation on living tissues were recognized. Organized efforts to reduce radiation hazards began in early 1920s. Major efforts by the ICRP since 1928, aided by ICRU, greatly helped in formulating principles, policies and guidance for radiation protection. The WHO formally recognized ICRP in 1956 and began implementing ICRP recommendations and guidance throughout the world. The IAEA, after it took office in 1957, began to establish or adopt standards of safety based on ICRP recommendations and provide for application of these standards in the field of atomic energy. Later on, other pertinent international organizations joined IAEA in establishing the Basic Safety Standards on radiation safety. The IAEA has issued, until now, nearly couple of hundred safety related documents on radiation safety and waste management. However, in spite of all such international efforts for three quarter of a century, there has been no effective universal control in radiation safety. Problems exist at the user, national, international and manufacturers and suppliers levels. Other problems are management of spent sources and smuggling of sources across international borders. Although, radiation and radionuclides are used by all countries of the world, regulatory and technical control measures in many countries are either lacking or inadequate. The recommendations and technical guidance provided by the international organizations are only advisory and carry no mandatory force to oblige countries to apply them. Member States approve IAEA safety standards and guides at the technical meetings and General Conference, but many of them do not apply these. An International Convention is, therefore, essential to establish international instrument to ensure universal application of radiation safety. (author)

A new model for accreditation of residency programs in internal medicine.

Science.gov (United States)

Goroll, Allan H; Sirio, Carl; Duffy, F Daniel; LeBlond, Richard F; Alguire, Patrick; Blackwell, Thomas A; Rodak, William E; Nasca, Thomas

2004-06-01

A renewed emphasis on clinical competence and its assessment has grown out of public concerns about the safety, efficacy, and accountability of health care in the United States. Medical schools and residency training programs are paying increased attention to teaching and evaluating basic clinical skills, stimulated in part by these concerns and the responding initiatives of accrediting, certifying, and licensing bodies. This paper, from the Residency Review Committee for Internal Medicine of the Accreditation Council for Graduate Medical Education, proposes a new outcomes-based accreditation strategy for residency training programs in internal medicine. It shifts residency program accreditation from external audit of educational process to continuous assessment and improvement of trainee clinical competence.

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

Science.gov (United States)

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

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

Implementation of a Radiological Safety Coach program

Energy Technology Data Exchange (ETDEWEB)

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

1998-02-01

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

Implementation of a Radiological Safety Coach program

International Nuclear Information System (INIS)

Konzen, K.K.

1998-01-01

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

International validation of safety analyses for nuclear power plants; Mednarodno preverjanje varnostnih analiz za jedrske elektrane

Energy Technology Data Exchange (ETDEWEB)

Gregoric, N; Mavko, B [Institut ' Jozef Stefan' Ljubljana (Yugoslavia)

1988-07-01

Paper describes the participation of 'J.Stefan' Institute in international standard problems for validation of modeling and programs for safety analysis. Listed are main international experimental facilities for collecting data basic for understanding of physical phenomena, code development and validation of modelling and programs. Since the results of international standard problem analyses are published in a joint final report, it is simple to asses the conformance of the results of a particular group with the experiment. Good results from three international exercises done so far, have encouraged the group to currently participate in OECD-ISP-22 which is a model of the Italian three loop PWR. (author)

Liquefied gaseous fuels safety and environmental control assessment program: third status report

Energy Technology Data Exchange (ETDEWEB)

1982-03-01

This Status Report contains contributions from all contractors currently participating in the DOE Liquefied Gaseous Fuels (LG) Safety and Environmental Control Assessment Program and is presented in two principal sections. Section I is an Executive Summary of work done by all program participants. Section II is a presentation of fourteen individual reports (A through N) on specific LGF Program activities. The emphasis of Section II is on research conducted by Lawrence Livermore National Laboratory (Reports A through M). Report N, an annotated bibliography of literature related to LNG safety and environmental control, was prepared by Pacific Northwest Laboratory (PNL) as part of its LGF Safety Studies Project. Other organizations who contributed to this Status Report are Aerojet Energy Conversion Company; Applied Technology Corporation; Arthur D. Little, Incorporated; C/sub v/ International, Incorporated; Institute of Gas Technology; and Massachusetts Institute of Technology. Separate abstracts have been prepared for Reports A through N for inclusion in the Energy Data Base.

Public Health Service Safety Program

Energy Technology Data Exchange (ETDEWEB)

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

1969-07-01

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

Public Health Service Safety Program

International Nuclear Information System (INIS)

McBride, J.R.

1969-01-01

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

Research program on regulatory safety - Overview report 2010

International Nuclear Information System (INIS)

Mailaender, R

2011-01-01

This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2010 and the results obtained. The main highlights of the research program, which was co-ordinated by the Swiss Federal Nuclear Safety Inspectorate ENSI are reported on. Topics reported on include nuclear fuels and materials, the development of a data base on damage and internal incidents, external incidents and human factors. Also, system behaviour and hazardous accident events are reported on, as are radiation protection and waste disposal. Project highlights include the KORA II project, which examined corrosion crack development in austenitic structural materials, the OECD's Halden Reactor Project in the man-technology-organisational area, and work done in the Mont Terri rock research laboratory. Also, national and international co-operation is briefly looked at and work to be done in 2011 is reviewed. A list of current and completed projects completes the report

Assistance of Foreign Countries and International Organizations to Support Safety Improvements at Ignalina NPP

International Nuclear Information System (INIS)

Shevaldin, V.

1997-01-01

International cooperation and assistance for the improving safety of Ignalina NPP is described. Sweden was among the first countries which supported safety improvements at Ignalina NPP. The first project in the cooperation was BARSELINA, Probabilistic Safety Analysis of Ignalina NPP. The cooperation is still bringing significant support to the plant, including improvements in the fire protection, communications system, physical protection, and many other areas. Another one very important source of assistance was Nuclear Safety Account, administered by the EBRD. In 1993 experts of the plant, together with representatives of VATESI and SKI (Sweden) have worked out a short-term safety improvement program SIP-1, which was financed by the EBRD . Eighteen safety related projects were selected, expensive and reliable equipment was procured and installed

Towards an International Approach to Nuclear Safety

International Nuclear Information System (INIS)

Tomihiro Taniguchi

2006-01-01

This document presents in a series of transparencies the different activities of the IAEA: Introduction of International Atomic Energy Agency, Changing world, Changing Technology, Changing Global Security, Developing Innovative Nuclear Energy Systems, Global Nuclear Safety Regime, IAEA Safety Standards: Hierarchy - Global Reference for Striving for Excellence, IAEA Safety Reviews and Services: Integrated Safety Approach, Global Knowledge Network - Asian Nuclear Safety Network, Safety Issues and Challenges, Synergy between Safety and Security, Recent Developments: Safety and Security of Radioactive Sources, Convention on Physical Protection of Nuclear Material (CPPNM), Incident and Emergency Preparedness and Response, Holistic Approach for Safety and Security, Sustainable Development. (J.S.)

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

International Nuclear Information System (INIS)

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

2000-01-01

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

Specifications of the International Atomic Energy Agency's international project on safety assessment driven radioactive waste management solutions

International Nuclear Information System (INIS)

Ghannadi, M.; Asgharizadeh, F.; Assadi, M. R.

2008-01-01

Radioactive waste is produced in the generation of nuclear power and the production and use of radioactive materials in the industry, research, and medicine. The nuclear waste management facilities need to perform a safety assessment in order to ensure the safety of a facility. Nuclear safety assessment is a structured and systematic way of examining a proposed facility, process, operation and activity. In nuclear waste management point of view, safety assessment is a process which is used to evaluate the safety of radioactive waste management and disposal facilities. In this regard the International Atomic Energy Agency is planed to implement an international project with cooperation of some member states. The Safety Assessment Driving Radioactive Waste Management Solutions Project is an international programme of work to examine international approaches to safety assessment in aspects of p redisposal r adioactive waste management, including waste conditioning and storage. This study is described the rationale, common aspects, scope, objectives, work plan and anticipated outcomes of the project with refer to International Atomic Energy Agency's documents, such as International Atomic Energy Agency's Safety Standards, as well as the Safety Assessment Driving Radioactive Waste Management Solutions project reports

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 ...

NASA Aviation Safety Program Systems Analysis/Program Assessment Metrics Review

Science.gov (United States)

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

2003-01-01

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

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

International Nuclear Information System (INIS)

Chung, Dae Wook

2011-01-01

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

Introduction to 'International Handbook of Criticality Safety Benchmark Experiments'

International Nuclear Information System (INIS)

Komuro, Yuichi

1998-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization for Economic Cooperation and Development-Nuclear Energy Agency (OECD-NEA). 'International Handbook of Criticality Safety Benchmark Experiments' was prepared and is updated year by year by the working group of the project. This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used. The author briefly introduces the informative handbook and would like to encourage Japanese engineers who are in charge of nuclear criticality safety to use the handbook. (author)

Pressure Safety Program Implementation at ORNL

Energy Technology Data Exchange (ETDEWEB)

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

2013-01-01

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

National Ignition Facility Project Site Safety Program

International Nuclear Information System (INIS)

Dun, C

2003-01-01

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

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources international basic safety standards

CERN Document Server

International Atomic Energy Agency. Vienna

2014-01-01

The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

Gap Analysis Approach for Construction Safety Program Improvement

Directory of Open Access Journals (Sweden)

Thanet Aksorn

2007-06-01

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

Health, safety and environmental research program

International Nuclear Information System (INIS)

Dinner, P.J.

1983-01-01

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

Seismic safety margins research program overview

International Nuclear Information System (INIS)

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

1978-01-01

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

Safety of radioactive waste management. Proceedings of an international conference

International Nuclear Information System (INIS)

2000-01-01

The principal objective of the Conference was to enable members of the scientific community and representatives of facilities which produce radioactive waste, of bodies responsible for radioactive waste management, of nuclear regulatory bodies and of public interest groups, among others, to engage in an open dialogue. The open dialogue which took place may, by providing policy and decision makers with a basis for political action, prove to be an important step in the search for the international consensus so essential in the area of radioactive waste management. The relevant policies and activities of the IAEA, the European Commission, the OECD Nuclear Energy Agency and the World Health Organization were presented. The evolution, under the aegis of the IAEA, of a de facto international radiation and nuclear safety regime was noted. In the area of radioactive waste safety, this regime consists of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the body of international waste safety standards established by the IAEA and other international organizations, and the IAEA's mechanisms for providing for the application of those standards. The topics covered by the Conference were: Current international co-operative efforts; Recommendations from the International Commission on Radiological Protection; Recommendations from the International Nuclear Safety Advisory Group; Conclusions and recommendations of the International Symposium on the Restoration of Environments with Radioactive Residues; Siting of radioactive waste management facilities; Participation of interested parties; Legislative and general radiation safety aspects; Removal of material from regulatory control (exclusion, exemption and clearance); Predisposal management (dilution, recycling, transmutation, etc.); Near surface disposal; Residues from the mining and processing of radioactive ores; Long term institutional control; Geological disposal

Dark Skies Awareness Programs for the International Year of Astronomy

Science.gov (United States)

Walker, C. E.; Pompea, S. M.

2008-12-01

The loss of a dark night sky as a natural resource is a growing concern. It impacts not only astronomical research, but also our environment in terms of ecology, health, safety, economics and energy conservation. For this reason, "Dark Skies are a Universal Resource" is a cornerstone project for the U.S. International Year of Astronomy (IYA) program in 2009. Its goal is to raise public awareness of the impact of artificial lighting on local environments by getting people involved in a variety of dark skies-related programs. These programs focus on citizen-scientist sky-brightness monitoring programs, a planetarium show, podcasting, social networking, a digital photography contest, the Good Neighbor Lighting Program, Earth Hour, National Dark Skies Week, a traveling exhibit, a video tutorial, Dark Skies Discovery Sites, Astronomy Nights in the (National) Parks, Sidewalk Astronomy, and a Quiet Skies program. Many similar programs are available internationally through the "Dark Skies Awareness" Global Cornerstone Project. Working groups for both the national and international dark skies cornerstone projects are being chaired by the National Optical Astronomy Observatory (NOAO). The presenters from NOAO will provide the "know-how" and the means for session participants to become community advocates in promoting Dark Skies programs as public events at their home institutions. Participants will be able to get information on jump-starting their education programs through the use of well-developed instructional materials and kits. For more information, visit http://astronomy2009.us/darkskies/ and http://www.darkskiesawareness.org/.

Nuclear Criticality Safety Department Qualification Program

International Nuclear Information System (INIS)

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

1996-01-01

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

National HTGR safety program

International Nuclear Information System (INIS)

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

1982-01-01

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

International Safety Regulation and Standards for Space Travel and Commerce

Science.gov (United States)

Pelton, J. N.; Jakhu, R.

The evolution of air travel has led to the adoption of the 1944 Chicago Convention that created the International Civil Aviation Organization (ICAO), headquartered in Montreal, Canada, and the propagation of aviation safety standards. Today, ICAO standardizes and harmonizes commercial air safety worldwide. Space travel and space safety are still at an early stage of development, and the adoption of international space safety standards and regulation still remains largely at the national level. This paper explores the international treaties and conventions that govern space travel, applications and exploration today and analyzes current efforts to create space safety standards and regulations at the national, regional and global level. Recent efforts to create a commercial space travel industry and to license commercial space ports are foreseen as means to hasten a space safety regulatory process.

Hanford internal dosimetry program manual

International Nuclear Information System (INIS)

Carbaugh, E.H.; Sula, M.J.; Bihl, D.E.; Aldridge, T.L.

1989-10-01

This document describes the Hanford Internal Dosimetry program. Program Services include administrating the bioassay monitoring program, evaluating and documenting assessments of internal exposure and dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating internal radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. 13 refs., 16 figs., 42 tabs

Promoting Dark Skies Awareness Programs Beyond the International Year of Astronomy 2009

Science.gov (United States)

Walker, Constance E.; Dark Skies Working Group

2010-01-01

The preservation of dark skies is a growing global concern, yet it is one of the easiest environmental problems people can address on local levels. For this reason, the goal of the International Year of Astronomy 2009 (IYA2009) Dark Skies Awareness Cornerstone Project is to raise public awareness of the impact of artificial lighting on local environments by getting people worldwide involved in a variety of programs. These programs provide resources on light pollution for new technologies like a presence in Second Life and podcasts, for local thematic events at national parks and observatory open houses, for international thematic events like International Dark Skies Week and Earth Hour, for a program in the arts like an international photo contest, for global citizen-science programs that measure night sky brightness worldwide, and for educational materials like a kit with a light shielding demonstration. These programs have been successfully used around the world during IYA2009 to raise awareness of the effects of light pollution on public health, economic issues, ecological consequences, energy conservation, safety and security, and astronomy. The poster will provide an update, take a look ahead at the project's sustainability, and describe how people can be involved in the future. Information about the programs is at www.darkskiesawareness.org.

Bohunice Nuclear Power Plant Safety Upgrading Program

International Nuclear Information System (INIS)

Toth, A.; Fagula, L.

1996-01-01

Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

Effective safety training program design

International Nuclear Information System (INIS)

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

1991-01-01

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

The Department of Energy nuclear criticality safety program

International Nuclear Information System (INIS)

Felty, J.R.

2004-01-01

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

New challenges for the internal safety organisation

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, Per Langå

2003-01-01

Research from several countries indicates that the internal health and safety organisation in most companies is placed in an appendix position. Introduc-tion of learning is a possibility for the development of a stronger and more ef-fective health and safety organisation. This approach has been...

Nuclear power safety

International Nuclear Information System (INIS)

1991-11-01

This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

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

International Nuclear Information System (INIS)

1998-01-01

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

Safety program considerations for space nuclear reactor systems

International Nuclear Information System (INIS)

Cropp, L.O.

1984-08-01

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

USNRC HTGR safety research program overview

International Nuclear Information System (INIS)

Foulds, R.B.

