WorldWideScience

Sample records for nuclear safety issues

  1. Nuclear safety - Topical issues

    International Nuclear Information System (INIS)

    1995-01-01

    The following topical issues related to nuclear safety are discussed: steam generators; maintenance strategies; control rod drive nozzle cracks; core shrouds cracks; sump strainer blockage; fire protection; computer software important for safety; safety during shutdown; operational safety experience; external hazards and other site related issues. 5 figs, 5 tabs

  2. Nuclear reactors safety issues

    International Nuclear Information System (INIS)

    Barre, Francois; Seiler, Nathalie

    2008-01-01

    Full text of publication follows: Since the seventies, economic incentives have led the utilities to drive a permanent evolution of the light water reactor (LWR). The evolution deals with the reactor designs as well as the way to operate them in a more flexible manner. It is for instance related to the fuel technologies and management. On the one hand, the technologies are in continuous evolution, such as the fuel pellets (MOX, Gd fuel, or Cr doped fuels..) as well as advanced cladding materials (M5 TM , MDA or ZIRLO). On the other hand, the fuel management is also subject to continuous evolution in particular in terms of increasing the level of burn-up, the reactor (core) power, the enrichment, as well as the duration of reactor cycles. For instance, in a few years in France, the burn-up has raised beyond the value of 39 GWj/t, initially authorized up to 52 GWj/t for the UO 2 fuel. In the near future, utilities foreseen to reach fuel burn-up of 60 GWj/t for MOX fuel and 70 GWj/t for UO 2 fuel. Furthermore, the future reactor of fourth generation will use new fuels of advanced conception. Furthermore with the objective of improving the safety margins, methods and calculation tools used by the utilities in the elaboration of their safety demonstrations submitted to the Safety Authority, are in movement. The margin evaluation methodologies often consist of a calculation chain of best-estimate multi-field simulations (e.g. various codes being coupled to simulate in a realistic way the evolution of the thermohydraulic, neutronic and mechanic state of the reactor). The statistical methods are more and more sophisticated and the computer codes are integrating ever-complex physical models (e.g. three-dimensional at fine scale). Following this evolution, the Institute of Radioprotection and Nuclear Safety (IRSN), whose one of the roles is to examine the safety records and to rend a technical expertise, considers the necessity of reevaluating the safety issues for advanced

  3. 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.

  4. 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

  5. Safety issues of nuclear production of hydrogen

    International Nuclear Information System (INIS)

    Piera, Mireia; Martinez-Val, Jose M.; Jose Montes, Ma

    2006-01-01

    Hydrogen is not an uncommon issue in Nuclear Safety analysis, particularly in relation to severe accidents. On the other hand, hydrogen is a household name in the chemical industry, particularly in oil refineries, and is also a well known chemical element currently produced by steam reforming of natural gas, and other methods (such as coal gasification). In the not-too-distant future, hydrogen will have to be produced (by chemical reduction of water) using renewable and nuclear energy sources. In particular, nuclear fission seems to offer the cheapest way to provide the primary energy in the medium-term. Safety principles are fundamental guidelines in the design, construction and operation both of hydrogen facilities and nuclear power plants. When these two technologies are integrated, a complete safety analysis must consider not only the safety practices of each industry, but any interaction that could be established between them. In particular, any accident involving a sudden energy release from one of the facilities can affect the other. Release of dangerous substances (chemicals, radiotoxic effluents) can also pose safety problems. Although nuclear-produced hydrogen facilities will need specific approaches and detailed analysis on their safety features, a preliminary approach is presented in this paper. No significant roadblocks are identified that could hamper the deployment of this new industry, but some of the hydrogen production methods will involve very demanding safety standards

  6. Nuclear power and related safety issues

    International Nuclear Information System (INIS)

    Valdezco, Eulinia M.

    2009-01-01

    There are a cluster of trends that reinforce the importance of nuclear power on the world scene. Energy is the essential underpinning for economic and societal progress and, as the developing world advances, the demand for energy is growing significantly. At the same time, the carbon-intensive sources of energy on which the world has traditionally relied - in particular, coal, oil, and natural gas - pose grave threats because the growing concentrations of carbon dioxide in the atmosphere will bring about climate and ocean acidification. At the same time, rising and volatile fossil fuel prices, coupled with concerns about the security of supplies of oil and gas, enhance interest in sources of energy that do not pose the same costs and risks. As an important part of the world's response to these threats, many countries are embarking on either new or expanded nuclear power programs, more commonly referred to as a nuclear renaissance. The construction of nuclear power plants is under consideration in over thirty countries that do not currently use nuclear power. For new entrants that may have experience in constructing and operating large-scale industrial and infrastructure projects, they may not be fully familiar with the unique requirements of nuclear power and may not be fully recognize the major commitments and understandings that they must assume. Additionally, an understanding of the full range of obligations may have diminished in those countries with only one or a few reactors and where nuclear construction has not been undertaken for a long time. It is therefore in the interest of all to ensure that every country with a nuclear power program has the resources, expertise, authority and capacity to assure safety in a complete and effective manner and is committed to doing so. This presentation will outline some of the more important national infrastructure considerations including nuclear safety issues for launching a nuclear power program. An update on the

  7. Japan's regulatory and safety issues regarding nuclear materials transport

    International Nuclear Information System (INIS)

    Saito, T.; Yamanaka, T.

    2004-01-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses

  8. 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.

  9. 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

  10. The Norwegian Plan of Action for nuclear safety issues

    International Nuclear Information System (INIS)

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects

  11. The Norwegian Plan of Action for nuclear safety issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects.

  12. Nuclear power plant safety related pump issues

    Energy Technology Data Exchange (ETDEWEB)

    Colaccino, J.

    1996-12-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed.

  13. Nuclear power plant safety related pump issues

    International Nuclear Information System (INIS)

    Colaccino, J.

    1996-01-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed

  14. Nuclear power systems: Their safety. Current issue review

    International Nuclear Information System (INIS)

    Myers, L.C.

    1994-04-01

    Human beings utilize energy in many forms and from a variety of sources. A number of countries have chosen nuclear-electric generation as a component of their energy system. At the end of 1992, there were 419 power reactors operating in 29 countries, accounting for more than 15% of the world's production of electricity. In 1992, 13 countries derived at least 25% of their electricity from nuclear units, with Lithuania leading at just over 78%, followed closely by France at 72%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 53 power reactors are under construction in 14 countries outside the former USSR. Within the ex-USSR countries, six new reactors are currently under construction. No human endeavour carries the guarantee of perfect safety and the question of whether of not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986 in the then Soviet Union, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor irrevocably changed all that. This disaster brought the matter of nuclear safety into the public mind in a dramatic fashion. Subsequent opening of the ex-Soviet nuclear power program to outside scrutiny has done little to calm people's concerns about the safety of nuclear power in that part of the world. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents that have occurred to date, as well as more recent, less dramatic events touching on the safety issue. (author). 7 refs

  15. Advanced nuclear reactor safety issues and research needs

    International Nuclear Information System (INIS)

    2002-01-01

    On 18-20 February 2002, the OECD Nuclear Energy Agency (NEA) organised, with the co-sponsorship of the International Atomic Energy Agency (IAEA) and in collaboration with the European Commission (EC), a Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Currently, advanced nuclear reactor projects range from the development of evolutionary and advanced light water reactor (LWR) designs to initial work to develop even further advanced designs which go beyond LWR technology (e.g. high-temperature gas-cooled reactors and liquid metal-cooled reactors). These advanced designs include a greater use of advanced technology and safety features than those employed in currently operating plants or approved designs. The objectives of the workshop were to: - facilitate early identification and resolution of safety issues by developing a consensus among participating countries on the identification of safety issues, the scope of research needed to address these issues and a potential approach to their resolution; - promote the preservation of knowledge and expertise on advanced reactor technology; - provide input to the Generation IV International Forum Technology Road-map. In addition, the workshop tried to link advancement of knowledge and understanding of advanced designs to the regulatory process, with emphasis on building public confidence. It also helped to document current views on advanced reactor safety and technology, thereby contributing to preserving knowledge and expertise before it is lost. (author)

  16. IAEA activities on communication of nuclear safety issues

    International Nuclear Information System (INIS)

    Wieland, P.