1982-01-01

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

Nuclear Safety through International Cooperation

International Nuclear Information System (INIS)

Flory, Denis

2013-01-01

The Fukushima Daiichi nuclear accident was the worst at a nuclear facility since the Chernobyl accident in 1986. It caused deep public anxiety and damaged confidence in nuclear power. Following this accident, strengthening nuclear safety standards and emergency response has become an imperative at the global level. The IAEA is leading in developing a global approach, and the IAEA Action Plan on Nuclear Safety is providing a comprehensive framework and acting as a significant driving force to identify lessons learned and to implement safety improvements. Strengthening nuclear safety is addressed through a number of measures proposed in the Action Plan including 12 main actions focusing on safety assessments in the light of the accident. Significant progress has been made in assessing safety vulnerabilities of nuclear power plants, strengthening the IAEA's peer review services, improvements in emergency preparedness and response capabilities, strengthening and maintaining capacity building, as well as widening the scope and enhancing communication and information sharing with Member States, international organizations and the public. Progress has also been made in reviewing the IAEA's safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on accident prevention, in particular severe accidents, and emergency preparedness and response.

R&D Challenges for SFR Design and Safety Analysis – Opportunities for International Cooperations

International Nuclear Information System (INIS)

Devictor, Nicolas

2013-01-01

Examples of R&D challenges related to safety have been presented. For any domain, R&D activities includes modelling, codes development and their V&V process, with the support of experimental programs. The success in the R&D will help the safety case and the acceptability of SFR. Some of these activities are relevant for international cooperation especially benchmarks and sharing of experimental facilities. This last point could take benefit of recent catalogues experimental facilities (already operational or in project), for example from the TAREF Task Force of OECD/NEA and the European project ADRIANA

International conference on topical issues in nuclear safety. Contributed papers

International Nuclear Information System (INIS)

2001-01-01

The objective of the Conference was to foster the exchange of information on topical issues in nuclear safety, with the aim of consolidating an international consensus on the present status of these issues, priorities for future work, and needs for strengthening international cooperation, including the IAEA recommendations for future activities. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference: risk informed decision making, influence of external factors on safety, safety of fuel cycle facilities, safety of research reactors, and safety performance indicators

International conference on topical issues in nuclear safety. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The objective of the Conference was to foster the exchange of information on topical issues in nuclear safety, with the aim of consolidating an international consensus on the present status of these issues, priorities for future work, and needs for strengthening international cooperation, including the IAEA recommendations for future activities. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference: risk informed decision making, influence of external factors on safety, safety of fuel cycle facilities, safety of research reactors, and safety performance indicators.

International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

International Nuclear Information System (INIS)

2011-01-01

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

Guidelines for dynamic international programs

International Nuclear Information System (INIS)

Gold, M.A.

1993-01-01

Matters of global concern-deforestation, global warming, biodiversity loss, sustainable development, fuelwood crises, watershed destruction, and large-scale flooding-frequently involve forests and natural resources. In the future, university students will enter a global setting that more than ever depends on a strong knowledge of international issues. USA land-grant universities are attempting to prepare students for this challenge by improving their international programs including forestry. To improve university programs, several factors will need to be addressed and are discussed, with examples, in this article: commitment of the faculty; program specialization; geographic specialization; reward systems for international contributions; international collaboration; recycled dollars within the university; active teaching programs; research; extention and outreach; language training; international faculty; travel grants; twinning relationships with sister institutions; selective in pursuit of international development assistance; and study centers. 6 refs

International cooperation in the safety and environmental assessment for the ITER engineering design activities

International Nuclear Information System (INIS)

Gordon, C.; Baker, D.J.; Bartels, H-W.

1998-01-01

The ITER Project includes design and assessment activities to ensure the safety and environmental attractiveness of ITER and demonstrate that it can be sited in any of the sponsoring Parties with a minimum of site-specific redesign. This paper highlights some of the efforts to develop an international consensus approach for ITER safety design and assessment, including: development of general safety and environmental design criteria; development of quantitative dose-release assessment criteria; development of a radiation protection program; waste characterization; and development of safety analysis guidelines. The high level of interaction, cooperation and collaboration between the Joint Central Team and the Home Teams, and between the safety team and designers, and the spirit of consensus that has guided them have resulted in a safe design for ITER and a safety design and assessment that can meet the needs of the potential host countries. (author)

EPR safety. Consideration of the internal and external hazards in the safety studies

International Nuclear Information System (INIS)

Gueguin, H.

2008-04-01

The author presents the main points of the Preliminary Safety Report of EDF on the EPR reactor safety. It concerns the considerations of the internal (fire, flood, explosions, pipes failures) and external (earthquakes, airplane falls, explosions, exceptional natural disasters, extreme meteorological conditions) damages. It presents how the safety report takes into account the aggression. (A.L.B.)

Implementation of radiation safety program in a medical institution

International Nuclear Information System (INIS)

Palanca, Elena D.

1999-01-01

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

The radiation safety self-assessment program of Ontario Hydro

International Nuclear Information System (INIS)

Armitage, G.; Chase, W.J.

1987-01-01

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

The nuclear power safety programme of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Rosen, M.

1981-01-01

The role of the International Atomic Energy Agency in the field of nuclear power safety is growing. In the period since the Three Mile Island accident, a significant expansion in its nuclear safety programme has taken place. To assure an acceptable safety level world-wide, new emphasis is being placed on the major effort to establish and foster the use of a comprehensive set of internationally agreed safety standards for nuclear power plants. New initiatives are in progress to intensify international co-operative safety efforts through the exchange of information on safety-related operating occurrences, and through a more open sharing of safety research results. Emergency accident assistance lends itself to international co-operation and steps are being taken to establish an emergency assistance programme so the Agency can aid in co-ordinating a timely response to provide, at short notice, help and advice in case of a nuclear power accident. There has been some strengthening of those advisory services which involve missions of international experts primarily to countries with less developed nuclear power programmes, and in conjunction with the Technical Assistance Programme there is a co-ordinated programme for developing countries, involving safety training courses and assistance aimed at promoting an effective national regulatory programme in all countries using nuclear power. This paper discusses the major features of the IAEA activities in nuclear power plant safety. An understanding of the programme and its limitations is essential to its more effective use. Additional initiatives may still be proposed, but the possibilities for international and regional co-operation to assure an adequate level of safety world-wide already exist. (author)

Using Contemporary Leadership Skills in Medication Safety Programs.

Science.gov (United States)

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

2016-04-01

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

The International Criticality Safety Benchmark Evaluation Project (ICSBEP)

International Nuclear Information System (INIS)

Briggs, J.B.

2003-01-01

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organisation for Economic Cooperation and Development (OECD) - Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Israel, Spain, and Brazil are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled 'International Handbook of Evaluated Criticality Safety Benchmark Experiments.' The 2003 Edition of the Handbook contains benchmark model specifications for 3070 critical or subcritical configurations that are intended for validating computer codes that calculate effective neutron multiplication and for testing basic nuclear data. (author)

International survey of living PSA and safety indicators

International Nuclear Information System (INIS)

Holmberg, J.; Laakso, K.; Lehtinen, E.; Bjoere, S.

1992-01-01

The report contains an international overview of applications of living probabilistic assessment and development of operational safety indicators. Features of an ideal living PSA tool are summarized as well as a limited survey of code systems for managing a living probabilistic safety assessment (living PSA) is included. The international survey is used as an input for planning and performance of related tasks within the nordic NKS/SIK-1 project conducted in 1990-93. The research notes are distributed to the Nordic organizations involved or interested in the subject. The report includes an overview and conclusions from technical reports and articles available and presentations and discussions related to development and use of above methods for the evaluation and management of the operational safety of nuclear power plants. A large part of this material is based on material collected and discussed in connection to international specialist meetings relating to the subject

Assuring fish safety and quality in international fish trade

International Nuclear Information System (INIS)

Ababouch, Lahsen . E-mail lahsen.ababouch@fao.org

2006-01-01

International trade in fishery commodities reached US$ 58.2 billion in 2002, a 5% improvement relative to 2000 and a 45% increase over 1992 levels. Within this global trade, developing countries registered a net trade surplus of US$ 17.4 billion in 2002 and accounted for almost 50% by value and 55% of fish exports by volume. This globalization of fish trade, coupled with technological developments in food production, handling, processing and distribution, and the increasing awareness and demand of consumers for safe and high quality food have put food safety and quality assurance high in public awareness and a priority for many governments. Consequently, many countries have tightened food safety controls, imposing additional costs and requirements on imports. As early as 1980, there was an international drive towards adopting preventative HACCP-based safety and quality systems. More recently, there has been a growing awareness of the importance of an integrated, multidisciplinary approach to food safety and quality throughout the entire food chain. Implementation of this approach requires an enabling policy and regulatory environment at national and international levels with clearly defined rules and standards, establishment of appropriate food control systems and programmes at national and local levels, and provision of appropriate training and capacity building. This paper discusses the international framework for fish safety and quality, with particular emphasis on the United Nation's Food and Agricultural Organization's (FAO) strategy to promote international harmonization and capacity building

Assuring fish safety and quality in international fish trade

Energy Technology Data Exchange (ETDEWEB)

Ababouch, Lahsen [United Nations, Food and Agricultural Organization, Chief, Fish Utilization and Marketing Services, FAO Headquarters, F-607 Rome (Italy)]. E-mail lahsen.ababouch@fao.org

2006-07-01

International trade in fishery commodities reached US$ 58.2 billion in 2002, a 5% improvement relative to 2000 and a 45% increase over 1992 levels. Within this global trade, developing countries registered a net trade surplus of US$ 17.4 billion in 2002 and accounted for almost 50% by value and 55% of fish exports by volume. This globalization of fish trade, coupled with technological developments in food production, handling, processing and distribution, and the increasing awareness and demand of consumers for safe and high quality food have put food safety and quality assurance high in public awareness and a priority for many governments. Consequently, many countries have tightened food safety controls, imposing additional costs and requirements on imports. As early as 1980, there was an international drive towards adopting preventative HACCP-based safety and quality systems. More recently, there has been a growing awareness of the importance of an integrated, multidisciplinary approach to food safety and quality throughout the entire food chain. Implementation of this approach requires an enabling policy and regulatory environment at national and international levels with clearly defined rules and standards, establishment of appropriate food control systems and programmes at national and local levels, and provision of appropriate training and capacity building. This paper discusses the international framework for fish safety and quality, with particular emphasis on the United Nation's Food and Agricultural Organization's (FAO) strategy to promote international harmonization and capacity building.

International views on nuclear safety

International Nuclear Information System (INIS)

Birkhofer, A.

2002-01-01

Safety has always been an important objective in nuclear technology. Starting with a set of sound physical principles and prudent design approaches, safety concepts have gradually been refined and cover now a wide range of provisions related to design, quality and operation. Research, the evaluation of operating experiences and probabilistic risk assessments constitute an essential basis and international co-operation plays a significant role in that context. Concerning future developments a major objective for new reactor concepts, such as the EPR, is to practically exclude a severe core damage accident with large scale consequences outside the plant. (author)

Nuclear safety training program (NSTP) for dismantling

International Nuclear Information System (INIS)

Cretskens, Pieter; Lenie, Koen; Mulier, Guido

2014-01-01

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

International program: Feasibility of the evacuation of high-level radioactive wastes under the ocean depths. (Seabed Program)

International Nuclear Information System (INIS)

Barbreau, A.

1990-01-01

The Seabed feasibility program is an international scientific program of research on the feasibility of the disposal of high-level radioactive wastes into the geological formations making up the floor of the great abyssal plains of the oceans. Decided in 1977, the program is aimed at answering the three following questions: 1) are there potentially favourable sites. 2) is the disposal of wastes possible. 3) does the operation present safety guarantees. First initiated by four countries (USA, UK, Japan and France), the program sponsored by the OECD nuclear energy agency was gathering ten countries and the Commission of the European communities in 1988. The techniques of waste disposal by means of drilling in consolidated sediments and penetrators in loose sediments have been studied. The penetrator technique has been the most thoroughly studied, especially through in situ experiments in the Atlantic ocean. The various factors affecting safety have been studied and the radiological consequences of a burial operation assessed through models. It has been concluded that such an operation could be carried out technically under quite satisfying conditions [fr

Medication safety programs in primary care: a scoping review.

Science.gov (United States)

Khalil, Hanan; Shahid, Monica; Roughead, Libby

2017-10-01

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

Strengthening the Global Nuclear Safety Regime. INSAG-21. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2014-01-01

The Global Nuclear Safety Regime is the framework for achieving the worldwide implementation of a high level of safety at nuclear installations. Its core is the activities undertaken by each country to ensure the safety and security of the nuclear installations within its jurisdiction. But national efforts are and should be augmented by the activities of a variety of international enterprises that facilitate nuclear safety - intergovernmental organizations, multinational networks among operators, multinational networks among regulators, the international nuclear industry, multinational networks among scientists, international standards setting organizations and other stakeholders such as the public, news media and non-governmental organizations (NGOs) that are engaged in nuclear safety. All of these efforts should be harnessed to enhance the achievement of safety. The existing Global Nuclear Safety Regime is functioning at an effective level today. But its impact on improving safety could be enhanced by pursuing some measured change. This report recommends action in the following areas: - Enhanced use of the review meetings of the Convention on Nuclear Safety as a vehicle for open and critical peer review and a source for learning about the best safety practices of others; - Enhanced utilization of IAEA Safety Standards for the harmonization of national safety regulations, to the extent feasible; - Enhanced exchange of operating experience for improving operating and regulatory practices; and - Multinational cooperation in the safety review of new nuclear power plant designs. These actions, which are described more fully in this report, should serve to enhance the effectiveness of the Global Nuclear Safety Regime

The role of international cooperation regarding safety assessment development in the SKB research program

International Nuclear Information System (INIS)

Eng, T.; Ahlstrom, P.

1989-01-01

Cooperation and exchange of information with organizations in foreign countries regarding nuclear waste management constitutes an important part of the overall research and development activities of SKB. In the safety assessment of a repository for spent nuclear fuel natural phenomena have to be described with different kinds of models based on both general and site specific data. The international cooperation efforts to achieve models and methods for this type of descriptions, and where SKB are largely part, is summarized in this paper

International Photovoltaic Program Plan

Energy Technology Data Exchange (ETDEWEB)

Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

1979-12-01

The International Photovoltaics Program Plan is in direct response to the Solar Photovoltaic Energy Research, Development, and Demonstration Act of 1978 (PL 95-590). As stated in the Act, the primary objective of the plan is to accelerate the widespread use of photovoltaic systems in international markets. Benefits which could result from increased international sales by US companies include: stabilization and expansion of the US photovoltaic industry, preparing the industry for supplying future domestic needs; contribution to the economic and social advancement of developing countries; reduced world demand for oil; and improvements in the US balance of trade. The plan outlines programs for photovoltaic demonstrations, systems developments, supplier assistance, information dissemination/purchaser assistance, and an informaion clearinghouse. Each program element includes tactical objectives and summaries of approaches. A program management office will be established to coordinate and manage the program plan. Although the US Department of Energy (DOE) had the lead responsibility for preparing and implementing the plan, numerous federal organizations and agencies (US Departments of Commerce, Justice, State, Treasury; Agency for International Development; ACTION; Export/Import Bank; Federal Trade Commission; Small Business Administration) were involved in the plan's preparation and implementation.

Nuclear Data Activities in Support of the DOE Nuclear Criticality Safety Program

International Nuclear Information System (INIS)

Westfall, R.M.; McKnight, R.D.

2005-01-01

The DOE Nuclear Criticality Safety Program (NCSP) provides the technical infrastructure maintenance for those technologies applied in the evaluation and performance of safe fissionable-material operations in the DOE complex. These technologies include an Analytical Methods element for neutron transport as well as the development of sensitivity/uncertainty methods, the performance of Critical Experiments, evaluation and qualification of experiments as Benchmarks, and a comprehensive Nuclear Data program coordinated by the NCSP Nuclear Data Advisory Group (NDAG).The NDAG gathers and evaluates differential and integral nuclear data, identifies deficiencies, and recommends priorities on meeting DOE criticality safety needs to the NCSP Criticality Safety Support Group (CSSG). Then the NDAG identifies the required resources and unique capabilities for meeting these needs, not only for performing measurements but also for data evaluation with nuclear model codes as well as for data processing for criticality safety applications. The NDAG coordinates effort with the leadership of the National Nuclear Data Center, the Cross Section Evaluation Working Group (CSEWG), and the Working Party on International Evaluation Cooperation (WPEC) of the OECD/NEA Nuclear Science Committee. The overall objective is to expedite the issuance of new data and methods to the DOE criticality safety user. This paper describes these activities in detail, with examples based upon special studies being performed in support of criticality safety for a variety of DOE operations

Occupational Safety and Health Programs in Career Education.

Science.gov (United States)

DiCarlo, Robert D.; And Others

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

Sandia Laboratories environment and safety programs

International Nuclear Information System (INIS)

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

1975-01-01

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

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

Science.gov (United States)

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

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

International conference on the operational safety performance in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2005-01-01

In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

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

Science.gov (United States)

2013-07-19

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

75 FR 15484 - Railroad Safety Technology Program Grant Program

Science.gov (United States)

2010-03-29

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

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

International Nuclear Information System (INIS)

1980-05-01

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

High-heat tank safety issue resolution program plan

International Nuclear Information System (INIS)

Wang, O.S.

1993-12-01

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

IRSN research programs concerning reactor safety

International Nuclear Information System (INIS)

Bardelay, J.

2005-01-01

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

Safety sans Frontières: An International Safety Culture Model.

Science.gov (United States)

Reader, Tom W; Noort, Mark C; Shorrock, Steven; Kirwan, Barry

2015-05-01

The management of safety culture in international and culturally diverse organizations is a concern for many high-risk industries. Yet, research has primarily developed models of safety culture within Western countries, and there is a need to extend investigations of safety culture to global environments. We examined (i) whether safety culture can be reliably measured within a single industry operating across different cultural environments, and (ii) if there is an association between safety culture and national culture. The psychometric properties of a safety culture model developed for the air traffic management (ATM) industry were examined in 17 European countries from four culturally distinct regions of Europe (North, East, South, West). Participants were ATM operational staff (n = 5,176) and management staff (n = 1,230). Through employing multigroup confirmatory factor analysis, good psychometric properties of the model were established. This demonstrates, for the first time, that when safety culture models are tailored to a specific industry, they can operate consistently across national boundaries and occupational groups. Additionally, safety culture scores at both regional and national levels were associated with country-level data on Hofstede's five national culture dimensions (collectivism, power distance, uncertainty avoidance, masculinity, and long-term orientation). MANOVAs indicated safety culture to be most positive in Northern Europe, less so in Western and Eastern Europe, and least positive in Southern Europe. This indicates that national cultural traits may influence the development of organizational safety culture, with significant implications for safety culture theory and practice. © 2015 Society for Risk Analysis.

A Computer Program for Assessing Nuclear Safety Culture Impact

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

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

Atomic bomb suffering and Chernobyl accident lessons learnt from international medical aid programs

International Nuclear Information System (INIS)

Yamashita, Shunichi

2005-01-01

The cooperative medical projects between Nagasaki University and countries of the former USSR have had being performed in mainly two regions: Chernobyl and Semipalatinsk since 1990 and 1995, respectively. The 21 st Center of Excellence (COE) program of ''International Consortium for Medical Care of Hibakusha and Radiation Life Science'' recently established in Nagasaki University can now serve our knowledge and experience much more directly. Its activity can be further extended to the radiocontaminated areas around the world, and based on the lessons of the past, it can indeed contribute to the future planning of the Network of Excellence (NOE) for Radiation Education Program as well as Radiation Emergency Medical Preparedness and Assistance under the auspices of the WHO-REMPAN. Within the frame of International Consortium of Radiation Research, a molecular epidemiology of thyroid diseases are now conducted in our departments in addition to international medical assistance. The clue of radiation-associated thyroid carcinogenesis may give us a new concept on experimental and epidemiological approaches to low dose radiation effects on human health, including those of internal radiation exposure. Concerning the role and responsibility of our work to the public, to avoid unnecessary radiophobia and to correctly understand radiation hazard and safety, we must build a bridge between basic research and widely open public education. Therefore, it is of high necessity to continuously work on clarification of the effects of ionizing radiation on human beings worldwide and to contribute the development of general guideline of radiation safety and radiation hazard, and to strive for the creation of substantiated radiation protection programs. (author)

Atomic bomb suffering and Chernobyl accident lessons learnt from international medical aid programs

Energy Technology Data Exchange (ETDEWEB)

Yamashita, Shunichi [Nagasaki Univ. Graduate School of Biomedical Sciences, Atomic Bomb Disease Inst., Dept. of Molecular Medicine, Nagasaki (Japan)

2005-03-01

The cooperative medical projects between Nagasaki University and countries of the former USSR have had being performed in mainly two regions: Chernobyl and Semipalatinsk since 1990 and 1995, respectively. The 21{sup st} Center of Excellence (COE) program of ''International Consortium for Medical Care of Hibakusha and Radiation Life Science'' recently established in Nagasaki University can now serve our knowledge and experience much more directly. Its activity can be further extended to the radiocontaminated areas around the world, and based on the lessons of the past, it can indeed contribute to the future planning of the Network of Excellence (NOE) for Radiation Education Program as well as Radiation Emergency Medical Preparedness and Assistance under the auspices of the WHO-REMPAN. Within the frame of International Consortium of Radiation Research, a molecular epidemiology of thyroid diseases are now conducted in our departments in addition to international medical assistance. The clue of radiation-associated thyroid carcinogenesis may give us a new concept on experimental and epidemiological approaches to low dose radiation effects on human health, including those of internal radiation exposure. Concerning the role and responsibility of our work to the public, to avoid unnecessary radiophobia and to correctly understand radiation hazard and safety, we must build a bridge between basic research and widely open public education. Therefore, it is of high necessity to continuously work on clarification of the effects of ionizing radiation on human beings worldwide and to contribute the development of general guideline of radiation safety and radiation hazard, and to strive for the creation of substantiated radiation protection programs. (author)

A Proposal for the Common Safety Approach of Space Programs

Science.gov (United States)

Grimard, Max

2002-01-01

For all applications, business and systems related to Space programs, Quality is mandatory and is a key factor for the technical as well as the economical performances. Up to now the differences of applications (launchers, manned space-flight, sciences, telecommunications, Earth observation, planetary exploration, etc.) and the difference of technical culture and background of the leading countries (USA, Russia, Europe) have generally led to different approaches in terms of standards and processes for Quality. At a time where international cooperation is quite usual for the institutional programs and globalization is the key word for the commercial business, it is considered of prime importance to aim at common standards and approaches for Quality in Space Programs. For that reason, the International Academy of Astronautics has set up a Study Group which mandate is to "Make recommendations to improve the Quality, Reliability, Efficiency, and Safety of space programmes, taking into account the overall environment in which they operate : economical constraints, harsh environments, space weather, long life, no maintenance, autonomy, international co-operation, norms and standards, certification." The paper will introduce the activities of this Study Group, describing a first list of topics which should be addressed : Through this paper it is expected to open the discussion to update/enlarge this list of topics and to call for contributors to this Study Group.

Business and International Education Program

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2012

2012-01-01

This paper presents an overview of the Business and International Education Program of the International Education Programs Service (IEPS). This program provides funds to institutions of higher education that enter into an agreement with a trade association, a business, or both for the purpose of improving business curriculum and as a means of…

Nuclear safety: an international approach: the convention on nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1994-01-01

This paper is a general presentation of the IAEA Convention on Nuclear Safety which has already be signed by 50 countries and which is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The paper gives a review of its development and some key provisions for a better understanding of how this agreement will operate in practice. The Convention consists of an introductory preamble and four chapters consisting of 35 articles dealing with: the principal objectives, definitions and scope of application; the various obligations (general provisions, legislation, responsibility and regulation, general safety considerations taking into account: the financial and human resources, the human factors, the quality assurance, the assessment and verification of safety, the radiation protection and the emergency preparedness; the safety of installations: sitting, design and construction, operation); the periodic meetings of the contracting parties to review national reports on the measures taken to implement each of the obligations, and the final clauses and other judicial provisions common to international agreements. (J.S.). 1 append

Nuclear criticality safety program at the Fuel Cycle Facility

International Nuclear Information System (INIS)

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

1994-01-01

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

Cabri - water loop a new IPSN-OECD international research program

International Nuclear Information System (INIS)

Anon.

2001-01-01

In 1993, the Institut de Protection et de Surete Nucleaire (IPSN, the French Nuclear Safety and Radiation Protection Institute) working with EDF (electric utilities) and backed by the NRC (Nuclear Regulatory Commission, USA) launched a research program, dubbed Cabri REP Na addressing uranium oxide-based fuels and MOX fuels. So far twelve tests have been conducted including eight on UO 2 fuel and four on MOX fuel. More testing is now required to determine fuel performance at higher specific burn-up levels in typical PWR (Pressurized Water Reactor) conditions, the purpose being to determine the acceptance criteria for tomorrow's fuels. IPSN has defined a new research program for the Cabri reactor. The OECD's Nuclear Energy Agency is quarterbacking the international program called 'Cabri-Water Loop'. (authors)

Safety upgrading program in NPP Mochovce

International Nuclear Information System (INIS)

Baumeister, P.

1999-01-01

EMO interest is to operate only nuclear power plants with high standards of nuclear safety. This aim EMO declare on preparation completion and commissioning of Mochovce Nuclear Power Plant. Wide co-operation of our company with International Atomic Energy Agency and west European Inst.ions and companies has been started with aim to fulfil the nuclear safety requirements for Mochovce NPP. Set of 87 safety measures was implemented at Mochovce Unit 1 and is under construction at Unit 2. Mochovce NPP approach to safety upgrading implementation is showed on chosen measures. This presentation is focused on the issues category III.(author)

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

Science.gov (United States)

1998-08-26

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

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

International Nuclear Information System (INIS)

Bennett, G.L.

1979-09-01

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

Tenaga Nasional Berhad dam safety and surveillance program

International Nuclear Information System (INIS)

Jansen Luis; Zulkhairi Abd Talib

2006-01-01

This paper discusses the current practice of dam surveillance, which includes dam monitoring which is a process of visual inspections, measuring, processing, compiling and analyzing dam instrumentation data to determine the performance of a dam. The prime objective of the dam surveillance system is to ensure that any occurrence and development of safety deficiencies and problems are quickly detected, identified, analyzed and the required remedial actions are determined and consequently carried out in due time. In brief, the section is responsible to ensure that the dam monitoring and surveillance works are implemented as per scheduled and in accordance with the requirement and guidelines prepared by the dam designers and in accordance with international commission on large dams, ICOLD. The paper also illustrates and recommends an alternative approach for dam surveillance program using risk management approach, which is currently being actively adopted by some countries like USA, Canada, Australia and etc, towards improving the dam safety management and the decision making process. The approach provides a wider area of opportunity, improvements and benefits particular in the evaluation and modifications to the dam performance and safety. The process provides an effective and efficient tool for the decision makers and engineers through a comprehensive evaluation and a good understanding of the hazards, risks and consequences in relation to dam safety investigations. (Author)

AEC sets five year nuclear safety research program

International Nuclear Information System (INIS)

Anon.

1976-01-01

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

Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

International Nuclear Information System (INIS)

Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

International contributions of JNES on seismic safety areas

International Nuclear Information System (INIS)

Ebisawa, Katsumi; Uchiyama, Yuichi; Yamada, Hiroyuki

2010-01-01

JNES actively promotes the international cooperation in seismic safety areas, aiming to play a role as the important international hub for it. To meet this purpose, JNES is now mainly focusing on the increased support of the international organizations including IAEA and the technological improvement in the seismic related assessment of Asian countries. This paper summarizes these efforts made by JNES. (author)

Directory of Academic Programs in Occupational Safety and Health.

Science.gov (United States)

Weis, William J., III; And Others

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

Fundamentals of a patient safety program

International Nuclear Information System (INIS)

Frush, Karen S.

2008-01-01

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

Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

International Nuclear Information System (INIS)

Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

2004-01-01

Full text: The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by (1) implementing safety upgrades, or (2) assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

International Nuclear Information System (INIS)

Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

2004-01-01

The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by implementing safety upgrades, or assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

49 CFR 659.19 - System safety program plan: contents.

Science.gov (United States)

2010-10-01

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

Can international safety overcome national prejudice

International Nuclear Information System (INIS)

Thomas, S.

1986-01-01

Following the accident at the Chernobyl nuclear power plant, a proposal has been made that the International Atomic Energy Agency (IAEA) should carry out a programme of reactor assessments and inspections to ensure that the plant is competently run. The 13 proposals for improving safety that arose from the recent IAEA meeting in Vienna about the events at Chernobyl are listed. They also propose international collaboration on many points. This article draws attention to the difficulties in achieving international cooperation. Comparison is made with the case of international air and marine transport and an attempt to get an agreement to reduce emissions of acid rain precursors by 30%. The essential requirements for international regulation are stated. Four specific activities that could be covered are discussed. These are inspection of operating plant, enforcement of minimum standards for routine emissions, establishment of design standards and establishment of post-accident procedures for international co-operation. (UK)

Current status of international cooperation on nuclear safety research

International Nuclear Information System (INIS)

Katsuragi, Satoru

1984-01-01

JAERI (Japan Atomic Energy Research Institute), as a representative organization in Japan, has been participating in many international cooperations on nuclear safety research. This report reviews the recent achievement and evolution of the international cooperative safety studies. Twelve projects that are based on the agreements between JAERI and foreign organizations are reviewed. As the fuel irradiation studies, the recent achievement of the OECD Halden Reactor Project and the agreement between Pacific Northwest Laboratories, Battelle Memorial Institute, and JAERI are explained. As for the study of reactivity accident, the cooperation of the NSRR (Nuclear Safety Research Reactor) project in Japan with PBF, PNS and PHEBUS projects in the U.S., West Germany and France, respectively, are now in progress. The fuel performance in abnormal transient and the experiment and analysis of severe fuel damage are the new areas of international interest. The OECD/LOFT project and ROSA-4 projects are also explained in connection with the FP source term problem and the analysis codes such as RELAP-5 and TRAC. As the safety studies associated with the downstream of the nuclear fuel cycle, the BEFAST project of IAEA and the ISIRS project of OECD/NEA are shortly reviewed. (Aoki, K.)

International Cooperation of the Republic of Croatia in the Field of Nuclear Safety

International Nuclear Information System (INIS)

Novosel, N.; Rosandic, L.

2010-01-01

International cooperation of the Republic of Croatia in the field of nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Nuclear Safety is responsible, in cooperation with other state administration bodies, where applicable. According to the Nuclear Safety Act (OG 73/2003) the State Office for Nuclear Safety: 'coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia'; 'fulfills the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons' and 'cooperates with international organizations and associations in the area of nuclear safety, and appoints its own expert representatives to take part in the work of such organizations and associations or to monitor their work'. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of nuclear safety, will be presented. Also, cooperation with other international organizations and associations in the nuclear area, such as Nuclear Suppliers Group, Zangger Committee, Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, will be described.(author).

International handbook of evaluated criticality safety benchmark experiments

International Nuclear Information System (INIS)

2010-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirement and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 55,000 pages and contain 516 evaluations with benchmark specifications for 4,405 critical, near critical, or subcritical configurations, 24 criticality alarm placement / shielding configurations with multiple dose points for each, and 200 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these evaluations; however, benchmark specifications are not derived for such experiments (in some cases models are provided in an appendix). Approximately 770 experimental configurations are categorized as unacceptable for use as criticality safety benchmark experiments. Additional evaluations are in progress and will be

International Research and Studies Program

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2012

2012-01-01

The International Research and Studies Program supports surveys, studies, and instructional materials development to improve and strengthen instruction in modern foreign languages, area studies, and other international fields. The purpose of the program is to improve and strengthen instruction in modern foreign languages, area studies and other…

India's power program and its concern over environmental safety

International Nuclear Information System (INIS)

Prasad, G.E.; Mittra, J.

2001-01-01

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

Progress toward international agreement to improve reactor safety

International Nuclear Information System (INIS)

Lieberman, J.I.; Graham, B.