    2001-01-01

    The regulatory authorities in several countries have taken the initiative to overcome the renowned difficulties of communicating nuclear safety issues. They communicate with segments of the public specially in case of nuclear/radiological accidents, waste disposal, transport of radioactive material or food irradiation. This reflects the full recognition of the importance of the topic. However it is also recognized that there is hitherto a need of international assistance in order to develop a regulatory communication strategy that could be harmonized and at the same time customized to the different needs. Communications on nuclear, radiation, transport and radioactive waste safety are needed to: disseminate information on safety to the public in both routine and emergency situations ; be attentive to public concerns, and address them; maintain social trust and confidence by keeping society informed on the established safety standards and how they are enforced; facilitate the decision-making process on nuclear matters by promptly presenting factual information in a clear manner; integrate and maintain an information network at both the national and international levels; improve co-operation with other countries and international organizations; encourage the dissemination of factual information on nuclear issues in schools. A major factor in addressing all of these questions is understanding the audience(s). A two way communication process is needed to establish what particular audiences want to know and in what form they prefer to receive information. This will differ depending on the audience and circumstances. For example, the information on a routine day-to-day basis will be different from what might be needed at the time of an accident. Communication with the news media is a matter of particular importance, as they are both an audience in themselves and a channel for communicating with wider audiences. (author)

  17. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 12, September 2009

    International Nuclear Information System (INIS)

    2009-09-01

    The current issue presents information about the following topics: Nuclear Security Report 2009; G8 Nuclear Safety and Security Group (NSSG); Uranium Production Site Appraisal Team (UPSAT); New Entrant Nuclear Power Programmes Safety Guide on the Establishment of the Safety Infrastructure (DS424)

  18. Draft report on compilation of generic safety issues for light water reactor nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    A generally accepted approach to characterizing the safety concerns in nuclear power plants is to express them as safety issues which need to be resolved. When such safety issues are applicable to a generation of plants of a particular design or to a family of plants of similar design, they are termed generic safety issues. Examples of generic safety issues are those related to reactor vessel embrittlement, control rod insertion reliability or strainer clogging. The safety issues compiled in this document are based on broad international experience. This compilation is one element in the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. Refs.

  19. Draft report on compilation of generic safety issues for light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1997-07-01

    A generally accepted approach to characterizing the safety concerns in nuclear power plants is to express them as safety issues which need to be resolved. When such safety issues are applicable to a generation of plants of a particular design or to a family of plants of similar design, they are termed generic safety issues. Examples of generic safety issues are those related to reactor vessel embrittlement, control rod insertion reliability or strainer clogging. The safety issues compiled in this document are based on broad international experience. This compilation is one element in the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. Refs

  20. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 11, June 2009

    International Nuclear Information System (INIS)

    2009-06-01

    The current issue presents information about the following topics: Nuclear Safety Review for the Year 2008; Feedback from IRS Topical Studies and Events Applied to Safety Standards; Education and Training Programmes at the IAEA Department of Nuclear Safety and Security; Peer Review of Operational Safety Performance (PROSPER)

  1. Nuclear versus fossil weighing up the safety issues

    International Nuclear Information System (INIS)

    Gittus, Dzh.

    1992-01-01

    The problems of nuclear power plant safety are discussed as compared with those for the plants based on fossil fuel utilization. The conclusion is made that merits of nuclear power are much greater than its disadvantages as far as the environmental impacts are concerned

  2. Major nuclear safety and regulatory issues in Korea

    International Nuclear Information System (INIS)

    Chang, Soon Heung

    2004-01-01

    Recently the value of nuclear energy is being re-considered due to the increase of oil price, the lack of energy supply, and the competition with renewable energy source. In Unites States, Europe, and East Asia, the prospects for continuous nuclear energy development or the policy for retaining nuclear energy have been announced. According to the nuclear energy promotion plan in Korea, there are 19 operating nuclear plants currently and more 7 plants will be constructed in the future. Until now, qualitative as well as quantitative growth is remarkable. Korean nuclear power plants achieved world-best level of capacity factor. However, because of the various nuclear industrial activities, we have a lot of regulatory issues for operating plants, building new plants, and other nuclear related facilities such as research reactors or radioactive waste storage facility. In this article, important regulatory issues which are emerging in Korea will be reviewed and the approaches to solve the issues including public acceptance will be presented. Especially, I will go into detail of two special case studies: The one is the thermal sleeve separation incident in Younggwang nuclear units 5 and 6 whose outage lasts about 80 days and 90 days respectively, which is not common in worldwide nuclear history. The other is about consensus meeting of Korea nuclear energy policy which was managed by a non-governmental organization. (author)

  3. The accession to the European Union. The nuclear safety issue

    International Nuclear Information System (INIS)

    Mayer, S.; Tomic, B.; Goldemund, M.; Van der Mheen, W.; Johanson, G.

    2000-01-01

    Since mid 1999, a project based on an initiative by the European Commission has been conducted with the primary objective to develop a comprehensive, consistent, and wellbalanced methodology for the evaluation of the status of nuclear safety in countries with operating nuclear power plants, and to perform a preliminary assessment for Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. In addition to the safety status of nuclear power plants, emphasis is placed on nuclear regulation, both on organisational and legislative aspects, and on the practice of performing safety assessment. A brief overview will also be given on the nuclear safety situation in the Newly Independent States (NIS). During the course of the project, a Performance Evaluation Guide was developed with the objective to establish a sound methodology for evaluating safety of nuclear reactors in different countries in a consistent manner. The project is performed by a Consortium led by ENCONET Consulting (Austria), with participation of NNC (United Kingdom), NRG (Netherlands), and ES-konsult (Sweden). (author)

  4. An interagency space nuclear propulsion safety policy for SEI - Issues and discussion

    Science.gov (United States)

    Marshall, A. C.; Sawyer, J. C., Jr.

    1991-01-01

    An interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition, the NSPWG reviewed safety issues for nuclear propulsion and recommended top level safety requirements and guidelines to address these issues. Safety topics include reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations. In this paper the emphasis is placed on the safety policy and the issues and considerations that are addressed by the NSPWG recommendations.

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

    International Nuclear Information System (INIS)

    2009-03-01

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

  6. 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

    programmes. National safety authorities could take the initiative of organizing international workshops on how OEF has been used and implemented. Moreover, lessons learned from new construction should be provided and shared between all countries embarking and considering new build. 5. It is vital in today's environment that the synergies between safety and security are maximized, and that culture be developed that integrates safety and security requirements. Safety and security have the same purpose: protecting people, society, environment and both could be based on similar principles even if there are some differences in implementation such as openness and transparency. There are important advantages from integrating the regulation of safety and security as much as possible. 6. The quality of the supply chain is an emerging issue. Harmonization of safety requirements, design codes and quality standards within the supply chain is acknowledged as requiring further collaboration among Member States, international organizations and supplier companies. Multinational Design Evaluation Programme (MDEP) is an important first step towards this goal. 7. Transparency, collaboration, information sharing and openness is responsibility of all Member States to assure not only safety but to foster confidence and trust among all stakeholders. 8. Despite NPPs high level of safety, emergency preparedness and response is an important issue in the context of developing nuclear energy. Through international cooperation, emergency and response plans need to be developed and well coordinated within all relevant entities. 9. In the context of developing nuclear energy the generation gap in education and training as well as the necessity to build technical capacity to properly address safety issues has been acknowledged by the Conference. Therefore, adequate education and training programmes should be developed and implemented.

  7. 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

    programmes. National safety authorities could take the initiative of organizing international workshops on how OEF has been used and implemented. Moreover, lessons learned from new construction should be provided and shared between all countries embarking and considering new build. 5. It is vital in today's environment that the synergies between safety and security are maximized, and that culture be developed that integrates safety and security requirements. Safety and security have the same purpose: protecting people, society, environment and both could be based on similar principles even if there are some differences in implementation such as openness and transparency. There are important advantages from integrating the regulation of safety and security as much as possible. 6. The quality of the supply chain is an emerging issue. Harmonization of safety requirements, design codes and quality standards within the supply chain is acknowledged as requiring further collaboration among Member States, international organizations and supplier companies. Multinational Design Evaluation Programme (MDEP) is an important first step towards this goal. 7. Transparency, collaboration, information sharing and openness is responsibility of all Member States to assure not only safety but to foster confidence and trust among all stakeholders. 8. Despite NPPs high level of safety, emergency preparedness and response is an important issue in the context of developing nuclear energy. Through international cooperation, emergency and response plans need to be developed and well coordinated within all relevant entities. 9. In the context of developing nuclear energy the generation gap in education and training as well as the necessity to build technical capacity to properly address safety issues has been acknowledged by the Conference. Therefore, adequate education and training programmes should be developed and implemented.