1993-01-01

Representatives of nearly one-half of the 114 member states of the International Atomic Energy Agency (IAEA), including the United States, have participated in the development of an international nuclear safety conventions proposed multilateral treaty to improve civil nuclear power reactor safety. A preliminary draft of the convention has been developed (referred to as the draft convention for this report), but discussions are continuing, and when the final convention text will be completed and presented to IAEA member states for signature is uncertain. This report responds to the former and current Chairman's request that we provide information on the development of the nuclear safety convention, including a discussion of (1) the draft convention's scope and objectives, (2) how the convention will be implemented and monitored, (3) the views of selected country representatives on what provisions should be included in the draft convention, and (4) the convention's potential benefits and limitations

Thermonuclear generation program: risks and safety; Programa de geracao termonuclear: seus riscos e segurancas

Energy Technology Data Exchange (ETDEWEB)

Goes, Alexandre Gromann de Araujo

1999-07-01

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

Safety Test Program Summary SNAP 19 Pioneer Heat Source Safety Program

Energy Technology Data Exchange (ETDEWEB)

None,

1971-07-01

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

International nuclear safety center database on material properties

International Nuclear Information System (INIS)

Fink, J.K.

1996-01-01

International nuclear safety center database on the following material properties is described: fuel, cladding,absorbers, moderators, structural materials, coolants, concretes, liquid mixtures, uranium dioxide

The NASA Aviation Safety Program: Overview

Science.gov (United States)

Shin, Jaiwon

2000-01-01

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

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

The main requirements of the International Basic Safety Standards

International Nuclear Information System (INIS)

Webb, G.A.M.

1998-01-01

The main requirements of the new international basic safety standards are discussed, including such topics as health effects of ionizing radiations, the revision of basic safety standards, the requirements for radiation protection practices, the requirements for intervention,and the field of regulatory infrastructures. (A.K.)

Decoupling from international food safety standards

DEFF Research Database (Denmark)

Mercado, Geovana; Hjortsø, Carsten Nico; Honig, Benson

2018-01-01

rural producers who, grounded in culturally-embedded food safety conceptions, face difficulties in complying. We address this gap here through a multiple case study involving four public school feeding programs that source meals from local rural providers in the Bolivian Altiplan. Institutional logics...... in the market. These include: (1) partial adoption of formal rules; (2) selective adoption of convenient rules; and (3) ceremonial adoption to avoid compliance. Decoupling strategies allow local actors to largely disregard the formal food safety regulations while accommodating traditional cultural practices...

The US DOE EM international program

Energy Technology Data Exchange (ETDEWEB)

Elmetti, Rosa R.; Han, Ana M. [U.S. Department of Energy, Washington, D.C. (United States); Roach, Jay A. [Nexergy Technical, LLC., Falls Church, Virginia (United States)

2013-07-01

The U.S. Department of Energy (DOE) Office of Environmental Management (EM) conducts international collaboration activities in support of U.S. policies and objectives regarding the accelerated risk reduction and remediation of environmental legacy of the nations' nuclear weapons program and government sponsored nuclear energy research. The EM International Program supported out of the EM Office of the Associate Principal Deputy Assistant Secretary pursues collaborations with foreign government organizations, educational institutions and private industry to assist in identifying technologies and promote international collaborations that leverage resources and link international experience and expertise. In fiscal year (FY) 2012, the International Program awarded eight international collaborative projects for work scope spanning waste processing, groundwater and soil remediation, deactivation and decommissioning (D and D) and nuclear materials disposition initiatives to seven foreign organizations. Additionally, the International Program's scope and collaboration opportunities were expanded to include technical as well as non-technical areas. This paper will present an overview of the on-going tasks awarded in FY 2012 and an update of upcoming international activities and opportunities for expansion into the remainder of FY 2013 and beyond. (authors)

International electives in neurology training: a survey of US and Canadian program directors.

Science.gov (United States)

Lyons, Jennifer L; Coleman, Mary E; Engstrom, John W; Mateen, Farrah J

2014-01-14

To ascertain the current status of global health training and humanitarian relief opportunities in US and Canadian postgraduate neurology programs. There is a growing interest among North American trainees to pursue medical electives in low- and middle-income countries. Such training opportunities provide many educational and humanitarian benefits but also pose several challenges related to organization, human resources, funding, and trainee and patient safety. The current support and engagement of neurology postgraduate training programs for trainees to pursue international rotations is unknown. A survey was distributed to all program directors in the United States and Canada (December 2012-February 2013) through the American Academy of Neurology to assess the training opportunities, institutional partnerships, and support available for international neurology electives. Approximately half of responding programs (53%) allow residents to pursue global health-related electives, and 11% reported that at least 1 trainee participated in humanitarian relief during training (survey response rate 61%, 143/234 program directors). Canadian programs were more likely to allow residents to pursue international electives than US programs (10/11, 91% vs 65/129, 50%, p = 0.023). The number of trainees participating in international electives was low: 0%-9% of residents (55% of programs) and 10%-19% of residents (21% of programs). Lack of funding was the most commonly cited reason for residents not participating in global health electives. If funding was available, 93% of program directors stated there would be time for residents to participate. Most program directors (75%) were interested in further information on global health electives. In spite of high perceived interest, only half of US neurology training programs include international electives, mostly due to a reported lack of funding. By contrast, the majority of Canadian programs that responded allow international

International standardization of safety requirements for fast reactors

International Nuclear Information System (INIS)

2011-06-01

Japan Atomic Energy Agency (JAEA) is conducting the FaCT (Fast Reactor Cycle Technology Development) project in cooperation with Japan Atomic Power Company (JAPC) and Mitsubishi FBR systems inc. (MFBR), where an advanced loop-type fast reactor named JSFR (Japan Sodium-cooled Fast Reactor) is being developed. It is important to develop software technologies (a safety guideline, safety design criteria, safety design standards etc.) of FBRs as well as hardware ones (a reactor plant itself) in order to address prospective worldwide utilization of FBR technology. Therefore, it is expected to establish a rational safety guideline applicable to the JSFR and harmonized with national nuclear-safety regulations as well, including Japan, the United States and the European Union. This report presents domestic and international status of safety guideline development for sodium-cooled fast reactors (SFRs), results of comparative study for safety requirements provided in existing documents and a proposal for safety requirements of future SFRs with a roadmap for their refinement and worldwide utilization. (author)

National and international safety, safeguardability and security

International Nuclear Information System (INIS)

Wakabayashi, Hiroaki

1987-01-01

All nuclear power and fuel cycle facility development must comply with the predecided national regulation and security codes which each country's Atomic Energy Commission stipulates. Those codes will basically evolve as technologies and the social system will develop, change and shift. It is also to be noted that the IAEA's international guidelines have been adopted particularly by developing countries as a good reference for their proper establishment of their safety codes. The report first discusses the plant safety regulation of the inherently safe reactors in comparison to the existing code (or licensing guide) of the Japanese government. Then the new trend seen now in a regulatory body (the US NRC) is reviewed and a proposal of the smooth transition into the new philosophy is presented. In the second part of the paper, the fuel safeguarding and facility security (or physical protection) are discussed, because in the case of inherently safe reactors like ISER-PIUS, it seems that safety has much more to do with the safeguard and the security. In the third part, the international relevances to the security of the ISER-PIUS are discussed, because any ISER-PIUS will be meaningless unless they are used extensively and freely in any part of the world precluding the security concerns. In collaborative use of the state and international codes, regulatory guides and practices, it is evident that ISER-PIUS system can clear the requirements on all the aspects by ample margin. (Nogami, K.)

German Light-Water-Reactor Safety-Research Program

International Nuclear Information System (INIS)

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

1977-01-01

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

Dark Skies Awareness Programs for the International Year of Astronomy

Science.gov (United States)

Walker, Constance E.; US IYA Dark Skies Working Group

2009-05-01

The arc of the Milky Way seen from a truly dark location is part of our planet's cultural and natural heritage. More than 1/5 of the world population, 2/3 of the United States population and 1/2 of the European Union population have already lost naked-eye visibility of the Milky Way. This loss, caused by light pollution, is a serious and growing issue that impacts astronomical research, the economy, ecology, energy conservation, human health, public safety and our shared ability to see the night sky. For this reason, "Dark Skies” is a cornerstone project of the International Year of Astronomy. Its goal is to raise public awareness of the impact of artificial lighting on local environments by getting people worldwide involved in a variety of programs that: 1) Teach about dark skies using new technology (e.g., an activity-based planetarium show on DVD, podcasting, social networking on Facebook and MySpace, a Second Life presence) 2) Provide thematic events on light pollution at star parties and observatory open houses (Dark Skies Discovery Sites, Nights in the (National) Parks, Sidewalk Astronomy) 3) Organize events in the arts (e.g., a photography contest) 4) Involve citizen-scientists in naked-eye and digital-meter star hunting programs (e.g., GLOBE at Night, "How Many Stars?", the Great World Wide Star Count and the radio frequency interference equivalent: "Quiet Skies") and 5) Raise awareness about the link between light pollution and public health, economic issues, ecological consequences, energy conservation, safety and security, and astronomy (e.g., The Starlight Initiative, World Night in Defense of Starlight, International Dark Sky Week, International Dark-Sky Communities, Earth Hour, The Great Switch Out, a traveling exhibit, downloadable posters and brochures). The poster will provide an update, describe how people can continue to participate, and take a look ahead at the program's sustainability. For more information, visit www.darkskiesawareness.org.

EPR meeting international safety standards with margin

International Nuclear Information System (INIS)

Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

2005-01-01

The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

EPR meeting international safety standards with margin

International Nuclear Information System (INIS)

Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

2005-01-01

The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification in with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

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

Science.gov (United States)

2011-12-01

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

Patient Safety and Healthcare Quality

Directory of Open Access Journals (Sweden)

Aikaterini Toska

2012-01-01

Full Text Available Introduction: Due to a variety of circumstances and world-wide research findings, patient safety andquality care during hospitalization have emerged as major issues. Patient safety deficits may burdenhealth systems as well as allocated resources. The international community has examined severalproposals covering general and systemic aspects in order to improve patient safety; several long-termprograms and strategies have also been implemented promoting the participation of health-relatedagents, and also government agencies and non-governmental organizations.Aim: Those factors that have negative correlations with patient safety and quality healthcare weredetermined; WHO and EU programs as well as the Greek health policy were also reviewed.Method: Local and international literature was reviewed, including EU and WHO official publications,by using the appropriate keywords.Conclusions: International cooperation on patient safety is necessary in order to improvehospitalization and healthcare quality standards. Such incentives depend heavily on establishing worldwideviable and effective health programs and planning. These improvements also require further stepson safe work procedures, environment safety, hazard management, infection control, safe use ofequipment and medication, and sufficient healthcare staff.

A cost-effective methodology to internalize nuclear safety in nuclear reactor conceptual design

International Nuclear Information System (INIS)

Gimenez, M.; Grinblat, P.; Schlamp, M.

2003-01-01

A new methodology to perform nuclear reactor design, balancing safety and economics at the conceptual engineering stage, is presented in this work. The goal of this integral methodology is to take into account safety aspects in an optimization design process where the design variables are balanced in order to obtain a better figure of merit related with reactor economic performance. Design parameter effects on characteristic or critical safety variables, chosen from reactor behavior during accidents (safety performance indicators), are synthesized on Design Maps. These maps allow one to compare the safety indicator with limits, which are determined by design criteria or regulations, and to transfer these restrictions to the design parameters. In this way, reactor dynamic response and other safety aspects are integrated in a global optimization process, by means of additional rules to the neutronic, thermal-hydraulic, and mechanical calculations. An application of the methodology, implemented in Integrated Reactor Evaluation Program 3 (IREP3) code, to optimize safety systems of CAREM prototype is presented. It consists in balancing the designs of the Emergency Injection System (EIS), the Residual Heat Removal System (RHRS), the primary circuit water inventory and the containment height, to cope with loss of coolant and loss of heat sink (LOHS) accidental sequences, taking into account cost and reactor performance. This methodology turns out to be promising to internalize cost-efficiently safety issues. It also allows one to evaluate the incremental costs of implementing higher safety levels

Safety guidance and inspection program for particle accelerator

Energy Technology Data Exchange (ETDEWEB)

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

2001-03-15

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

Research program on nuclear technology and nuclear safety - Overview report 2010

International Nuclear Information System (INIS)

Cavedon, J.-M.

2011-01-01

This comprehensive report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2010 and the results obtained. The main highlights of the research program, which was co-ordinated by the Paul Scherrer Institute PSI are presented and discussed. Work done within the STARS program on third-generation nuclear power stations is discussed, as is that carried out on probabilistic safety analyses and human reliability. Analysis of activated materials and MOX nuclear fuel assemblies is discussed. A further project examined aging mechanisms in pressure-loaded components. Processes involved in serious accidents and cooling media loss were also examined. Other fluid-dynamic processes involved, along with other factors, are discussed. Work done on the upgrade of the PROTEUS experimental reactor is discussed, as is that done in connection with PSI's hot laboratory and on radiation-induced creeping in structural materials. Fuel cycles and the disposal of radioactive wastes are looked at and the optimisation of safety in sodium-cooled reactors is discussed. Energy economics aspects and national and international co-operation are briefly looked at and work to be done in 2011 is reviewed. A list of current and completed projects completes the report

International review of Kursk unit 1 in-depth safety analysis report

International Nuclear Information System (INIS)

Chouha, M.; Bolshov, L.; Butcher, P.; Janke, R.; Parsons, T.; Weber, J.P.

2004-01-01

The paper presents the objectives, organisation, main findings and conclusions of the international review of the Kursk unit 1 safety analysis report (K1IRSR). The K1IRSR was administered by RISKAUDIT IRSN/GRS international and carried out by international experts from 7 western countries plus the Russian Federation, under the supervision of the safety review group (SRG) of the European bank for reconstruction and development (EBRD). The project was financed by the nuclear safety account (NSA) administered by the EBRD. The Russian experts worked under a contract with IBRAE financed by Rosenergoatom. The main conclusions were that the SAR followed a correct approach, broadly in line with Russian and international guidance documents, but needed improvement in structure and content. It established that the safety level of the unit has been increased significantly by the modernisation programme. The important deviations of the unit from current Russian regulations and the IAEA safety issues for RBMK are either fully resolved or are being addressed to the extent possible by compensatory measures to further reduce the risk. The K1IRSR experts have made a number of recommendations for improvement of the K1SAR. The authors agreed to take the recommendations into account in future revision of the K1SAR. (orig.)

India's power programs and its concern over environmental safety

International Nuclear Information System (INIS)

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

2000-01-01

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

15 CFR 752.11 - Internal Control Programs.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Internal Control Programs. 752.11... COMPREHENSIVE LICENSE § 752.11 Internal Control Programs. (a) Scope—(1) Introduction. It is through Internal Control Programs (ICPs) that the SCL holder and the consignee assure that exports and reexports are not...

ICSBEP-2007, International Criticality Safety Benchmark Experiment Handbook

International Nuclear Information System (INIS)

Blair Briggs, J.

2007-01-01

1 - Description: The Critically Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United Sates Department of Energy. The project quickly became an international effort as scientist from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization of Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA). This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material. The example calculations presented do not constitute a validation of the codes or cross section data. The work of the ICSBEP is documented as an International Handbook of Evaluated Criticality Safety Benchmark Experiments. Currently, the handbook spans over 42,000 pages and contains 464 evaluations representing 4,092 critical, near-critical, or subcritical configurations and 21 criticality alarm placement/shielding configurations with multiple dose points for each and 46 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. The handbook is intended for use by criticality safety analysts to perform necessary validations of their calculational techniques and is expected to be a valuable tool for decades to come. The ICSBEP Handbook is available on DVD. You may request a DVD by completing the DVD Request Form on the internet. Access to the Handbook on the Internet requires a password. You may request a password by completing the Password Request Form. The Web address is: http://icsbep.inel.gov/handbook.shtml 2 - Method of solution: Experiments that are found

Design of an internal dosimetry program

International Nuclear Information System (INIS)

Wu, C.F.; Goff, T.E.

2004-01-01

Measurement of radiation dose is an essential element of radiation protection programs at nuclear facilities. To protect workers and demonstrate compliance with regulatory requirements, dosimetry programs must be established based on sound technical basis. Historically, external exposure was controlled by occupational dose limits. Internal exposure to radionuclides was limited by maximum permissible body burden and maximum permissible concentration. With the issuance of ICRP 26, ICRP 30, DOE Order 5480.11, DOE/EH-0256T, and the new 10 CFR 20, it has become a requirement that internal dose be assessed and the sum of internal and external doses be maintained below regulatory limits. Nuclear facilities are required to have internal dose evaluation programs adequate to demonstrate compliance with radiation protection standards (RPSs). The Waste Isolation Pilot Plant is a DOE facility designed to demonstrate safe disposal of transuranic (TRU) wastes in an ancient salt bed 2,150 feet underground. Internal dose measurement is required to support waste handling activities. This paper describes the technical basis for the WIPP Internal Dosimetry Program. (author)

EPRI program in water reactor safety

International Nuclear Information System (INIS)

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

1975-01-01

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

Education and training on radiation safety for Asian countries

International Nuclear Information System (INIS)

Kitahara, Y.; Sakurai, N.; Kamei, M.

1993-01-01

The long-term program for development and Utilization of nuclear energy planned by Japan Atomic Energy Commission decided to promote the international corporation with Asian countries in nuclear fields. PNC (Power Reactor and Nuclear Fuel Development Corporation) has three programs in radiation safety field. They are STA program, JICA program and IAEA/RCA program. It is necessary to continue international cooperative activities to establish safety culture for development and utilization of nuclear energy in Asian countries

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

Science.gov (United States)

Corkern, Walter H.; Munchausen, Linda L.

1983-01-01

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

Dark Skies Awareness Programs for the International Year of Astronomy: Involvement, Outcomes and Sustainability

Science.gov (United States)

Walker, Constance E.

2010-01-01

The preservation of dark skies is a growing global concern, yet it is one of the easiest environmental problems people can address on local levels. For this reason, the goal of the IYA Dark Skies Awareness Cornerstone Project is to raise public awareness of the impact of artificial lighting on local environments by getting people worldwide involved in a variety of programs. These programs provide resources on light pollution for new technologies like a presence in Second Life and podcasts, for local thematic events at national parks and observatory open houses, for international thematic events like International Dark Skies Week and Earth Hour, for a program in the arts like an international photo contest, for global citizen-science programs that measure night sky brightness worldwide, and for educational materials like a kit with a light shielding demonstration. These programs have been successfully used around the world during IYA to raise awareness of the effects of light pollution on public health, economic issues, ecological consequences, energy conservation, safety and security, and astronomy. The presentation will provide an update, take a look ahead at the project's sustainability, and describe how people can be involved in the future. Information about the programs is at www.darkskiesawareness.org.

HTGR safety research program

International Nuclear Information System (INIS)

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

1981-01-01

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

Analysis of School Food Safety Programs Based on HACCP Principles

Science.gov (United States)

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

2014-01-01

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

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

International Nuclear Information System (INIS)

2011-01-01

, including: The Korean government, through the activities of MEST and KINS, has implemented a technically capable and effective nuclear safety regulatory program. KINS is an entrusted governmental corporation that functions as a nuclear safety regulation body. The team's findings note of the fact that the current Korean nuclear regulator is a combination of MEST and KINS; Transition to a new regulatory framework has the potential to enhance regulatory independence, expertise and transparency; however implementation details have yet to be finalized. Therefore, the team could not make a conclusion regarding the planned framework's effectiveness; and Korea's response to the accident at Fukushima has been prompt and effective. Communications with the public, development of actions for improvement and coordination with international stakeholders were of high quality. Among the good practices identified by the IRRS Review Team are the following: The regulatory body of Korea has a clear and structured national approach for nuclear safety; Korea strongly supports the global nuclear safety regime and provides training at national and international levels; KINS has a high level of technical competence and has implemented an effective human capital program; KINS performs detailed and comprehensive safety assessment using a broad range of deterministic and probabilistic codes and methods; and KINS has a comprehensive integrated computerized information and data management system. The IRRS Review Team identified certain issues warranting attention or in need of improvement and believes that consideration of these would enhance the overall performance of the future regulatory system. Transition to the new regulatory framework will require development of key implementation details that will impact the effectiveness of the new regulatory framework for safety; Enhancements to the management system in the areas of resource management, description of the internal safety culture, and

NPP safety and personnel training. XII International conference. Abstracts

International Nuclear Information System (INIS)

2011-01-01

The 12th International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7, 2011. The issues of nuclear technologies safety are considered.The problems of life-cycle management of nuclear facilities are discussed. The criteria of assessment of physical protection systems of nuclear facilities are presented [ru

Development of a safety communication and recognition program for construction.

Science.gov (United States)

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

2015-05-01

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

Fusion Safety Program. Annual report, FY 1982

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1983-07-01

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

Russian Minatom nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

Royen, J.

1999-01-01

An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

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...

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

OpenAIRE

Adjekum, Daniel Kwasi

2014-01-01

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

Effective radiological safety program for electron linear accelerators

International Nuclear Information System (INIS)

Swanson, W.P.

1980-10-01

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

41 CFR 128-1.8006 - Seismic Safety Program requirements.

Science.gov (United States)

2010-07-01

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

An integrated approach for improving occupational health and safety management: the voluntary protection program in Taiwan.

Science.gov (United States)

Su, Teh-Sheng; Tsai, Way-Yi; Yu, Yi-Chun

2005-05-01

A voluntary compliance program for occupational health and safety management, Voluntary Protection Programs (VPP), was implemented with a strategy of cooperation and encouragement in Taiwan. Due to limitations on increasing the human forces of inspection, a regulatory-based guideline addressing the essence of Occupational Health and Safety Management Systems (OHSMS) was promulgated, which combined the resources of third parties and insurance providers to accredit a self-improving worksite with the benefits of waived general inspection and a merit contributing to insurance premium payment reduction. A designated institute accepts enterprise's applications, performs document review and organizes the onsite inspection. A final review committee of Council of Labor Affairs (CLA) confers a two-year certificate on an approved site. After ten years, the efforts have shown a dramatic reduction of occupational injuries and illness in the total number of 724 worksites granted certification. VPP worksites, in comparison with all industries, had 49% lower frequency rate in the past three years. The severity rate reduction was 80% in the same period. The characteristics of Taiwan VPP program and international occupational safety and health management programs are provided. A Plan-Do-Check-Act management cycle was employed for pursuing continual improvements to the culture fostered. The use of a quantitative measurement for assessing the performance of enterprises' occupational safety and health management showed the efficiency of the rating. The results demonstrate that an employer voluntary protection program is a promising strategy for a developing country.

European and International Standards on health and safety in welding

International Nuclear Information System (INIS)

Howe, A

2009-01-01

A number of European and International Standards on health and safety in welding have been published in recent years and work on several more is nearing completion. These standards have been prepared jointly by the International Standards Organization (ISO) and the European Committee for Standardization (CEN). The standards development work has mostly been led by CEN/TC 121/SC 9, with excellent technical input from experts within Europe; but work on the revision of published standards, which has recently gathered pace, is now being carried out by ISO/TC 44/SC 9, with greater international involvement. This paper gives an overview of the various standards that have been published, are being revised or are under development in this field of health and safety in welding, seeking to (i) increase international awareness of published standards, (ii) encourage wider participation in health and safety in welding standards work and (iii) obtain feedback and solicit comments on standards that are currently under development or revision. Such an initiative is particularly timely because work is currently in progress on the revision of one of the more important standards in this field, namely EN ISO 10882:2001 Health and safety in welding and allied processes- Sampling of airborne particles and gases in the operator's breathing zone - Part 1: Sampling of airborne particles.

The role of the International Atomic Energy Agency in radiation and waste safety

International Nuclear Information System (INIS)

Wrixon, A.D.; Ortiz-Lopez, P.

1999-01-01

The International Atomic Energy Agency is specifically required by its Statute 'to establish or adopt ... standards of safety for protection of health and minimization of danger to life and property ... and to provide for the application of these standards ...'. Standards encompass three main elements: legally binding international undertakings among States; globally agreed international safety standards; and the provision for facilitating the application of those standards. Radiation safety standards are national responsibilities, but there is considerable value in formulating harmonized approaches throughout the world. The Agency has attempted to do this by establishing internationally agreed safety standards and by prompting their application. Of prime importance are the Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. These deal with the basic requirements that must be met in order to ensure an adequate standard of safety. More detailed guidance on the application of these requirements is given in Safety Guides established under them. Fuller technical support is given in a series of Safety Reports. A number of Safety Guides are relevant to this meeting. An existing Safety Guide on exemption is being revised to cover related topics such as exclusion and clearance, and this is the subject of a separate presentation. As part of the programme to combat illicit trafficking in radioactive materials, a new Safety Guide on the topic is being developed. Both are near completion. Another Safety Guide is being produced to elaborate the requirements in the Basic Safety Standards on the safety of radioactive sources. The topics of illicit trafficking in radioactive materials and the safety of radioactive sources were given added impetus by resolutions of the last General Conference of the Agency. This paper provides an overview of these activities of the Agency. (author)

International antiterrorist conventions concerning the safety of air transport

Directory of Open Access Journals (Sweden)

Jacek BARCIK

2008-01-01

Full Text Available In this article the international law regulations are presented concerning the civilian safety of the air transport. The history concerning air terrorism and international antiterrorist conventions was described in detail, involving The Chicago Convention, The Tokyo Convention, The Hague Convention and Montreal Convention.

Management of national nuclear power programs for assured safety. Report of visit by international participants to INEL on August 24, 1985

International Nuclear Information System (INIS)

Rouhani, S.Z.

1985-10-01

Through a special arrangement with the US State Department and support from the Department of Energy a group of high ranking officials from six different countries visited the Idaho National Engineering Laboratory on August 24, 1985. They were briefed on the highlights of the US-NRC's nuclear safety research programs at the INEL. The purpose of this project was to broadcast the advancements of the US nuclear safety technology to other nations that are at the start of major programs for peaceful use of nuclear energy in their countries

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

International Nuclear Information System (INIS)

1999-01-01

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

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

Science.gov (United States)

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

2018-04-01

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

MORT: a safety management program developed for ERDA

International Nuclear Information System (INIS)

1977-03-01

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

Nuclear Criticality Safety Organization qualification program. Revision 4

International Nuclear Information System (INIS)

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

1997-01-01

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

Nuclear criticality safety specialist training and qualification programs

International Nuclear Information System (INIS)

Hopper, C.M.

1993-01-01

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

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

Science.gov (United States)

Duarte, Alberto

2007-01-01

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

The International Criticality Safety Benchmark Evaluation Project

International Nuclear Information System (INIS)

Briggs, B. J.; Dean, V. F.; Pesic, M. P.

2001-01-01

In order to properly manage the risk of a nuclear criticality accident, it is important to establish the conditions for which such an accident becomes possible for any activity involving fissile material. Only when this information is known is it possible to establish the likelihood of actually achieving such conditions. It is therefore important that criticality safety analysts have confidence in the accuracy of their calculations. Confidence in analytical results can only be gained through comparison of those results with experimental data. The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the US Department of Energy. The project was managed through the Idaho National Engineering and Environmental Laboratory (INEEL), but involved nationally known criticality safety experts from Los Alamos National Laboratory, Lawrence Livermore National Laboratory, Savannah River Technology Center, Oak Ridge National Laboratory and the Y-12 Plant, Hanford, Argonne National Laboratory, and the Rocky Flats Plant. An International Criticality Safety Data Exchange component was added to the project during 1994 and the project became what is currently known as the International Criticality Safety Benchmark Evaluation Project (ICSBEP). Representatives from the United Kingdom, France, Japan, the Russian Federation, Hungary, Kazakhstan, Korea, Slovenia, Yugoslavia, Spain, and Israel are now participating on the project In December of 1994, the ICSBEP became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency's (OECD-NEA) Nuclear Science Committee. The United States currently remains the lead country, providing most of the administrative support. The purpose of the ICSBEP is to: (1) identify and evaluate a comprehensive set of critical benchmark data; (2) verify the data, to the extent possible, by reviewing original and subsequently revised documentation, and by talking with the

Program nuclear safety research: report 2000

International Nuclear Information System (INIS)

Muehl, B.

2001-09-01

The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2001. (orig.)

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

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

Science.gov (United States)

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

2013-06-01

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

Safety and economic impacts of photo radar program.

Science.gov (United States)

Chen, Greg

2005-12-01

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

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

Developing an integrated dam safety program

International Nuclear Information System (INIS)

Nielsen, N. M.; Lampa, J.

1996-01-01

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

Management of National Nuclear Power Programs for assured safety

Energy Technology Data Exchange (ETDEWEB)

Connolly, T.J. (ed.)

1985-01-01

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

Management of National Nuclear Power Programs for assured safety

International Nuclear Information System (INIS)

Connolly, T.J.

1985-01-01

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA)

Research program on nuclear technology and nuclear safety; Forschungsprogramm Kerntechnik und Nukleare Sicherheit - Synthesebericht 2009 des BFE-Programmleiters

Energy Technology Data Exchange (ETDEWEB)

Dreier, J.

2010-04-15

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

National Transportation Safety Board : weak internal control impaired financial accountability

Science.gov (United States)

2001-09-28

The U. S. General Accounting Office (GAO) was asked to review the National Transportation Safety Board's (NTSB) internal controls over selected types of fiscal year expenditures. They were asked to determine whether internal control weaknesses were a...

The Nordic safety program on accident consequence assessment

International Nuclear Information System (INIS)

Tveten, U.

1988-01-01

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

Systems Analysis of NASA Aviation Safety Program: Final Report

Science.gov (United States)

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

2013-01-01

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

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

International Nuclear Information System (INIS)

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

1997-05-01

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

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

Science.gov (United States)

2010-07-01

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

Fusion Safety Program annual report: Fiscal year 1987

International Nuclear Information System (INIS)

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

1988-02-01

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

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

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

International Nuclear Information System (INIS)

Wang, O.S.

1994-12-01

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

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

Science.gov (United States)

2010-07-01

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

The program of international intercomparison of accident dosimetry

International Nuclear Information System (INIS)

2002-06-01

The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a 60 Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

Experience with nuclear safety standards development in non-governmental international organizations

International Nuclear Information System (INIS)

Becker, K.

1985-01-01

Besides the IAEA as a 'governmental' organization dealing with basic safety recommendations addressed primarily to the national regulatory bodies in developing countries, two closely related non-governmental international standards organizations have gained extensive experience in the field of nuclear standardization. Over more than 25 years since their formation, both (a) the International Organization for Standardization's (ISO) Technical Committee 85 'Nuclear Energy', in particular in its Sub-Committee 3 'Reactor Technology and Safety' and (b) the International Electrotechnical Commission's (IEC) Technical Committee 45 'Nuclear Instrumentation' have published numerous standards. A brief review is given of these, draft standards, and other documents planned to become international standards. Many of them deal with rather specialized topics typical for 'industrial' standards such as standardized procedures, instruments, methods, materials, test methods, terminology, and signs and symbols, but others are directly related to more basic safety issues. In some areas such as quality assurance, seismic aspects of siting and terminology, there has been in the past occasional overlap in the activities of the NUSS programme, IEC and ISO. Letters of Understanding have since 1981 contributed to clarifying the borderlines and to avoiding redundant efforts. Also, some experiences and problems are described arising, for example, from the harmonization of different national safety philosophies and traditions into universally accepted international standards, and the transfer of international standards into national standards systems. Finally, based on a recent comprehensive compilation of some 3300 nuclear standards and standards projects, an attempt is made to present a cost/benefit analysis and an outlook on future developments. (author)

A program approach for site safety at oil spills

International Nuclear Information System (INIS)

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

1993-01-01

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

International movement on radiation safety related to the ICRP and the IAEA-RADWASS

International Nuclear Information System (INIS)

Kosako, Toshiso

1994-01-01

Nowadays discussion on Radiation Safety has a spread of world wide range. The main framework on radiation safety was constructed by ICRP (International Commission on Radiological Protection), which was established in 1928. This term of the committee was from June 1993 to May 1997 and the first plenary meeting was held at the Queen's hotel in Bournemouth of the United Kingdom on September 1993. The outline of this meeting, especially related items to the Committee 4, were summarized in this paper. The second point of our workshop considerations is radioactive waste problems, which are now under discussion in RADWASS (Radioactive Waste Safety Standards) project of IAEA (International Atomic Energy Agency). This IAEA-RADWASS will last nearly 10 years to cover whole subjects. These discussed items are arranged into various international standards; the safety fundamental, the safety standards, the safety guides and the safety practices. These systematic approach, if we could summarize, would be effective not only to the specialists but also to a general public to get an acceptance of radioactive waste problem. Here, this IAEA-RADWASS project is reviewed. (author)

International Cooperation of the Republic of Croatia in the Field of Radiological and Nuclear Safety

International Nuclear Information System (INIS)

Novosel, N.