  8. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 6, March 2008

    International Nuclear Information System (INIS)

    2008-03-01

    The current issue presents information about the following activities: 1) International Conference on Illicit Nuclear Trafficking which took place in November 2007 in Edinburgh. The principal aim of the conference was to examine the threat and context of illicit nuclear trafficking of radioactive material, specifically, what is being done to combat such trafficking and where more needs to be done. The conference was also to consider how the obligations and commitments of the legally binding and non-binding international instruments could be and are being implemented by various States. 2) INSAG Message on Nuclear Safety Infrastructure in which the INSAG Chairman Richard Meserve addressed nuclear safety in the current context and various issues that warrant special attention. 3) approved for publication the Safety Requirements publication on Safety of Nuclear Fuel Cycle Facilities. 4) The Asian Nuclear Safety Network (ANSN)

  9. Legislation for the countermeasures on special issues of nuclear safety regulations

    International Nuclear Information System (INIS)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul

    2004-02-01

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation

  10. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2004-02-15

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

  11. Factor Analysis and Framework Development for Incorporating Public Trust on Nuclear Safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seongkyung; Lee, Gyebong [The Myongji Univ., Seoul (Korea, Republic of); Lee, Gihyung; Lee, Gyehwi; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization in charge of nuclear safety in Korea, realized that a more fundamental and systematic analysis of activities is needed to actively meet the greater variety of concerns people have and increase the reliability of the results of regulation. Nuclear safety, a highly specialized field, has previously been discussed primarily from the viewpoint of the engineers who deal with the technology, but now 'public trust in nuclear safety' has to be viewed from the standpoint of the general public and from the socio-cultural perspective. Specific measures must be taken to examine which factors affect public trust and how we can secure and reproduce those factors to gain it. Also, an efficient system for incorporating public trust in nuclear safety must be established. In this study, various case studies were examined to identify the factors that affect public trust in nuclear safety. First, nuclear safety laws and information disclosure systems of major countries were examined by investigating data and conducting in-depth interviews. To explore a public framework concerning nuclear safety, big data of social media were analyzed. Also, Q methodology was used to analyze the risk schemata of the opinion leaders living in areas near nuclear power plants. Several surveys were conducted to analyze the amount of trust the public had in nuclear safety as well as their awareness of nuclear safety issues. Based on these analyses, factors affecting public trust in nuclear safety were extracted, and measures to build systems incorporating public trust in nuclear safety were proposed. This study addresses the public trust in nuclear safety on condition that the safety is ensured technically and mechanically.

  12. Factor Analysis and Framework Development for Incorporating Public Trust on Nuclear Safety issues

    International Nuclear Information System (INIS)

    Cho, Seongkyung; Lee, Gyebong; Lee, Gihyung; Lee, Gyehwi; Jeong, Jina

    2014-01-01

    The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization in charge of nuclear safety in Korea, realized that a more fundamental and systematic analysis of activities is needed to actively meet the greater variety of concerns people have and increase the reliability of the results of regulation. Nuclear safety, a highly specialized field, has previously been discussed primarily from the viewpoint of the engineers who deal with the technology, but now 'public trust in nuclear safety' has to be viewed from the standpoint of the general public and from the socio-cultural perspective. Specific measures must be taken to examine which factors affect public trust and how we can secure and reproduce those factors to gain it. Also, an efficient system for incorporating public trust in nuclear safety must be established. In this study, various case studies were examined to identify the factors that affect public trust in nuclear safety. First, nuclear safety laws and information disclosure systems of major countries were examined by investigating data and conducting in-depth interviews. To explore a public framework concerning nuclear safety, big data of social media were analyzed. Also, Q methodology was used to analyze the risk schemata of the opinion leaders living in areas near nuclear power plants. Several surveys were conducted to analyze the amount of trust the public had in nuclear safety as well as their awareness of nuclear safety issues. Based on these analyses, factors affecting public trust in nuclear safety were extracted, and measures to build systems incorporating public trust in nuclear safety were proposed. This study addresses the public trust in nuclear safety on condition that the safety is ensured technically and mechanically

  13. Nuclear energy in Lithuania: Its role, efficiency and safety issues

    International Nuclear Information System (INIS)

    Miskinis, V.; Galinis, A.; Streimikiene, D.

    2000-01-01

    This paper describes the present status of the Lithuanian economy and the power sector as well as problems related to further operation of the Ignalina Nuclear Power Plant (Ignalina NPP) which plays a crucial role in the Lithuanian energy sector. Recent studies have validated that it is economical to keep the Ignalina NPP in operation as long as it is possible and the necessary licenses can be obtained. However, its safe operation remains a very important issue determining its lifetime. Development of an infrastructure and activities necessary for safe and reliable operation of the plant are also very important. (author)

  14. Japan's regulatory and safety issues regarding nuclear materials transport

    Energy Technology Data Exchange (ETDEWEB)

    Saito, T. [Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry, Government of Japan, Tokyo (Japan); Yamanaka, T. [Japan Nuclear Energy Safety Organization, Government of Japan, Tokyo (Japan)

    2004-07-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses.

  15. Application of a methodology to determine priorities for nuclear power plant safety issues

    International Nuclear Information System (INIS)

    Daling, P.M.

    1988-01-01

    The Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) is sponsoring a research program to determine priorities of nuclear power plant safety issues. A methodology has been developed at the Pacific Northwest Laboratory (PNL) to provide technical assistance in the development of risk and cost estimates for implementing resolutions to the safety issues. The information development methods are intended to provide the NRC with a consistent level of information for use in ranking the issues. The NRC uses this information, along with judgmental factors, to rank the issues for further consideration by the NRC staff. The primary purpose of the priority rankings are to assist in the allocation of resources to issues that have high potential for reducing public risk as well as to remove issues from further consideration that have little safety significance

  16. Nuclear choice: are health and safety issues pre-empted

    International Nuclear Information System (INIS)

    Henderson, G.B. II.

    1980-01-01

    This article examines the scope of the NRC's regulatory jurisdiction under the Atomic Energy Act in order to determine its proper effect on state siting laws. At the outset, a brief history of federal regulation of commercial nuclear power plants is set forth, and the cases that have dealt with the pre-emption issue in this area are reviewed. Next, an examination of the doctrine of federal pre-emption is conducted, focussing on the legal principles as they have been developed by the Supreme Court. Since the application of the pre-emption doctrine turns largely on the intent of Congress, the Atomic Energy Act and other pertinent federal legislation are examined to discern how far Congress has sought to extend its power over regulation of nuclear power. Some policy questions are also explored to determine whether it is appropriate to imply an intent on the part of Congress to pre-empt the field. Finally, a conclusion having been reached, the practical problems of what types of evidence may be admitted into the state siting agency's hearing are discussed and some solutions offered

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

    International Nuclear Information System (INIS)

    2012-01-01

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

  18. Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste 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 co-operation, including recommendations for the IAEA`s future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper. Refs, figs, tabs

  19. Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

    International Nuclear Information System (INIS)

    1998-08-01

    The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste 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 co-operation, including recommendations for the IAEA's future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper

  20. Lessons Learned and Regulatory Countermeasures of Nuclear Safety Issues Last Year

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    Competitiveness of nuclear as the electric resource in terms of the least cost and the carbon abatement has been debated. Some institutions insist that the radioactive wastes management cost, nuclear accident cost and cheap shale gas would make the nuclear energy less competitive, while others still address the ability of nuclear energy as economical and low-carbon electric resource. This situation reminds that ensuring nuclear safety is the most important prerequisite to use of nuclear energy. Therefore, this paper will compare the different views on future nuclear competitiveness discussed right after the Fukushima accident and summarize the lessons learned and regulatory countermeasures from nuclear safety issues last year. Korea has improved the effectiveness of safety regulation up to now and still has been making efforts on further enhancing nuclear safety. The outcomes of these efforts have resulted in a high level of safety in Korean NPPs and contributing largely to the global nuclear safety through sharing and exchanging the information and knowledge of our nuclear experiences. However, now we are faced with the new challenges such as decreasing the public. Additionally, public criticism of the regulatory activities demands more clear regulatory guides and transparent process. Recently, new president announced the 'Priority to Safety and Public Trust' as the precondition to utilize the nuclear energy. We will continue to make much more efforts for the improvement of the quality of regulatory activities and effectiveness of regulatory decision making process than we have done so far. Competence through effective capacity building would be a helpful pathway to build up the public trust and ensure the acceptable level of nuclear safety. We are set to prepare the action items to be taken in the near future for improving the technical competency and transparency as the essential components of the national safety and will make efforts to implement them

  1. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Roh, Chang Hyun; Lee, Kwang Gu; Kim, Hong Chae; Lee, Yong Ho [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1999-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. Efforts are also required to cope with other circumstantial changes such as the establishment of International Nuclear Regulators Association (INRA)

  2. Resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants

    International Nuclear Information System (INIS)

    Johnson, R.E.

    1990-06-01

    This report describes the US Nuclear Regulatory Commission's (NRC's) Generic Safety Issue 29, ''Bolting Degradation or Failure in Nuclear Power Plants,'' including the bases for establishing the issue and its historical highlights. The report also describes the activities of the Atomic Industrial Forum (AIF) relevant to this issue, including its cooperation with the Materials Properties Council (MPC) to organize a task group to help resolve the issue. The Electric Power Research Institute, supported by the AIF/MPC task group, prepared and issued a two-volume document that provides, in part, the technical basis for resolving Generic Safety Issue 29. This report presents the NRC's review and evaluation of the two-volume document and NRC's conclusion that this document, in conjunction with other information from both industry and NRC, provides the bases for resolving this issue

  3. Safety issues in robotic handling of nuclear weapon parts

    International Nuclear Information System (INIS)

    Drotning, W.; Wapman, W.; Fahrenholtz, J.