2011-01-01

International cooperation of the Republic of Croatia in the field of radiological and nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Radiological and Nuclear Safety is responsible. According to the Radiological and Nuclear Safety Act (OG 28/10) the State Office for Radiological and Nuclear Safety: ''coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia''; ''fulfils the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning protection against ionising radiation, nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons'' and ''cooperates with international and domestic organisations and associations in the area of protection against ionising radiation and nuclear safety, and appoints its own expert representatives to take part in the work of such organisations and associations or to monitor their work''. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of radiological and nuclear safety, are presented. Also, cooperation with other international organizations and associations in the area of radiological and nuclear safety, such as Nuclear Suppliers Group, the Zangger Committee, the Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, is described. (author)

Researches in nuclear safety

International Nuclear Information System (INIS)

Souchet, Y.

2009-01-01

This article comprises three parts: 1 - some general considerations aiming at explaining the main motivations of safety researches, and at briefly presenting the important role of some organisations in the international conciliation, and the most common approach used in safety researches (analytical experiments, calculation codes, global experiments); 2 - an overview of some of the main safety problems that are the object of worldwide research programs (natural disasters, industrial disasters, criticality, human and organisational factors, fuel behaviour in accidental situation, serious accidents: core meltdown, corium spreading, failure of the confinement building, radioactive releases). Considering the huge number of research topics, this part cannot be exhaustive and many topics are not approached; 3 - the presentation of two research programs addressing very different problems: the evaluation of accidental releases in the case of a serious accident (behaviour of iodine and B 4 C, air infiltration, fission products release) and the propagation of a fire in a facility (PRISME program). These two programs belong to an international framework involving several partners from countries involved in nuclear energy usage. (J.S.)

Integrated program of using of Probabilistic Safety Analysis in Spain

International Nuclear Information System (INIS)

1998-01-01

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

Construction safety program for the National Ignition Facility

International Nuclear Information System (INIS)

Cerruti, S.J.

1997-01-01

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

Construction safety program for the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Cerruti, S.J.

1997-01-01

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

Commercial Crew Program and the Safety Technical Review Board

Science.gov (United States)

Mullen, Macy

2016-01-01

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

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

International Nuclear Information System (INIS)

2016-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-05-01

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

Relationship between internal medicine program board examination pass rates, accreditation standards, and program size.

Science.gov (United States)

Falcone, John L; Gonzalo, Jed D

2014-01-19

To determine Internal Medicine residency program compliance with the Accreditation Council for Graduate Medical Education 80% pass-rate standard and the correlation between residency program size and performance on the American Board of Internal Medicine Certifying Examination. Using a cross-sectional study design from 2010-2012 American Board of Internal Medicine Certifying Examination data of all Internal Medicine residency pro-grams, comparisons were made between program pass rates to the Accreditation Council for Graduate Medical Education pass-rate standard. To assess the correlation between program size and performance, a Spearman's rho was calculated. To evaluate program size and its relationship to the pass-rate standard, receiver operative characteristic curves were calculated. Of 372 Internal Medicine residency programs, 276 programs (74%) achieved a pass rate of =80%, surpassing the Accreditation Council for Graduate Medical Education minimum standard. A weak correlation was found between residency program size and pass rate for the three-year period (p=0.19, pInternal Medicine residency programs complied with Accreditation Council for Graduate Medical Education pass-rate standards, a quarter of the programs failed to meet this requirement. Program size is positively but weakly associated with American Board of Internal Medicine Certifying Examination performance, suggesting other unidentified variables significantly contribute to program performance.

THE PROGRAM SUPPORT SOCIAL AND PSYCHOLOGICAL SAFETY OF CHILDREN WITH INTELLECTUAL DISABILITIES

Directory of Open Access Journals (Sweden)

Pavel Aleksandrovich Kislyakov

2018-04-01

Full Text Available The article presents a description of the author’s program to support the social and psychological safety of children with intellectual disabilities enrolled in boarding school of VIII kind. The object of the study were children with intellectual disabilities. The subject of research – features of formation to children with intellectual disabilities the social and psychological safety. The methodological base are the special psychology (L.S. Vygotsky, S.L. Rubinstein, A. Speck. The results. Complex psychological and pedagogical support of social and psychological safety of children with intellectual disabilities reflects the content of psychological and pedagogical tasks (target function and technologies of their solution (instrumental function aimed at reducing internal and external risk factors. The target functions are: social and psychological adaptation, personal and developmental, the function of social support and psychological and pedagogical assistance, preventive and correctional function. Psycho-pedagogical objectives are the formation of skills of safe behavior and confront the dangers through the development of appropriate social skills, mental, physical and cognitive abilities, establishing a real and more comfortable with social contact (including municipal and educational environment, thereby ensuring individual protection and psychosocial well-being, support emotional balance, development of harmonious personality, to facilitate adaptation to the social environment, correction of risk factors of dysontogenesis. The program includes informative, technological and diagnostic modules. The basis for the construction of educational information in the field of security us based on the principle of integratively – interdisciplinary cooperation of academic subjects; a mix of mandatory core classes and extra-curricular and remedial work. Technological support included the following teaching methods: interactive (psychotechnical

Dark Skies Awareness Programs for the U.S. International Year of Astronomy

Science.gov (United States)

Walker, Constance E.; U. S. IYA Dark Skies Working Group

2009-01-01

The loss of a dark night sky as a natural resource is a growing concern. It impacts not only astronomical research, but also our ecology, health, safety, economics and energy conservation. For this reason, "Dark Skies are a Universal Resource” is one of seven primary themes of the U.S. International Year of Astronomy program in 2009. Its goal is to raise public awareness of the impact of artificial lighting on local environments by getting people involved in a variety of dark skies-related programs. To reach this goal, activities have been developed that: 1) Teach about dark skies using new technology (e.g., an activity-based planetarium show on DVD, podcasting, social networking, Second Life) 2) Provide thematic events on light pollution at star parties and observatory open houses (Dark Skies Discovery Sites, Astronomy Nights in the (National) Parks, Sidewalk Astronomy Nights) 3) Organize an event in the arts (e.g., a photography contest) 4) Involve citizen-scientists in unaided-eye and digital-meter star counting programs, as well as RFI monitoring (e.g., GLOBE at Night and Quiet Skies) and 5) Raise awareness about the link between light pollution and public health, economic issues, ecological consequences, energy conservation, safety and security (e.g., the Dark Skies Toolkit, Good Neighbor Lighting, Earth Hour, National Dark Skies Week, traveling exhibits and a 6-minute video tutorial). To deliver these programs, strategic networks have been established with astronomy clubs (ASP's Night Sky Network's astronomy clubs and the Astronomical League), science and nature centers (Astronomy from the Ground Up and the Association of Science and Technology), educational programs (Project ASTRO and GLOBE) and the International Dark-sky Association. The poster will describe the "know-how” and the means for people to become community advocates in promoting Dark Skies programs as public events at their home institutions. For more information, visit http://astronomy2009

Fast reactor test facilities in the US safety program

International Nuclear Information System (INIS)

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

1979-01-01

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

Implementation of probabilistic safety concepts in international codes

International Nuclear Information System (INIS)

Borges, J.F.

1977-01-01

Recent progress in the implementation of safety concepts in international structure codes is briefly presented. Special attention is paid to the work of the Joint-Committee on Structural Safety. The discussion is centered on some problems such as: safety differentiation, definition and combination of actions, spaces for checking safety and non-linear structural behaviour. When discussing safety differentiation it should be considered that the total probability of failure derives from a theoretical probability of failure and a probability of failure due to error and gross negligence. Optimization of design criteria should take into account both causes of failure. The quantification of reliability implies a probabilistic idealization of all basic variables. Steps taken to obtain an improved definition of different types of actions and rules for their combination are described. Safety checking can be carried out in terms of basic variables, action-effects, or any other suitable variable. However, the advantages and disadvantages of the different types of formulation should be discussed, particularly in the case of non-linear structural behaviour. (orig.) [de

Safety in an international work environment: CERN

CERN Document Server

Potter, K.

1990-01-01

The European Laboratory for Particle Physics (CERN) has recently completed a new accelerator. The installation of this accelerator and its experimental areas represents an example of harmonization of safety rules in supranational areas, as CERN is an international organization and the machine is housed in a tunnel of 26.7 km circumference, of which 20 km is on French territory and 6.7 km on Swiss territory. The work was carried out by a large number of firms from all over Europe, CERN staff and physicists and technicians from all over the world, and represented almost 4 million working hours. The safety organization chosen and applied with the agreement of the two host-State safety authorities is described and the resulting application, including the results in terms of accident statistics, from the installation of the machine, experimental areas and detectors are presented.

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

International Nuclear Information System (INIS)

Linsley, G.

1999-01-01

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

A fresh start of nuclear safety regulation and international perspective

International Nuclear Information System (INIS)

Oshima, Kenzo

2013-01-01

It should be explained more to the outside modestly the Fukushima nuclear accident would be a man-made complex disaster, which might be reluctant to do but not be neglected. Utmost efforts to change inward-looking attitude and reform safety culture should be done so as to prevent superficial reflection of the Fukushima nuclear accident. Since all nuclear regulatory functions ('3S': safety, security, safeguards) were integrated in Nuclear Regulation Authority (NRA), NRA and secretariat of NRA became more responsible for international response, and strengthening of organization system and human resources development would be an urgent necessity. This article described present stage of NRA focusing on international dimension including personal views. Overseas strong concern over the Fukushima nuclear accident and international communications were reviewed. The Fukushima nuclear accident started from natural disaster and enlarged as a man-made complex disaster with many human factors (mainly inaction, wilful negligence) overlapping and safety culture flawed. Examples of overseas and Japanese action plan to learn and absorb lessons from the Fukushima accident were introduced. NRA's started activities on inviting IAEA's IRRS and OPPAS as soon as ready, strengthening nuclear security measures, safeguards to prevent nuclear proliferation, bilateral cooperation and international advisors were also presented. (T. Tanaka)

A reliability program approach to operational safety

International Nuclear Information System (INIS)

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

1985-01-01

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

International collaboration on CESR-TA program

International Nuclear Information System (INIS)

Flanagan, John; Suetsugu, Yusuke

2009-01-01

An international collaboration on the CESR-TA (Cornell Electron Storage Ring-Test Accelerator) program, which is a program to investigate electron cloud instability (ECI) issues in the positron damping ring of the ILC (International Linear-Collider), is currently underway a Cornell University, KEK is supporting the program through the development of an X-ray beam profile monitor system to measure the extremely small beam size, and through the development of clearing electrodes to mitigate the ECI. (author)

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

International Nuclear Information System (INIS)

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

2011-01-01

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

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

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.

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

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

Science.gov (United States)

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

2013-12-01

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

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

Science.gov (United States)

2010-07-01

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

Probabilistic studies for a safety assurance program

International Nuclear Information System (INIS)

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

1985-01-01

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

International Conference of Ukrainian Nuclear Society ''NPP's safety and protection''(annotations)

International Nuclear Information System (INIS)

Barbashev, S.V.

1997-01-01

The abstracts of reports submitted to the Conference include: - New developments of the safe nuclear installations; - NPP ecological safety; - Methods of personnel and population protection; - Waste management safety (at transportation, processing and storage); - Spent nuclear fuel management; - NPP life extension and decommissioning; - Public opinion as an element of NPP safety; - Training of personnel, scientific support and safety culture; - Forecasting of nuclear power and industry safe development; - Development of international cooperation in nuclear power

The Nuclear Energy Agency: Strengthening Nuclear Safety Technology and Regulation Through Effective International Cooperation

International Nuclear Information System (INIS)

Nieh, H.

2016-01-01

The NEA provides an effective forum for international co-operation on nuclear safety and regulatory issues in its specific task groups, working parties and expert groups, as well as through joint international safety research projects. In these activities, NEA member countries work together to share and analyse data and experiences, gain consensus and develop approaches that can be applied within each country’s governmental processes. Through effective international co-operation, NEA member countries have worked together to develop actions for improving their regulatory frameworks and nuclear installation safety. As a result of these efforts, safety improvements and further harmonisation have been realized in the areas operating reactors, new reactors, human and organisational factors and nuclear safety research. At the NEA, technical and programmatic work under the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI), joint safety research projects and the Multinational Design Evaluation Programme (MDEP) have helped NEA member countries to ensure a high standard for nuclear safety and to further develop the technical knowledge base. (author)

Overview of the Nuclear Regulatory Commission's safety research program

International Nuclear Information System (INIS)

Beckjord, E.S.

1989-01-01

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

Nuclear Safety Research Reactor (NSRR) program in JAERI

Energy Technology Data Exchange (ETDEWEB)

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

1974-07-01

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

Nuclear Safety Research Reactor (NSRR) program in JAERI

International Nuclear Information System (INIS)

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

1974-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1982-01-01

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

CERN safety expert receives international award

CERN Multimedia

2005-01-01

On 18 December 2004, the President of the Swiss Electro-technical Committee, Martin Reichle (left), presented the award to Helmut Schönbacher. Helmut Schönbacher, of the Safety Commission at CERN, has received, the "1906 Award" of the International Electrotechnical Commission (IEC) for his standardisation work on the influence of ionizing radiation on insulating materials. From 1986 until 2004, Schönbacher was leader of a working group on radiation composed of internationally recognised experts. It edited standards of the IEC 60544 series on the determination of the effects of ionizing radiation on electrical insulating materials. The working group also edited three IEC Technical Reports on the determination of long-term radiation ageing in polymers. This standardisation work and long-term experience from CERN on the radiation ageing of materials also contributed to research coordination programmes of the International Atomic Energy Agency (IAEA). From 1968 until 1988, Schönbacher was a member of the Rad...

Analysis of international approaches which are used at development of theoperational safety performance indicators

International Nuclear Information System (INIS)

Lyigots'kij, O.Yi.; Nosovs'kij, A.V.; Chemeris, Yi.O.

2009-01-01

Description of international approaches and experience of the use of theoperational safety performance indicators system is provided for estimationof current status and making a decision on corrections in the operationpractice. The state of development of the operational safety performanceindicators system by the operating organization is overviewed. Thepossibility of application of international approaches during development ofthe integral safety performance indicators system is analyzed. Aims and tasksof future researches are formulated in relation to development of theintegral safety performance indicators system.

10 CFR 1.29 - Office of International Programs.

Science.gov (United States)

2010-01-01

... maintains working relationships with individual countries and international nuclear organizations, as well... 10 Energy 1 2010-01-01 2010-01-01 false Office of International Programs. 1.29 Section 1.29 Energy... Staff § 1.29 Office of International Programs. The Office of International Programs— (a) Advises the...

Developing international safety standards for the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Metcalf, P.

2001-01-01

In the context of the International Atomic Energy Agency's (IAEA) programme to create a corpus of internationally accepted Radioactive Waste Safety Standards (RADWASS), focus is currently being placed on establishing standards for the 'geological disposal of radioactive waste'. This is a challenging task and to help the standards development process there is a need to stimulate discussion of some of the associated scientific and technical issues. A number of position papers developed in recent years by a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, address many of the relevant issues. These include a common safety based framework for radioactive waste disposal, appropriate time frames for safety assessment, different possible indicators of long-term safety, the safety implications of reversibility and retrievability, the assessment of possible human intrusion into the repository, the role and limitations of institutional control, establishing reference critical groups and biospheres for long-term assessment, and what is meant by 'compliance' with the standards. These papers will be discussed at a Specialists Meeting to be held at the IAEA in June 2001 as a means of establishing the extent to which they enjoy the general support of experts. In order to broaden that consensus, the conclusions reached at the Specialists Meeting on the issues listed above will be presented and discussed with participants at a number of international meetings. Later this year, a draft safety standard on the geological disposal of radioactive waste which takes account of the consensus positions reached through the various consultations will be submitted for the consideration of Waste Safety Standards Committee (WASSC), the officially approved body within the IAEA for the review and approval of waste safety standards. The Committee is made up of government appointed radioactive waste regulators

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

Energy Technology Data Exchange (ETDEWEB)

1981-03-01

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

The official website of the U.S. department of energy's nuclear criticality safety program

Energy Technology Data Exchange (ETDEWEB)

Koponen, B.; Heinrichs, D.; Lee, C. [Lawrence Livermore National Laboratory, CA (United States); Scott, L. [SAIC, Solana Beach, CA (United States)

2014-07-01

The U.S. Department of Energy (DOE) Nuclear Criticality Safety Program (NCSP) mission is to provide sustainable expert leadership, direction, and the technical infrastructure necessary to develop, maintain, and disseminate the essential technical tools, training, and data to support safe, efficient fissionable material operations within the DOE. The NCSP Website site makes a variety of information available to the criticality safety practitioner, including reference materials, training modules and links to related sites. It assists criticality safety personnel to keep abreast of NCSP activities or current developments in criticality safety via a 'What's New' section within the Website. Convenient access to the many useful features of the Website is available via drop-down menus. The Website is also available to non-DOE and international professionals tasked with ensuring safe operations involving fissionable nuclear materials. (author)

International conference on safety culture in nuclear installations. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The industry literature provides a great deal of insight at the artefact and espoused value levels, although as yet it remains somewhat disorganized. There is, however, an overall lack of understanding of the assumption level of safety culture. The IAEA has organised the conference on safety culture for better understanding of the safety culture issues on the international level.

International conference on safety culture in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2002-01-01

Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The industry literature provides a great deal of insight at the artefact and espoused value levels, although as yet it remains somewhat disorganized. There is, however, an overall lack of understanding of the assumption level of safety culture. The IAEA has organised the conference on safety culture for better understanding of the safety culture issues on the international level

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

International Nuclear Information System (INIS)

Rappe, G.M.

1984-10-01

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

[Karachi Nuclear Power Plant (KANUPP), Safety Management

Energy Technology Data Exchange (ETDEWEB)

Hasan, S M [Karachi Nuclear Power Plant (KANUPP), Karachi (Pakistan)

1997-12-01

The present regime for CANDU safety management in Pakistan has evolved in line with contemporary international practice, and is essential adequate to ensure the continued safety of KANUPP and other future CANDU reactors, as confirmed by international reviews as well. But the small size of Pakistan nuclear power program poses limitations in developing - expert judgment in analysis of in-service inspection data; and own methodology for CANDU safety analysis.

[Karachi Nuclear Power Plant (KANUPP), Safety Management

International Nuclear Information System (INIS)

Hasan, S.M.

1997-01-01

The present regime for CANDU safety management in Pakistan has evolved in line with contemporary international practice, and is essential adequate to ensure the continued safety of KANUPP and other future CANDU reactors, as confirmed by international reviews as well. But the small size of Pakistan nuclear power program poses limitations in developing - expert judgment in analysis of in-service inspection data; and own methodology for CANDU safety analysis

Internal Arc: People safety in the electrical wiring

International Nuclear Information System (INIS)

Inchausti, J. M.

2009-01-01

The aim of this article is to describe the internal arc phenomenon, an extremely fast, almost explosive and unattended process of transformation form an initial electric power to the generation of a pressure and heat wave inside the medium its produced its consequences for safety, current methods of limiting them and current regulations in general for equipment used in medium-voltage electrical distribution networks. Taking into account that this type of equipment is found thought the distribution network in both public buildings and unrestricted access areas, safety (of operators and the general public) must be taken into account in the design of equipment and installations to minimize the risk of internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which the manufacturer has to takes steps to minimize the risks of an internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which an internal arc occurring, it is understood to be vitally important that users, installers and designers of Medium Voltage installations are familiar with the installation conditions stated by the manufacturer and thus avoid risks. (Author) 14 refs

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

International Nuclear Information System (INIS)

1975-06-01

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

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

Science.gov (United States)

Sparer, Emily; Dennerlein, Jack

2013-01-01

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

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 ...

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

International Nuclear Information System (INIS)

2015-01-01

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

78 FR 66987 - Railroad Safety Technology Program Grant Program

Science.gov (United States)

2013-11-07

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

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

International Nuclear Information System (INIS)

1978-07-01

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

Development of nuclear safety issues program

Energy Technology Data Exchange (ETDEWEB)

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

2006-12-15

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

Development of nuclear safety issues program

International Nuclear Information System (INIS)

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

2006-12-01

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

Information requirements of the National Aeronautics and Space Administration's safety, environmental health, and occupational medicine programs

Science.gov (United States)

Whyte, A. A.

1978-01-01

A survey of the internal and external reporting and recordkeeping procedures of these programs was conducted and the major problems associated with them are outlined. The impact of probable future requirements on existing information systems is evaluated. This report also presents the benefits of combining the safety and health information systems into one computerized system and recommendations for the development and scope of that system.

The role of international atomic energy agency in maintaining nuclear safety competence

International Nuclear Information System (INIS)

Aro, I.; Mazour, T.

2000-01-01

This paper provides information how International Atomic Energy Agency can assist Member States in maintaining and developing nuclear safety competence. The topics covered include the development of safety standards, organisation of nuclear safety related conferences, provision of safety reviews, organisation of training courses and topical workshops and publication of training related documents. Usefulness of these activities for competence development is discussed. (author)

Laser safety considerations for a mobile laser program

Science.gov (United States)

Flor, Mary

1997-05-01

An increased demand for advanced laser technology, especially in the area of cutaneous and cosmetic procedures has prompted physicians to use mobile laser services. Utilization of a mobile laser service allows physicians to provide the latest treatments for their patients while minimizing overhead costs. The high capital expense of laser systems is often beyond the financial means of individual clinicians, group practices, free-standing clinics and smaller community hospitals. Historically rapid technology turnover with laser technology places additional risk which is unacceptable to many institutions. In addition, health care reform is mandating consolidation of equipment within health care groups to keep costs at a minimum. In 1994, Abbott Northwestern Hospital organized an in-house mobile laser technology service which employs a group of experienced laser specialists to deliver and support laser treatments for hospital outreach and other regional physicians and health care facilities. Many of the hospital's internal safety standards and policies are applicable to the mobile environment. A significant challenge is client compliance because of the delicate balance of managing risk while avoiding being viewed as a regulator. The clinics and hospitals are assessed prior to service to assure minimum laser safety standards for both the patient and the staff. A major component in assessing new sites is to inform them of applicable regulatory standards and their obligations to assure optimum laser safety. In service training is provided and hospital and procedures are freely shared to assist the client in establishing a safe laser environment. Physician and nursing preceptor programs are also made available.

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

Science.gov (United States)

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

2008-04-01

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

Effect of generic issues program on improving safety

International Nuclear Information System (INIS)

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

2010-01-01

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

International safety standards and regulatory practices and their application to Brazilian nuclear power plants - a realistic view

International Nuclear Information System (INIS)

Almeida, Claudio; Camargo, Claudio

1999-01-01

An international nuclear safety regime is being established through a series of binding safety conventions, voluntarily adopted international safety standards and an accompanying peer review process. The basis for the evaluation of each country performance within this international regime should be the international practices. However, local conditions should be taken into account to avoid undue stress of the limited resources available to countries with a limited nuclear power programme. This work reviews the current international nuclear safety and discusses the application of some international practices to the Brazilian situation, considering the peculiarities of the national nuclear power programme and the limitations of the available financial and human resources. (author)

Use of electronic group method in assessing food safety training needs and delivery methods among international college students in the U.S.

Science.gov (United States)

Garden-Robinson, Julie; Eighmy, Myron A; Lyonga, Agnes Ngale

2010-12-01

The purpose of this study was to determine the types of unfamiliar foods international students in the U.S. encounter and to assess food safety information that international students would like to receive for mitigating risks associated with handling and preparing unfamiliar foods. The study identified preferred instructional delivery methods and media for receiving food safety training or information. An electronic group method was used for this study. The electronic group method was chosen to maximize group efficiency by allowing participants to share ideas simultaneously and anonymously with minimal use of time and resources.Types of different (unfamiliar) foods were grouped into major categories. Fast and ready-to-eat foods, and processed and frozen foods constituted a major change for some international students, who were accustomed to homemade and fresh foods in their countries. Participants were interested in receiving information about how to safely handle and prepare unfamiliar foods in their new environment. Preferred methods for receiving food safety information included written materials, online publications, presentations, and materials provided during student orientation. Food packages, websites, and television programs were other preferred methods of receiving food safety information. Copyright © 2010 Elsevier Ltd. All rights reserved.

Development and implementation of a hospital-based patient safety program

International Nuclear Information System (INIS)

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

2006-01-01

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

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

Science.gov (United States)

2010-10-01

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

Nuclear health and safety

International Nuclear Information System (INIS)

1991-08-01

This paper is a review of environmental and safety programs at facilities in the Naval Reactors Program which shows no basis for allegations that unsafe conditions exist there or that the environment is being harmed by activities conducted there. The prototype reactor design provides safety measures that are consistent with commercial nuclear power plants. Minor incidents affecting safety and the environment have occurred, however, and dents affecting safety and the environment have occurred, however, and as with other nuclear facilities, past activities have caused environmental problems that require ongoing monitoring and vigilance. While the program has historically been exempt from most oversight, some federal and state environmental oversight agencies have recently been permitted access to Naval Reactors facilities for oversight purposes. The program voluntarily cooperates with the Nuclear Regulatory Commission regarding reactor modifications, safety improvements, and component reliability. In addition, the program and its contractors have established an extensive internal oversight program that is geared toward reporting the slightest deviations from requirements or procedures. Given the program's classification policies and requirements, it does not appear that the program routinely overclassifies information to prevent its release to the public or to avoid embarrassment. However, GAO did not some instances in which documents were improperly classified

[Analysis of the current situation the oral medical interns' awareness on occupation safety behavior in college].

Science.gov (United States)

Hongyan, Song; Yu, Wang; Rongrong, He; Ying, Xu

2015-04-01

This study aims to determine the awareness oral medical interns about occupation safety protection of knowledge and to present a scientific basis for perfecting the occupation safety education system and standard protection behavior. A self-designed questionnaire that used a retrospective questionnaire survey on 425 stomatological interns, scoring, and statistical analysis of the survey were performed. The questionnaire included occupation safety prevention knowledge, behavior cognitive, and protective behavior, among others. The questionnaire recovery rate was 100%, and the average scores of the prevention knowledge and behavior cognitive were 4.55 ± 0.91 and 4.40 ± 1.05, respectively. More than 90% interns can conduct the conventional protection, and less than 40% can perform special protection. For the item "occupation safety protection knowledge", the scores of three grade III hospitals were higher than that of stomatological hospitals and second level of first-class hospitals; the difference was statistically significant (P safety protection knowledge, behavioral cognitive, and protection behavior. The average score was higher for than for boys in the three contents, and the average score of interns accepting pre-job training was higher than those rejected; the difference was statistically significant (P safety knowledge of oral medical interns is not sufficient, and the protective behavior is poor. Schools and hospitals should strengthen the intern occupation safety and protection education and improve the status of occupation safety behavior.

Conclusions and Recommendations of the IAEA International Conference on Topical Issues in Nuclear Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Main Conclusions and Recommendations of International Conference on Topical Issues in Nuclear Installation Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Application of patient safety indicators internationally: a pilot study among seven countries.

Science.gov (United States)

Drösler, Saskia E; Klazinga, Niek S; Romano, Patrick S; Tancredi, Daniel J; Gogorcena Aoiz, Maria A; Hewitt, Moira C; Scobie, Sarah; Soop, Michael; Wen, Eugene; Quan, Hude; Ghali, William A; Mattke, Soeren; Kelley, Edward

2009-08-01

To explore the potential for international comparison of patient safety as part of the Health Care Quality Indicators project of the Organization for Economic Co-operation and Development (OECD) by evaluating patient safety indicators originally published by the US Agency for Healthcare Research and Quality (AHRQ). A retrospective cross-sectional study. Acute care hospitals in the USA, UK, Sweden, Spain, Germany, Canada and Australia in 2004 and 2005/2006. Routine hospitalization-related administrative data from seven countries were analyzed. Using algorithms adapted to the diagnosis and procedure coding systems in place in each country, authorities in each of the participating countries reported summaries of the distribution of hospital-level and overall (national) rates for each AHRQ Patient Safety Indicator to the OECD project secretariat. Each country's vector of national indicator rates and the vector of American patient safety indicators rates published by AHRQ (and re-estimated as part of this study) were highly correlated (0.821-0.966). However, there was substantial systematic variation in rates across countries. This pilot study reveals that AHRQ Patient Safety Indicators can be applied to international hospital data. However, the analyses suggest that certain indicators (e.g. 'birth trauma', 'complications of anesthesia') may be too unreliable for international comparisons. Data quality varies across countries; undercoding may be a systematic problem in some countries. Efforts at international harmonization of hospital discharge data sets as well as improved accuracy of documentation should facilitate future comparative analyses of routine databases.

Requirements and international co-operation in nuclear safety for evolutionary light water reactors

International Nuclear Information System (INIS)

Carnino, A.

1999-01-01

The principles of safety are now well known and implemented world-wide, leading to a situation of harmonisation in accordance with the Convention on Nuclear Safety. Future reactors are expected not only to meet current requirements but to go beyond the safety level presently accepted. To this end, technical safety requirements, as defined by the IAEA document Safety Fundamentals, need be duly considered in the design, the risks to workers and population must be decreased, a stable, transparent and objective regulatory process, including an international harmonisation with respect to licensing of new reactors, must be developed, and the issue of public acceptance must be addressed. Well-performing existing installations are seen as a prerequisite for an improved public acceptability; there should be no major accidents, the results from safety performance indicators must be unquestionable, and compliance with internationally harmonised criteria is essential. Economical competitiveness is another factor that influences the acceptability; the costs for constructing the plant, for its operation and maintenance, for the fuel cycle, and for the final decommissioning are of paramount importance. Plant simplification, longer fuel cycles, life extension are appealing options, but safety will have first priority. The IAEA can play an important role in this field, by providing peer reviews by teams of international experts and assistance to Member States on the use of its safety standards. (author)

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

Science.gov (United States)

2014-11-01

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

Space reactor safety, 1985--1995 lessons learned

International Nuclear Information System (INIS)

Marshall, A.C.

1995-01-01

Space reactor safety activities and decisions have evolved over the last decade. Important safety decisions have been made in the SP-100, Space Exploration Initiative, NEPSTP, SNTP, and Bimodal Space Reactor programs. In addition, international guidance on space reactor safety has been instituted. Space reactor safety decisions and practices have developed in the areas of inadvertent criticality, reentry, radiological release, orbital operation, programmatic, and policy. In general, the lessons learned point out the importance of carefully reviewing previous safety practices for appropriateness to space nuclear programs in general and to the specific mission under consideration

Space reactor safety, 1985--1995 lessons learned

Energy Technology Data Exchange (ETDEWEB)

Marshall, A.C.

1995-12-31

Space reactor safety activities and decisions have evolved over the last decade. Important safety decisions have been made in the SP-100, Space Exploration Initiative, NEPSTP, SNTP, and Bimodal Space Reactor programs. In addition, international guidance on space reactor safety has been instituted. Space reactor safety decisions and practices have developed in the areas of inadvertent criticality, reentry, radiological release, orbital operation, programmatic, and policy. In general, the lessons learned point out the importance of carefully reviewing previous safety practices for appropriateness to space nuclear programs in general and to the specific mission under consideration.

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

International Nuclear Information System (INIS)

Clark, J.L.

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

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

Science.gov (United States)

2016-02-01

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

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

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

Science.gov (United States)

2015-06-01

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

Occupational Safety and Health Program at the West Valley Demonstration Project

International Nuclear Information System (INIS)

L. M. Calderon

1999-01-01

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

International service learning programs: ethical issues and recommendations.