    1993-01-01

    Robotic systems are being developed by the Intelligent Systems and Robotics Center at Sandia National Laboratories to perform automated handling tasks with radioactive weapon parts. These systems will reduce the occupational radiation exposure to workers by automating operations that are currently performed manually. The robotic systems at Sandia incorporate several levels of mechanical, electrical, and software safety for handling hazardous materials. For example, tooling used by the robot to handle radioactive parts has been designed with mechanical features that allow the robot to release its payload only at designated locations in the robotic workspace. In addition, software processes check for expected and unexpected situations throughout the operations. Incorporation of features such as these provides multiple levels of safety for handling hazardous or valuable payloads with automated intelligent systems

  4. Non-technical issues in safety assessments for nuclear disposal facilities

    International Nuclear Information System (INIS)

    Kallenbach-Herbert, Beate; Brohmann, Bettina

    2010-09-01

    The paper highlights that a comprehensive approach to safety affords the consideration of technology, organisation, personnel and social environment. In several safety relevant contexts of nuclear waste disposal these fields are closely interrelated. The approach for the consideration of socio-scientific aspects which is sketched in this paper supports the systematic treatment of safety relevant non-technical issues in the safety case or in safety assessments for a disposal project. Furthermore it may foster the dialogue among specialists from the technical, the natural- and the socio-scientific field on questions of disposal safety. In this way it may contribute to a better understanding among the affected scientific disciplines in nuclear waste disposal.

  5. The human side of the nuclear safety issue

    International Nuclear Information System (INIS)

    Wallis, L.R.

    1995-01-01

    Historically, scientists have been primarily concerned with the technical integrity of their own speciality within the rest of the technical community. No one saw a need to establish dialogue with the general public, special interest groups or women's groups about decisions governed by their own professions. Public support, confidence and respect came automatically. As society became more complex, this mode of operation by scientists became even more intense while institutions became more and more unwieldy. At the same time they failed to note a rather dramatic change slowly taking place - the public began making their decisions for them -decisions based many times on propaganda not fact. Left unchallenged, our sons and daughters will grow up believing that nuclear power is the most visible and potent symbol of a technological society gone amok, and it must be destroyed. Fortunately, the scientific community now recognizes that public support, confidence and respect no longer comes automatically; they must be cultivated and earned. (author)

  6. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Lee, Kwang Gu; Huh, Gyun Young; Hahn, Young Tae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. The approach to improve regulatory effectiveness is also reviewed and a transition to 'knowledge-based regulation' is suggested.

  7. EDF ageing management program of nuclear components: a safety and economical issue

    International Nuclear Information System (INIS)

    Faidy, C.

    2005-01-01

    Ageing management of Nuclear Power Plants is an essential issue for utilities, in term of safety and availability and corresponding economical consequences. Practically all nuclear countries have developed a systematic program to deal with ageing of components on their plants. This paper presents the ageing management program developed by EDF and that are compared with different other approaches in other countries (IAEA guidelines and GALL report). The paper presents a general overview of the programs, the major results, recommendations and conclusions. (author)

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  9. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

  10. Ranking of safety issues for WWER-440 model 230 nuclear power plants

    International Nuclear Information System (INIS)

    1992-02-01

    In response to requests from Member States operating Soviet designed WWER-440/230 nuclear power plants (NPPs) for assistance through the IAEA's nuclear safety services, a major international project was established to evaluate these first generation reactors as a complement to relevant ongoing national, bilateral and multilateral activities. The objective is to assist countries operating WWER-440/230 NPPs in performing comprehensive safety reviews aimed at identifying design and operational weaknesses. The scope of the project includes a review of the conceptual design of WWER-440/230 NPPs, safety review missions to each one of the operating reactors to review design and operational aspects and studies to resolve issues of generic safety concern. This report was prepared by a group of international experts and the IAEA staff and discussed by the Project Steering Committee, December 9-13, 1991 in Vienna. An overview of the safety issues identified is presented indicating their effect on the performance of the basic safety functions. Conceptual recommendations related to design issues are given as a technical basis for the safety modifications required

  11. Nuclear safety

    International Nuclear Information System (INIS)

    1991-02-01

    This book reviews the accomplishments, operations, and problems faced by the defense Nuclear Facilities Safety Board. Specifically, it discusses the recommendations that the Safety Board made to improve safety and health conditions at the Department of Energy's defense nuclear facilities, problems the Safety Board has encountered in hiring technical staff, and management problems that could affect the Safety Board's independence and credibility

  12. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Lee, Byong Ho; Baek, Woon Pil; Lee, Seong Wook; Choi, Seong Soo; Roh, Chang Hyun; Lee, Kwang Gu [Korea Advanced Institute of Scienc and Technology, Taejon (Korea, Republic of)

    1998-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. The derivation of an effective regulation system considering 'Rhodic Safety Review (PSR)', 'operating License Renewal (LR)', 'backfitting' and 'maintenance rule' is the main objective of the first two years. It is found that those approaches should be introduced in Korea as soon as possible, with cross lingkage to maximize the effectiveness of regulation. In particular, the approaches for PSR are discussed with consultation of IAEA document and foreign practices.

  13. Nuclear safety

    International Nuclear Information System (INIS)

    Tarride, Bruno

    2015-10-01

    The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

  14. Generic safety issues for nuclear power plants with light water reactors and measures taken for their resolution

    International Nuclear Information System (INIS)

    1998-09-01

    The IAEA Conference on 'The Safety of Nuclear Power: Strategy for the Future' in 1991 was a milestone in nuclear safety. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. A number of publications related to these two items issued subsequent to this conference were: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-9 (1995), the IAEA Safety Guide 50-SG-O12, periodic Safety Review of Operational Nuclear Power Plants (1994) and an IAEA publication on the Safety Evaluation of Operating Nuclear Power Plants Built to Earlier Standards - A Common Basis for Judgement (1997). Some of the findings of the 1991 Conference have not yet been fully addressed. An IAEA Symposium on reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review operating nuclear power plants which do not meet the high safety levels of the vast majority of plants and to undertake improvements with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear safety and its implementation. The purpose of this TECDOC compilation based on broad international experience, is to assist the Member States in the reassessment of operating plants by providing a list of generic safety issues identified in nuclear power plants together with measures taken to resolve these issues. These safety issues are generic in nature with regard to light water reactors and the measures for their resolution are for use as a reference for the safety reassessment of operating plants. The TECDOC covers issues thought to be significant to Member States based on consensus process. It provides an introduction to the use of generic safety issues for

  15. Nuclear law - Nuclear safety

    International Nuclear Information System (INIS)

    Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

    2012-01-01

    This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

  16. Stakeholder involvement in nuclear issues. INSAG-20. A report by the International Nuclear Safety Group

    International Nuclear Information System (INIS)

    2006-01-01

    enterprise. We believe that full and open engagement among the various stakeholders will serve to improve decision making, as well as advance the common interest in assuring the safety of nuclear installations

  17. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 8, September 2008

    International Nuclear Information System (INIS)

    2008-09-01

    The current issue presents information about the following activities: 1) International Workshops on Denial of Shipments raise awareness of suppliers, recipients, regulators, carriers/consignors and international organizations of the problems relating to denials of radioactive shipments to determine effective measures to prevent or reduce the instances of shipment denials and delays. 2) Communication and knowledge Management in the Department of Nuclear Safety and Security (NS). 3) Nuclear Security at the Beijing Olympics - an excellent example of the IAEA's work in protecting large scale public events. 4) The Incident and Emergency Centre's Participation in the ConvEx 3 Exercise, 9-10 July 2008, which took place at the Laguna Verde nuclear power plant in Mexico. During the 43 hour long exercise, the Incident and Emergency Centre (IEC) was fully activated. Staff members participating in the exercise represented different departments within the IAEA and the diversity of their knowledge and experience ensured an effective response

  18. The critical issue of nuclear power plant safety in developing countries

    International Nuclear Information System (INIS)

    Rosen, M.

    1977-01-01

    A little more than a decade from now, large commercial nuclear power facilities will be in operation in almost 40 countries, of which approximately one-half are presently considered industrially less developed. Ambitious nuclear programmes coupled with minimal and frequently under-staffed regulatory and utility organizations are only one aspect of the difficulties related to the safety of nuclear plants that face these developing countries. Inherent problems of meeting current safety standards and requirements for the significantly non-standard nuclear power plant exports can be compounded by financial considerations that may lead to purchases of reactors of various types, from more than one supplier country and with different safety standards and requirements. An examination of these issues points to the necessity and opportunity for effective action which could include provision for adequate funding for safety considerations in the purchase contract, and for sufficient regulatory assistance and training from the developed countries. The article will introduce the topic, discuss specific examples, and offer some suggestions. (author)

  19. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 15, February 2011

    International Nuclear Information System (INIS)

    2011-02-01

    The current issue presents information about the following topics: Supporting radiation protection in medicine. Wano's pre-startup support. One stop for incident and emergency communications. Emergency preparedness in IAEA Member States. Sophisticated On-Site Nuclide Identification (RanidSONNI). Over land, sea and air: safe and secure transport of radioactive material. INES at 20: Success from simplicity. IAEA and Ibero-American Forum - strengthening ties. Highlights of the 54th IAEA General Conference, 20-24 September 2010. Highlights of the International conference on Challenges faced by TSOs. Department of Nuclear Safety programme highlights

  20. The future of nuclear power after Sizewell B. 3 v.: v. 1 Economic issues; v. 2 Environmental and safety issues; v. 3 Public perception issues

    International Nuclear Information System (INIS)

    1987-01-01

    The three days of conference proceedings are published in three separate volumes. The first includes 7 papers relating to economic issues - those presented at the Sizewell-B public inquiry and the changes in the economic situation since the inquiry ended. The electricity demand, how this demand is to be met by nuclear and other fuel sources and how energy conservation might be an economic alternative to simply building more generating capacity are all issues discussed. The possible privatisation of the industry is also touched on. Volume two has 8 papers concerned with environmental and safety issues. These include the influence of the Sizewell-B decision on nuclear licensing and reactor safety, the technical and safety aspects of pressurized water reactors (PWR), the roles of British Nuclear Fuels and the United Kingdom Atomic Energy Authority, and radiation protection and effluent discharge control. The six papers in volume 3 look at public perception issues - not only towards nuclear power but towards the public inquiry process. The local authority view, the Friends of the Earth case against the PWR, and technical expertise in the decision process are also topics covered. All the papers are indexed separately. (UK)

  1. Nuclear Safety

    International Nuclear Information System (INIS)

    1978-09-01

    In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

  2. Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

    International Nuclear Information System (INIS)

    Thatcher, D.

    1989-05-01

    This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

  3. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 3

    International Nuclear Information System (INIS)

    Andrews, W.B.; Bickford, W.E.; Counts, C.A.; Gallucci, R.H.V.; Heaberlin, S.W.; Powers, T.B.; Weakley, S.A.

    1985-09-01

    This supplemental report is the fourth in a series that document and use methods developed to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. The initial report in this series was published by Andrews et al. in 1983 as NUREG/CR-2800. This supplement consists of two parts describing separate research efforts: (1) an alternative human factors methodology approach, and (2) a prioritization of the NRC's Human Factors Program Plan. The alternative human factors methodology approach may be used in specific future cases in which the methods identified in the initial report (NUREG/CR-2800) may not adequately assess the proper impact for resolution of new safety issues. The alternative methodology included in this supplement is entitled ''Methodology for Estimating the Public Risk Reduction Affected by Human Factors Improvement.'' The prioritization section of this report is entitled ''Prioritization of the US Nuclear Regulatory Commission Human Factors Program Plan.''

  4. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 9, December 2008

    International Nuclear Information System (INIS)

    2008-12-01

    The current issue presents information about the following activities: 1) IRRS Lessons Learned Workshop held on 3-5 November 2008, Seville. The main purpose of the workshop was to provide information to interested Member States regarding the IRRS, to discuss their experiences and lessons learned from the regulatory review conducted at the CSN and to explore further improvements in the planning and implementation of the IRRS, including the establishment of a network of experts from regulatory authorities. 2) Highlights of the 52 General Conference. 3) The 2008 IAEA General Conference welcomed the endorsement of the new International Nuclear and Radiological Event Scale (INES) User's Manual. 4) Safety and Security Infrastructure for Countries Embarking on Nuclear Power Programmes

  5. RBMK nuclear power plants: Generic safety issues. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-05-01

    This report has been prepared on the basis of above mentioned report and it is intended to provide information on RBMK NPPs generic safety issues. As all other insights, recommendations and conclusions resulting from the IAEA Programme, this report is intended to assist national decision makers, who have sole responsibility for the regulation and safe operation of their nuclear power plants. It also serves to focus national and international projects on priority of the RBMK safety improvements. 23 refs, 10 figs, 3 tabs

  6. France - Convention on Nuclear Safety. Fourth National Report Issued for the 2008 Peer Review Meeting

    International Nuclear Information System (INIS)

    2007-01-01

    The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 with the aim of proposing binding international obligations regarding nuclear safety. France signed the Convention on 20 September 1994, the date on which it was opened for signature during the IAEA's General Conference, and approved it on 13 September 1995. The Convention entered into force on 24 October 1996. For many years France has been participating actively in international initiatives to enhance nuclear safety, and it considers the Convention on Nuclear Safety to be an important instrument for achieving this aim. The areas covered by the Convention have long been part of the French approach to nuclear safety. This report, the fourth of its kind, is issued in compliance with Article 5 of the Convention on Nuclear Safety and presents the measures taken by France to fulfil each of the obligations of the Convention. As such, the Convention on Nuclear Safety applies to nuclear power reactors, and so most of this report deals with measures taken to ensure their safety. However, in this fourth report, as in the third, France has decided to include the measures taken concerning all research reactors, with a graded approach tailored to their size where appropriate. First of all, research reactors are subject to the same general regulations as nuclear power reactors with regard to nuclear safety and radiation protection. Furthermore, the most powerful research reactor also generates electricity. Secondly, in the reports under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, to which France is a party, the measures taken for research reactors in these areas have been described. Finally, in March 2004 the IAEA Board of Governors, on which France has a seat, approved the Code of Conduct on the Safety of Research Reactors, which incorporates most of the

  7. Generic safety issues for nuclear power plants with pressurized heavy water reactors and measures for their resolution

    International Nuclear Information System (INIS)

    2007-06-01

    The IAEA Conference on The Safety of Nuclear Power: Strategy for the Future in 1991 was a milestone in nuclear safety. The objective of this conference was to review nuclear power safety issues for which achieving international consensus would be desirable, to address concerns on nuclear safety and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. Publications related to these two items, that have been issued subsequent to this conference, include: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-8 (1995), the IAEA Safety Guide 50-SG-O12, Periodic Safety Review of Operational Nuclear Power Plants (1994) and an IAEA publication on the Safety Evaluation of Operating Nuclear Power Plants Built to Earlier Standards - A Common Basis for Judgement (1997). Some of the findings of the 1991 conference have not yet been fully addressed. An IAEA Symposium on Reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review operating nuclear power plants which do not meet the high safety levels of the vast majority of plants and to undertake improvements, with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear Safety and its implementation. To perform safety reviews and to reassess the safety of operating nuclear power plants in a uniform manner, it is imperative to have an internationally accepted reference. Existing guidance needs to be complemented by a list of safety issues which have been encountered and resolved in other plants and which can

  8. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 7, July 2008

    International Nuclear Information System (INIS)

    2008-09-01

    The current issue presents information about the following activities: 1) International Conference on Radioecology and Environmental Radioactivity 15-20 June 2008, Bergen organized by the Norwegian Radiation Protection Authority (NRPA) and the French Institute for Radiation Protection and Nuclear Safety (IRSN) in cooperation with IAEA, WHO, OECD/NEA, the International Union of Radioecology (IUR), the International Commission on Radiological Protection (ICRP) and the Journal of environmental Radioactivity (JER). This conference has evolved from the merging of the series of conferences by ECORAD and of the International Conferences on Radioactivity in the Environment. The primary objective of the conference was to review all scientific themes related to the study of environmental radioactivity and to identify new societal needs and requirements for regulatory bodies and industry. All sources of radiation, from industrial discharges in planned exposure situations through to sources in existing and emergency exposure situations, were included in the scope of the conference. 2) The Ibero American Forum of Nuclear and Radiation Safety and Security Regulatory Agencies (the FORO); 3) Kashiwazaki-Kariwa Nuclear Power Plant in the earthquake on 16 July 2007 - plant's response and effects and lessons learned

  9. Public involvement in environmental, safety and health issues at the DOE Nuclear Weapons Complex

    International Nuclear Information System (INIS)

    Taylor, Laura L.; Morgan, Robert P.