Science.gov (United States)

Reisch, Rebecca A

2011-08-01

Inequities in global health are increasingly of interest to health care providers in developed countries. In response, many academic healthcare programs have begun to offer international service learning programs. Participants in these programs are motivated by ethical principles, but this type of work presents significant ethical challenges, and no formalized ethical guidelines for these activities exist. In this paper the ethical issues presented by international service learning programs are described and recommendations are made for how academic healthcare programs can carry out international service learning programs in a way that minimizes ethical conflicts and maximizes benefits for all stakeholders. Issues related to project sustainability and community involvement are emphasized. © 2011 Blackwell Publishing Ltd.

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

Science.gov (United States)

McLaughlin, Karen A; Glang, Ann

2010-05-01

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

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

Science.gov (United States)

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

2016-09-01

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

A Model Program for International Commerce Education.

Science.gov (United States)

Funston, Richard

To address the economy's growing reliance on international business, San Diego State University has recently introduced a program in international commerce. The program was developed by packaging coursework in three existing areas: business administration, language training, and area studies. Although still in its infancy, the international…

Safety upgrading of the PAKS Nuclear Plant

International Nuclear Information System (INIS)

Vamos, G.; Vigassy, J.

1993-01-01

In the last several years the net electricity from the Paks NPP represents almost half of the Hungarian total. The 4 units of Paks belong to the latest generation of the VVER-440 units, the small-sized Russian designed PWRs. Reviewing the main design features of them, the safety merits and safety concerns are summarized. Due to the conservative design and the extensive operating experience the safety merits appear to be more significant than generally believed. The VVER-440 type has two models, the 230 and 213, which have a large number of distinctive safety features. These are highlighted in the section comparisons. A quality assurance program was initiated in Paks very early. A long-term safety upgrading program was also initiated, originating from vendor recommendations, regulatory decisions, in-house operating experience and safety concerns, and independent reviews. The main areas and some examples of the measures are described. This program, like all other activities related to nuclear safety, has been under regulatory control. The specific features of the Hungarian regulatory system are described. For advanced, general and new evaluation of the safety of the units in Paks in accordance with the internationally recommended criteria of the 90's, the project AGNES has been launched with international participation. The scope of this project is summarized. International efforts as the IAEA Regional Project on safety assessment of VVER-440/213 and VVER-440/230 units are underway. Since safety is not only a question of design, but it can be significantly influenced by operations and maintenance practices, the Paks NPP has invited LAEA's OSART and ASSET missions, WANO's Pilot Peer Review

Proceedings of the international symposium on research reactor safety operations and modifications

International Nuclear Information System (INIS)

1990-03-01

The International Symposium on Research Reactor Safety, Operations and Modifications was organized by the International Atomic Energy Agency in cooperation with Atomic Energy of Canada Limited-Research Company. The main objectives of this Symposium were: (1) to exchange information and to discuss current perspectives and concerns relating to all aspects to research reactor safety, operations, and modifications; and, (2) to present views and to discuss future initiatives and directions for research reactor design, operations, utilization, and safety. The symposium topics included: research reactor programmes and experience; research reactor design safety and analysis; research reactor modifications and decommissioning; research reactor licensing; and new research reactors. These topics were covered during eight oral sessions and three poster sessions. These Proceedings include the full text of the 93 papers presented. The subject of Symposium was quite wide-ranging in that it covered essentially all aspects of research reactor safety, operations, and modifications. This was considered to be appropriate and timely given the 326 research reactors currently in operation in some 56 countries; given the degree of their utilization which ranges from pure and applied research to radioisotopes production to basic training and manpower development; and given that many of these reactors are undergoing extensive modifications, core conversions, power upratings, and are becoming the subject of safety reassessment and regulatory reviews. Although the Symposium covered many topics, the majority of papers and discussions tended to focus mainly on research reactor safety. This was seen as a clear sign of the continuing recognition of the fundamental importance of identifying and addressing, particularly through international cooperation, issues and concerns associated with research reactor safety

The Impact of a Patient Safety Program on Medical Error Reporting

Science.gov (United States)

2005-05-01

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

Development of plasma arc cutting technique for dismantlement of reactor internals in JPDR decommissioning program

International Nuclear Information System (INIS)

Yanagihara, Satoshi; Tanaka, Mitsugu; Ujihara, Norio.

1988-01-01

The decommissioning program for JPDR has been conducted by JAERI since 1981 under contact with the Science and Technology Agency of Japan. The development of cutting tools for dismantling the JPDR is one of the important items in the program. An underwater plasma arc cutting technique was selected for dismantling the JPDR core internals. The study was concentrated on improving the cutting ability in water. Various cutting tests were conducted changing the parameters such as arc current, supply gas and cutting speed to evaluate the most effective cutting condition. Through the study, it has been achieved to be able to cut a 130 mm thick stainless steel plate in water. In addition, the amount and the characteristics of by-products were measured during the cutting tests for the safety evaluation of the dismantling activities. Final cutting tests and checkout of whole plasma arc cutting system were conducted using a mockup water pool and test pieces simulating the JPDR core internals. It was proved from the tests that the cutting system developed in the program will be applicable for the JPDR core internals dismantlement. (author)

The IAEA International Seismic Safety Centre and IAEA safety standards for site evaluation and design of NPPs

International Nuclear Information System (INIS)

Godoy, A.; Sollogoub, P; )

2009-01-01

This presentation covers the following topics: 'Lessons learned' from the occurrence of strong natural events, (tsunamis, earthquakes, hurricanes, etc.) The International Seismic Safety Centre as a global focal point for the nuclear engineering community in those fields. A need for international cooperation, openness and transparency – Sharing of experience

International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report

International Nuclear Information System (INIS)

1999-06-01

The Objective of the Conference was to assess the past decade of nuclear safety efforts in countries operating WWER and RBMK nuclear reactors and to address remaining safety issues which require further work. A particular focus of the Conference was on international co-operation and assistance and where such efforts should be focused in the future. All Eastern European countries that operate RBMK or WWER reactors participated in the Conference, and presented papers on three key areas of nuclear safety: Regulatory Aspects of Nuclear Power Plant Safety; Status of Safety Improvements; and Status of Safety Analysis Reports. In addition, representatives from 18 additional countries that provide financial and/or technical assistance and co-operation in the area of WWER and RBMK safety offered the most extensive commentary. Key international (IAEA, World Association of Nuclear Operators, the Nuclear Energy Agency, the G-24 NUSAC, the European Commission, and the EBRD) organizations that provide nuclear safety assistance for WWER and RBMK reactors also made presentations. There is no question that considerable progress on nuclear safety has been made in Eastern Europe. Special mention should be made of successful efforts to strengthen the independence and technical competence of the nuclear regulatory authorities. Efforts should now concentrate on improving the depth and scope of the technical abilities of the regulatory authorities. More attention by governments is needed to ensure that the regulatory authorities have the financial resources and enforcement authority to fully execute their missions. In respect to the operators of the nuclear power plants, they have demonstrated clear progress in operational safety improvements. Significant additional efforts are required to maintain and enhance an effective safety culture. Design safety improvement programmes are in place in all countries. Implementation of these programmes has varied and is particularly affected by

Enlightenment on international cooperation for nuclear safety in China in light of Fukushima nuclear accident

International Nuclear Information System (INIS)

Fu Jie; Feng Yi; Luan Haiyan; Meng Yue; Zhang Ou

2013-01-01

This thesis elaborates on the impact of Fukushima nuclear accident on global nuclear power development and subsequent international activities carried out by major countries. It analyses significance of international cooperation in ensuring nuclear safety and promoting nuclear power development and makes some suggestions to further strengthen the international cooperation on nuclear safety in China. (authors)

New Possibilities for development of the internal health and safety organisation

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, Per Langå

2004-01-01

Research from several countries indicates that the internal health and safety organisation in most companies is placed in an appendix position. A possibility for developing a stronger and more effective health and safety organisation is to introduce learning. This approach has been applied...... in a Danish network project with eleven companies. The results indicate that health and safety managers and safety representatives have difficulties in fulfilling the role as change agents in mastering such a development project. Only three of the eleven companies turned out to be able to implement successful...

Keys to effective third-party process safety audits

International Nuclear Information System (INIS)

Birkmire, John C.; Lay, James R.; McMahon, Mona C.

2007-01-01

The Occupational Safety and Health Administration's (OSHA's) Process Safety Management (PSM) regulation was promulgated in 1992. The U.S. Environmental Protection Agency's (EPA's) corresponding Risk Management Program (RMP) rule followed in 1996. Both programs include requirements for triennial compliance audits. Effective compliance audits are critical in identifying program weaknesses and ensuring the safety of facility personnel and the surrounding public. Large companies with corporate and facility health, safety, and environmental groups typically have the resources and experience to conduct audits internally, either through a corporate audit team or the sharing of personnel between multiple facilities. Small to medium sized businesses frequently do not have the expertise or the resources to perform compliance audits, and rely on third-party consultants to provide these services. This paper will discuss the observations of the authors in performing audits and working with PSM/RMP programs across a number of market sectors (e.g. chemical, petrochemical, pharmaceutical, food and beverage, water treatment), including effective practices, hurdles to successful implementation and execution of programs, and typical program shortcomings. The paper will also discuss steps to improve the audit process and increase effectiveness whether performed by a third party or internally

Nuclear materials control and accountability internal audit program

International Nuclear Information System (INIS)

Barham, M.A.; Abbott, R.R.

1991-01-01

This paper reports that the Department of Energy Order (DOE) 5633.3, Control and Accountability for Nuclear Materials, includes several requirements for development and implementation of an internal audit program. Martin Marietta Energy System, Inc., manages five sites in Tennessee, Kentucky, and Ohio for the DOE Field Office, Oak Ridge and has a Central Nuclear Materials Control and Accountability (NMC and A) Manager with matrixed responsibility for the NMC and A program at the five sites. The Energy Systems Central NMC and A Manager has developed an NMC and A Internal Audit Handbook which defines the functional responsibilities, performance criteria, and reporting and documentation requirements for the Energy Systems NMC and A Internal Audit Program. The initial work to develop and implement these standards was tested at the K-25 Site when the site hired an internal auditor to meet the DOE requirements for an NMC and A Internal Audit program

The NordiNet® International Outcome Study and NovoNet® ANSWER Program®: rationale, design, and methodology of two international pharmacoepidemiological registry-based studies monitoring long-term clinical and safety outcomes of growth hormone therapy (Norditropin®).

Science.gov (United States)

Höybye, Charlotte; Sävendahl, Lars; Christesen, Henrik Thybo; Lee, Peter; Pedersen, Birgitte Tønnes; Schlumpf, Michael; Germak, John; Ross, Judith

2013-01-01

Randomized controlled trials have shown that growth hormone (GH) therapy has effects on growth, metabolism, and body composition. GH therapy is prescribed for children with growth failure and adults with GH deficiency. Carefully conducted observational study of GH treatment affords the opportunity to assess long-term treatment outcomes and the clinical factors and variables affecting those outcomes, in patients receiving GH therapy in routine clinical practice. The NordiNet® International Outcome Study (IOS) and the American Norditropin® Web Enabled Research (ANSWER Program®) are two complementary, non-interventional, observational studies that adhere to current guidelines for pharmacoepidemiological data. The studies include pediatric and adult patients receiving Norditropin®, as prescribed by their physicians. The studies gather long-term data on the safety and effectiveness of reallife treatment with the recombinant human GH, Norditropin®. We describe the origins, aims, objectives, and design methodology of the studies, as well as their governance and validity, strengths, and limitations. The NordiNet® IOS and ANSWER Program® studies will provide valid insights into the effectiveness and safety of GH treatment across a diverse and large patient population treated in accordance with real-world clinical practice and following the Good Pharmacoepidemiological Practice and STrengthening the Reporting of OBservational studies in Epidemiology (STROBE) guidelines.

Research program on nuclear technology and nuclear safety - Synthesis report 2008

International Nuclear Information System (INIS)

Dreier, J.

2009-06-01

This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2008 and the results obtained. Four main projects at the Paul Scherrer Institute's Laboratory for Reactor Physics and System Behaviour LRS are noted, and work done at the Laboratories for Thermohydraulics LTH, Nuclear Materials LNM, Final Depository Safety LES and Energy System Analyses LEA are discussed. The results obtained in thirteen areas of research in 2008 are discussed in some detail. Finally, national and international co-operation is briefly looked at and work to be done in 2009 is reviewed. The report is completed with a list of the PSI research and development projects referred to

International Photovoltaic Program Plan. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

1979-12-01

This second volume of a two-part report on the International Photovoltaic Program Plan contains appendices summarizing the results of analyses conducted in preparation of the plan. These analyses include compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about how US government actions could affect this market; international financing issues; and information on issues affecting foreign policy and developing countries.

Concept of Draft International Standard for a Unified Approach to Space Program Quality Assurance

Science.gov (United States)

Stryzhak, Y.; Vasilina, V.; Kurbatov, V.

2002-01-01

procedures to define risks related to the specific component application and evaluate safety for the entire program implementation. In the eyes of the authors, those features together with a number of other conceptual proposals should constitute a unified standard-technical basis for implementing international space programs.

Promoting Success: A Professional Development Coaching Program for Interns in Medicine.

Science.gov (United States)

Palamara, Kerri; Kauffman, Carol; Stone, Valerie E; Bazari, Hasan; Donelan, Karen

2015-12-01

Residency is an intense period. Challenges, including burnout, arise as new physicians develop their professional identities. Residency programs provide remediation, but emotional support for interns is often limited. Professional development coaching of interns, regardless of their performance, has not been reported. Design, implement, and evaluate a program to support intern professional development through positive psychology coaching. We implemented a professional development coaching program in a large residency program. The program included curriculum development, coach-intern interactions, and evaluative metrics. A total of 72 internal medicine interns and 26 internal medicine faculty participated in the first year. Interns and coaches were expected to meet quarterly; expected time commitments per year were 9 hours (per individual coached) for coaches, 5 1/2 hours for each individual coachee, and 70 hours for the director of the coaching program. Coaches and interns were asked to complete 2 surveys in the first year and to participate in qualitative interviews. Eighty-two percent of interns met with their coaches 3 or more times. Coaches and their interns assessed the program in multiple dimensions (participation, program and professional activities, burnout, coping, and coach-intern communication). Most of the interns (94%) rated the coaching program as good or excellent, and 96% would recommend this program to other residency programs. The experience of burnout was lower in this cohort compared with a prior cohort. There is early evidence that a coaching program of interactions with faculty trained in positive psychology may advance intern development and partially address burnout.

Research on international cooperation for nuclear and radiation safety

International Nuclear Information System (INIS)

Cheng Jianxiu

2013-01-01

This paper describes the importance and related requirements of international cooperation on nuclear and radiation safety, analyzes the current status, situation and challenges faced, as well as the existing weakness and needs for improvement, and gives some proposals for reference. (author)

Implementation of Programmatic Quality and the Impact on Safety

Science.gov (United States)

Huls, Dale Thomas; Meehan, Kevin

2005-01-01

The purpose of this paper is to discuss the implementation of a programmatic quality assurance discipline within the International Space Station Program and the resulting impact on safety. NASA culture has continued to stress safety at the expense of quality when both are extremely important and both can equally influence the success or failure of a Program or Mission. Although safety was heavily criticized in the media after Colimbiaa, strong case can be made that it was the failure of quality processes and quality assurance in all processes that eventually led to the Columbia accident. Consequently, it is possible to have good quality processes without safety, but it is impossible to have good safety processes without quality. The ISS Program quality assurance function was analyzed as representative of the long-term manned missions that are consistent with the President s Vision for Space Exploration. Background topics are as follows: The quality assurance organizational structure within the ISS Program and the interrelationships between various internal and external organizations. ISS Program quality roles and responsibilities with respect to internal Program Offices and other external organizations such as the Shuttle Program, JSC Directorates, NASA Headquarters, NASA Contractors, other NASA Centers, and International Partner/participants will be addressed. A detailed analysis of implemented quality assurance responsibilities and functions with respect to NASA Headquarters, the JSC S&MA Directorate, and the ISS Program will be presented. Discussions topics are as follows: A comparison of quality and safety resources in terms of staffing, training, experience, and certifications. A benchmark assessment of the lessons learned from the Columbia Accident Investigation (CAB) Report (and follow-up reports and assessments), NASA Benchmarking, and traditional quality assurance activities against ISS quality procedures and practices. The lack of a coherent operational

Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

1998-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project