    1992-01-01

    The state of public involvement in environmental, safety, and health issues at the DOE Nuclear Weapons Complex is assessed through identification of existing opportunities for public involvement and through interviews with representatives of ten local citizen groups active in these issues at weapons facilities in their communities. A framework for analyzing existing means of public involvement is developed. On the whole, opportunities for public involvement are inadequate. Provisions for public involvement are lacking in several key stages of the decision-making process. Consequently, adversarial means of public involvement have generally been more effective than cooperative means in motivating change in the Weapons Complex. Citizen advisory boards, both on the local and national level, may provide a means of improving public involvement in Weapons Complex issues. (author)

  10. Common issues found in operating safety peer review of nuclear power plants

    International Nuclear Information System (INIS)

    Wu Meijing; Zhang Fengping

    2004-01-01

    The 3rd stage of the safety culture promotion in a Nuclear Power Plant (NPP) is characterized by establishing learning organization and continuous self-improvement. Peer Review was used as an effective tool by a lot of NPPs to improve the overall management and performance. This Paper provided the WANO Peer Review Methodology, the common issues found, the recommendation or suggestions to correct the area for improvement. It may be beneficial to other NPP which planning to have Peer Review or Self Evaluation. (authors)

  11. Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1989-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  12. Safety culture and organisational issues specific to the transitional phase from operation to decommissioning of the Ignalina Nuclear Power Plant

    International Nuclear Information System (INIS)

    Medeliene, D.

    2005-01-01

    The PHARE project Support to State Nuclear Power Safety Inspectorate for safety culture and organisational issues specific to the pre-shutdown phase of Ignalina Nuclear Power Plant was aimed at providing assistance to VATESI in their task to oversee that the Ignalina Nuclear Power Plant's management and staff are able to provide an acceptable level of reactor safety taking into account possible safety culture related problems that may occur due to the decision of an early closure of both units. Safety culture is used as a concept to characterise the attitudes, behaviour and perceptions of people that are important in ensuring the safety of nuclear power facility. Since the Chernobyl accident, the International Atomic Energy Agency (IAEA) has been active in creating guidance for ensuring that an adequate safety culture can be created and maintained. The transition from operation to decommissioning introduces uncertainty for both the organisation and individuals. This creates new challenges that need to be dealt with. Although safety culture and organisational issues have to be addressed during the entire life cycle of a nuclear power plant, owing to these special challenges, it should be especially highlighted during the transitional period from operation to decommissioning. Nuclear safety experts from Sweden, Finland, Italy, the UK and Germany, as well as Lithuanian specialists, participated in the project, and it proved to be a most effective way to share experience. The aim of this brochure is to provide information about: the importance of safety culture issues during the transitional phase from operation to decommissioning of Ignalina Nuclear Power Plant; the purpose, activities and results of this PHARE project; recommendations that are provided by western experts concerning the management of safety culture issues specific to the pre-decommissioning phase of Ignalina Nuclear Power Plant. (author)

  13. Key considerations and safety issues for the stretch power uprate at Chinshan Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Huang, P., E-mail: u808966@taipower.com.tw [Taiwan Power Company, Taipei, Taiwan (China)

    2014-07-01

    The Taiwan Power Company (TPC) has elected in recent years to implement the power uprate program as a key measure to improve the performance for TPC's nuclear power plants. The Measurement Uncertainty Recapture (MUR) power uprate for the TPC's three operating plants (reported in 16th PBNC) had been successfully implemented by July 2009. For the stretch power uprate (SPU) followed, the magnitude of uprate (~3%) is determined based on the available margins for original plant design, constant pressure approach (BWR) is adopted to simplify the evaluation, and major plant modifications are not considered. As the first application, the SPU safety analysis report (SAR) for the Chinshan plant was submitted to the ROCAEC in December 2010. A review task force was organized by the ROCAEC to perform a very thorough review. As the licensing bases are fully re-examined during the review process, many important issues have been identified and addressed. The key issues resolved include: conformance of SAR to ROCAEC's review guidance; re-examination of post-Fukushima comprehensive safety assessment; qualification of containment protective coatings; GL 96-06 (Assurance of Equipment Operability and Containment Integrity During DBA Conditions); credit for Containment Accident Pressure; issue for Annulus Pressurization Loads Evaluation. These issues required very extensive efforts to resolve. With the cooperative efforts by TPC and contractor (Institute of Nuclear Energy Research), however, all the issues were fully clarified and SAR was approved by ROCAEC on November 15, 2012. The first step SPU (2% OLTP) was successfully implemented in November 2012 at both units. (author)

  14. Nuclear safety regulations

    International Nuclear Information System (INIS)

    1998-01-01

    The Departmental Rules and The Safety Guides were issued by the NNSA in 1998. The NNSA performed the activities of propagation and implementation of nuclear safety regulations at QTNPP in order to improve the nuclear safety culture of operating organization and construct and contract organizations

  15. Advanced CFD simulation for the assessment of nuclear safety issues at EDF. Some examples

    International Nuclear Information System (INIS)

    Vare, Christophe

    2014-01-01

    EDF R and D has computer power that puts it amongst the top industrial research centers in the world. Its supercomputers and in-house codes as well as its experts represent important capabilities to support EDF activities (safety analyses, support to the design of new reactors, analysis of accidental situations non reproducible by experiments, better understanding of physics or complex system response, effects of uncertainties and identification of prominent parameters, qualification and optimization of processes and materials...). Advanced numerical simulation is a powerful tool allowing EDF to increase its competitiveness, improve its performance and the safety of its plants. On this issue, EDF made the choice to develop its own in-house codes, instead of using commercial software, in order to be able to capitalize its expertise and methodologies. This choice allowed as well easier technological transfer to the concerned business units or engineering divisions, fast adaptation of our simulation tools to emerging needs and the development of specific physics or functionalities not addressed by the commercial offer. During the last ten years, EDF has decided to open its in-house codes, through the Open Source way. This is the case for Code – Aster (structure analysis), Code – Saturne (computational fluid dynamics, CFD), TELEMAC (flow calculations in aquatic environment), SALOME (generic platform for Pre and Post-Processing) and SYRTHES (heat transfer in complex geometries), among others. The 3 open source software: Code – Aster, Code – Saturne and TELEMAC, are certified by the French Nuclear Regulatory Authority for many «Important to Safety» studies. Advanced simulation, which treats complex, multi-field and multi-physics problems, is of great importance for the assessment of nuclear safety issues. This paper will present 2 examples of advanced simulation using Code – Saturne for safety issues of nuclear power plants in the fields of R and D and

  16. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2003-02-15

    Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

  17. Legislation for the countermeasures on special issues of nuclear safety regulations

    International Nuclear Information System (INIS)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul

    2003-02-01

    Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea

  18. Safety issues to be taken into account in designing future nuclear fusion facilities

    Energy Technology Data Exchange (ETDEWEB)

    Perrault, Didier, E-mail: didier.perrault@irsn.fr

    2016-11-01

    Highlights: • Assess if decay heat removal is a safety function. • Re-study accidents considered for ITER and identify those specific to DEMO. • Limit tritium inventory and optimize main gaseous tritium release routes. • Take into account constraints related to requirements of waste disposal routes. - Abstract: For several years now, the French “Institut de Radioprotection et de Sûreté Nucléaire” has been carrying out expertise of ITER fusion facility safety files at the request of the French “Autorité de Sûreté Nucléaire”. As part of the lengthy process which should lead to mastering nuclear fusion, different fusion facility projects are currently under study throughout the world to be ready to continue building on the work which will take place in the ITER facility. On the basis of the experience acquired during the ITER safety expertise, the IRSN has carried out a preliminary study of the safety issues which seem necessary to take into account right from the earliest design phase of these DEMO facilities. The issues studied have included the decay heat removal, exposure to ionizing radiation, potential accidents, and effluent releases and waste. The study shows that it will be important to give priority to the following actions, given that their results would have a major influence on the design: assess if decay heat removal is a safety function, re-study the accidents considered in the context of the ITER project and identify those specific to DEMO, and optimize each of the main routes for gaseous tritium releases.

  19. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 2

    International Nuclear Information System (INIS)

    Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.; Heaberlin, S.W.; Fecht, B.A.; Allen, C.H.; Allen, R.D.; Bickford, W.E.; Carbaugh, E.H.; Lewis, J.R.

    1983-12-01

    This is the third in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 31 issues. Each issue was considered within the constraints of available information as of summer 1983, and two staff-weeks of labor. The results are referenced, as one consideration in setting priorities for reactor safety issues, in NUREG-0933, A Prioritization of Generic Safety Issues

  20. Addressing issues raised by stakeholders: evolving practices at the Canadian Nuclear Safety Commission (CNSC)

    International Nuclear Information System (INIS)

    Flavelle, Peter

    2004-01-01

    In the 1980's the Atomic Energy Control Board (AECB) opened its hearings to the public and began making decisions and documents related to these hearings publicly available. In response to stakeholder concerns, in the 1990's the AECB began holding some hearings in the communities where licensees had their operations, giving a wide range of stakeholders better access to the hearings. During the same period, societal concern over environmental issues culminated in environmental protection legislation, environmental assessment legislation and explicit inclusion of environmental protection in the responsibilities of the CNSC which regulates the nuclear industry in Canada under the authority of the Nuclear Safety and Control Act. The CNSC has continued the approach to openness and transparency through the participation of applicants and intervenors in its public hearing and meeting processes. License applications, environmental assessments, stakeholder interventions and CNSC staff evaluations and recommendations are published and distributed to all interested stakeholders in a timely manner, sufficient for thorough examination. Improved scheduling of hearings and meetings, holding more hearings and meetings where the licensed activities take place and the use of teleconferencing, video conferencing and video web-casting improve accessibility to the hearings, allowing full participation by all stakeholders. The CNSC also publishes detailed Records of Proceedings, including the reasons for decision, within six weeks of the closing of a hearing. In addition to operating and publishing documents in both official languages, the CNSC adopts some measures to communicate with aboriginal stakeholders in their own language. In addition to the hearing process, the CNSC provides a broad range of documents and information on its internet site. A new Communications and Consultation Policy has been developed to help ensure that communications and consultation initiatives of

  1. Identification of unresolved safety issues relating to nuclear power plants. Report to Congress

    International Nuclear Information System (INIS)

    1979-01-01

    The report describes the review undertaken over the last year that resulted in identifying 17 issues as Unresolved Safety Issues. In addition, the report provides specific discussions of why certain issues were not included. The report also provides a brief background discussion describing Section 210 of the Energy Reorganization Act and the NRC program for the resolution of generic issues described in NUREG-0410

  2. Information report on nuclear safety and radiation protection of the ECRIN INB - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    Published in compliance with the French code of the environment, this report first presents the Malvesi establishment, the ECRIN basic nuclear installation (INB), the COMURHEX II project, and the policy for a sustainable development and continuous progress of this establishment. It describes the various measures regarding nuclear safety and radiation protection: nuclear safety, safety guarantee for personnel and installations, management of emergency situations, preservation of staff health and protection, inspections, actions undertaken regarding nuclear safety and radiation protection. It reports nuclear events which occurred, describes the management of effluents and the control of the environment (environmental policy, management of effluents from the Malvesi establishment, management of effluents from the ECRIN INB, reduction of consumptions). It addresses the waste management (industrial and radioactive wastes) and the management of other impacts of the ECRIN INB. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  3. Information report on nuclear safety and radiation protection of the ECRIN INB - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents the Malvesi establishment, the ECRIN basic nuclear installation (INB), the COMURHEX II project, and the policy for a sustainable development and continuous progress of this establishment. It describes the various measures regarding nuclear safety and radiation protection: nuclear safety, safety guarantee for personnel and installations, management of emergency situations, preservation of staff health and protection, inspections, actions undertaken regarding nuclear safety and radiation protection. It reports nuclear events which occurred, describes the management of effluents and the control of the environment (environmental policy, management of effluents from the Malvesi establishment, management of effluents from the ECRIN INB, reduction of consumptions). It addresses the waste management (industrial and radioactive wastes) and the management of other impacts of the ECRIN INB. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  4. Guidelines for nuclear-power-plant safety-issue-prioritization information development

    International Nuclear Information System (INIS)

    Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L.; Smith, R.I.; Weakley, S.A.

    1983-02-01

    Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions

  5. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    International Nuclear Information System (INIS)

    Daling, P.M.; Lavender, J.C.

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983)

  6. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    Energy Technology Data Exchange (ETDEWEB)

    Daling, P.M.; Lavender, J.C. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983).

  7. Nuclear safety. Seguranca nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

    1981-01-01

    What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

  8. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 14, March 2010

    International Nuclear Information System (INIS)

    2010-03-01

    The current issue presents information about the following topics: Highlights of the 2nd International Conference on Effective Nuclear Regulatory Systems, Cape Town, 14 December 2009. Denial of Shipment of Radioactive Material. Emergency Preparedness Review (EPREV)

  9. Guidelines for nuclear-power-plant safety-issue prioritization information development

    International Nuclear Information System (INIS)

    Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.

    1983-05-01

    This is the second in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report contains results of issue-specific analyses for 15 issues. Each issue was considered within the contraints of available information as of September 1982 and two staff-weeks of labor. The results will be referenced, as one consideration in setting priorities for reactor safety issues, in an NRC prioritization report to be published at a future date

  10. Application of Solar Chimney Concept to Solve Potential Safety Issues of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Khalid; PARK, Youn Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    In this paper two main events and their causes have been investigated and a potential alternative supporting system will be provided. The first event to be addressed is the Station Blackout (SBO) caused by the inherent unreliability of the Emergency Diesel Generators (EDGs) and Alternative AC (AAC) power sources. Different parameters affect The EDG unreliability; for instance, mechanical, operational, maintenance and surveillance. Those parameters will be analyzed and linked to plant safety and Core Damage Frequency (CDF). Also the AACs, the SBO diesel generators, will be studied and their operational requirements similarity with the EDGs will be discussed. The second event to be addressed is the Loss of Ultimate Heat Sink (LUHS) caused by the degradation of heat exchange effectiveness, that is, the poor heat transfer to the Ultimate Heat Sink (UHS). Different causes to such case were observed; intake lines blockages due to ice and foreign biological matters formation and oil spill near the heat sink causing the oil leakage to the heat exchangers tubes. The later cause, oil spill, has been given a special attention here due its potential effects for different nuclear power plants (NPPs) around the world; for example, Finland and the United Arab Emirates (UAE). For the Finnish case, the Finnish nuclear regulator (STUK) took already countermeasures for such scenario by introducing alternative heat sink, cooling towers, for the primary used heat sink, sea water, for one of its nuclear power plants. The abundance of the solar irradiation in the UAE region provides a perfect condition for the implementation of solar power applications. Utilizing this unique characteristic of that region may provide promising alternative and diverse options for solving potential safety related issues of their NPPs. The Solar Chimney Power Plant (SCPP) could be employed to serve as a supporting system to provide emergency power, in the case of SBO, and emergency cooling, in the case of

  11. Application of Solar Chimney Concept to Solve Potential Safety Issues of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Khasawneh, Khalid; PARK, Youn Won

    2014-01-01

    In this paper two main events and their causes have been investigated and a potential alternative supporting system will be provided. The first event to be addressed is the Station Blackout (SBO) caused by the inherent unreliability of the Emergency Diesel Generators (EDGs) and Alternative AC (AAC) power sources. Different parameters affect The EDG unreliability; for instance, mechanical, operational, maintenance and surveillance. Those parameters will be analyzed and linked to plant safety and Core Damage Frequency (CDF). Also the AACs, the SBO diesel generators, will be studied and their operational requirements similarity with the EDGs will be discussed. The second event to be addressed is the Loss of Ultimate Heat Sink (LUHS) caused by the degradation of heat exchange effectiveness, that is, the poor heat transfer to the Ultimate Heat Sink (UHS). Different causes to such case were observed; intake lines blockages due to ice and foreign biological matters formation and oil spill near the heat sink causing the oil leakage to the heat exchangers tubes. The later cause, oil spill, has been given a special attention here due its potential effects for different nuclear power plants (NPPs) around the world; for example, Finland and the United Arab Emirates (UAE). For the Finnish case, the Finnish nuclear regulator (STUK) took already countermeasures for such scenario by introducing alternative heat sink, cooling towers, for the primary used heat sink, sea water, for one of its nuclear power plants. The abundance of the solar irradiation in the UAE region provides a perfect condition for the implementation of solar power applications. Utilizing this unique characteristic of that region may provide promising alternative and diverse options for solving potential safety related issues of their NPPs. The Solar Chimney Power Plant (SCPP) could be employed to serve as a supporting system to provide emergency power, in the case of SBO, and emergency cooling, in the case of

  12. Handling of safety issues in the senior management group at the nuclear power plants

    International Nuclear Information System (INIS)

    Wahlstroem, B.

    2001-02-01

    The report describes the results from a series of interviews, which were made in the preparation of an application for a reserach project to the Nuclear Fission Safety Programme of EU. The project application 'Learning organisations for nuclear safety - LearnSafe' collected a consortium of 5 partners and 9 associated partneres and has been assigned the reference number FIS5-2001-00066 by the European Commission. (au)

  13. Legal issues, authoritative licenses and tasks in relation with nuclear safety in Hungary

    International Nuclear Information System (INIS)

    Oerdoegh, J.; Voeroess, L.

    1998-01-01

    After a brief historical overview of nuclear authorities in Hungary, the role and functions of the National Atomic Energy Office are presented. It is the primary authority in this country on nuclear safety, with tasks and functions of licensing, inspection and enforcing safety measures. The organizational structure of NAEO and its position as a Governmental body is shown. Other tasks include the promotion of R and D coordination and international cooperation. (R.P.)

  14. Nuclear safety

    International Nuclear Information System (INIS)

    2014-01-01

    The Program on Nuclear Safety comprehends Radioprotection, Radioactive Waste Management and Nuclear Material Control. These activities are developed at the Nuclear Safety Directory. The Radioactive Waste Management Department (GRR) was formally created in 1983, to promote research and development, teaching and service activities in the field of radioactive waste. Its mission is to develop and employ technologies to manage safely the radioactive wastes generated at IPEN and at its customer’s facilities all over the country, in order to protect the health and the environment of today's and future generations. The Radioprotection Service (GRP) aims primarily to establish requirements for the protection of people, as workers, contractors, students, members of the general public and the environment from harmful effects of ionizing radiation. Furthermore, it also aims to establish the primary criteria for the safety of radiation sources at IPEN and planning and preparing for response to nuclear and radiological emergencies. The procedures about the management and the control of exposures to ionizing radiation are in compliance with national standards and international recommendations. Research related to the main activities is also performed. The Nuclear Material Control has been performed by the Safeguard Service team, which manages the accountability and the control of nuclear material at IPEN facilities and provides information related to these activities to ABACC and IAEA. (author)

  15. Nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Program on Nuclear Safety comprehends Radioprotection, Radioactive Waste Management and Nuclear Material Control. These activities are developed at the Nuclear Safety Directory. The Radioactive Waste Management Department (GRR) was formally created in 1983, to promote research and development, teaching and service activities in the field of radioactive waste. Its mission is to develop and employ technologies to manage safely the radioactive wastes generated at IPEN and at its customer’s facilities all over the country, in order to protect the health and the environment of today's and future generations. The Radioprotection Service (GRP) aims primarily to establish requirements for the protection of people, as workers, contractors, students, members of the general public and the environment from harmful effects of ionizing radiation. Furthermore, it also aims to establish the primary criteria for the safety of radiation sources at IPEN and planning and preparing for response to nuclear and radiological emergencies. The procedures about the management and the control of exposures to ionizing radiation are in compliance with national standards and international recommendations. Research related to the main activities is also performed. The Nuclear Material Control has been performed by the Safeguard Service team, which manages the accountability and the control of nuclear material at IPEN facilities and provides information related to these activities to ABACC and IAEA. (author)

  16. Nuclear Safety Regulations

    International Nuclear Information System (INIS)

    Novosel, N.; Prah, M.

    2008-01-01

    Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

  17. For improvements of issues behind food safety regulations implemented following the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Hamada, Nobuyuki; Ogino, Haruyuki

    2011-01-01

    The great quake and a subsequent tsunami seriously damaged the Fukushima nuclear power plants on 11 March 2011, followed by radionuclide releases outside the crippled reactors. Regulatory limits stipulated as 'provisional regulation values' were set to minimize internal exposure via ingestion of contaminated food and drink. Tap water, raw milk, vegetables, seafood and tea exceeded the limit, and distribution and/or consumption of these stuffs were temporality restricted. It took 7 and 11 days to set the provisional regulation values and to order the first restriction after the declaration of nuclear emergency situations, respectively. All restrictions began within 25 days after the first excess in each item, but the commencement of restrictions was concomitant with the social dislocations. All restrictions for tap water were withdrawn within 51 days, but restrictions for food have yet to be lifted. Among all items, maximum levels were detected in leafy vegetables (54,100 Bq/kg of 131 I, 82,000 Bq/kg of 134 Cs and 137 Cs). Most provisional regulation values were adopted from the preexisting 'index values'. Index values were logically designed and practically convenient. However, food and radionuclides were not comprehensively covered, and the same value was given to emergency and existing exposure situations. Also, different provisional regulation values were set for infants and others. In this respect, we here propose the concept of the 'graded triphasic reference level system' to optimize food safety regulations in early, intermediate and late phases following the accident, where each example phase-specific reference level value is provided. This paper focuses on the logic and issues behind such food safety regulations. The food monitoring data of 24,685 samples and the enforced restrictions shall also be outlined predicated on the information available as of 12 June 2011. (author)

  18. Nuclear economics: Issues and facts

    International Nuclear Information System (INIS)

    Hudson, C.R.

    1993-01-01

    Nuclear economics has become on the more prominent topics related to nuclear power. Beyond the subjects of nuclear safety and waste disposal, questions and concerns of nuclear power economics have emerged with growing frequency in utility board rooms, in state and federal regulatory proceedings, and in the media. What has caused nuclear power economics to become such a popular topic? This paper addresses issues and facts related to historical nuclear plant costs, new nuclear plant projections, and warning signals for future plants

  19. Nuclear Safety Culture

    International Nuclear Information System (INIS)

    2017-01-01

    Ethics is caring about people and Safety is caring that no physical harm comes to people.Therefore Safety is a type of Ethical Behavior. Culture: is The Way We Do Things Here.Safety Culture is mixture of organization traditions, values, attitudes and behaviors modeled by Its leaders and internalized by its members that serve to make nuclear safety the overriding priority. Safety Culture is that assembly of characteristics and attitudes in Organisations and individuals which established that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance

  20. Nuclear Safety Review 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

  1. Nuclear Safety Review 2013

    International Nuclear Information System (INIS)

    2013-07-01

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis

  2. Aviation Safety Issues Database

    Science.gov (United States)

    Morello, Samuel A.; Ricks, Wendell R.

    2009-01-01

    The aviation safety issues database was instrumental in the refinement and substantiation of the National Aviation Safety Strategic Plan (NASSP). The issues database is a comprehensive set of issues from an extremely broad base of aviation functions, personnel, and vehicle categories, both nationally and internationally. Several aviation safety stakeholders such as the Commercial Aviation Safety Team (CAST) have already used the database. This broader interest was the genesis to making the database publically accessible and writing this report.

  3. Nuclear safety endeavour in Korea

    International Nuclear Information System (INIS)

    Sang-hoon lee

    1987-01-01

    Korea's nuclear power plant program is growing. As it grows, nuclear safety becomes an important issue. This article traces the development of Korean nuclear power program, the structure of the nuclear industries, the Nuclear Safety Center and its roles in the regulation and licensing of nuclear power plant, and also identifies some of the activities carried out to enhance the safety of nuclear power plants. (author)

  4. Facts about Nuclear Waste Safety - How the issue is being treated in Ghana

    International Nuclear Information System (INIS)

    Glover, E.T.; Fletcher, J.J.

    2001-01-01

    The fear of radioactive discharges and releases particularly from severe nuclear accidents and radioactive waste is central to public concern about nuclear activities. This fear was witnessed when Ghana began to suffer shortage in electricity supply from the hydroelectric power station at Akosombo and debates began on Ghana's energy mix and alternate options. As in every country, dependable and continuous supply of electricity is a prerequisite for ensuring sustainable development. The Ghana Atomic Energy Commission was confronted at that time more than ever with the problem of public education on nuclear power safety to enhance public acceptance. This paper presents what the Ghana Atomic Energy Commission is doing to communicate facts and education about nuclear waste safety to the Ghanaian public and to facilitate the comparison of risk from nuclear reactors and disposal facilities with risks from other forms of technology. The paper also tells of the usefulness of and difficulties in using Jos Draiger and John Lakey's manual on Radiation and Radiation Protection to educate pupils in the Ghana Atomic Energy Commission Preparatory School. The difficulties in communication of facts about nuclear, radiation and waste safety in Ghana, because of the different languages and dialects used by Ghanaians in the rural areas of Ghana. As a large number of factors influence decision making in the energy sector. To assist energy planners, the Ghana Atomic Energy Commission carried out assessments of alternative energy sources, covering a broad range of technical, economic and environmental factors. Cost-benefit and risk-benefit analyses place the nuclear power option on a scale comparable to the other electricity generating technologies. How come then that nuclear power option has so much negative publicity? The conclusion is drawn that literacy in nuclear radiation and waste safety is needed at all levels of the Ghanaian society. As inadequate perception of radiation risk

  5. Development of safety-related regulatory requirements for nuclear power in developing countries. Key issue paper no. 4

    International Nuclear Information System (INIS)

    Han, K.I.

    2000-01-01

    In implementing a national nuclear power program, balanced regulatory requirements are necessary to ensure nuclear safety and cost competitive nuclear power, and to help gain public acceptance. However, this is difficult due to the technology-intensive nature of the nuclear regulatory requirements, the need to reflect evolving technology and the need for cooperation among multidisciplinary technical groups. This paper suggests approaches to development of balanced nuclear regulatory requirements in developing countries related to nuclear power plant safety, radiation protection and radioactive waste management along with key technical regulatory issues. It does not deal with economic or market regulation of electric utilities using nuclear power. It suggests that national regulatory requirements be developed using IAEA safety recommendations as guidelines and safety requirements of the supplier country as a main reference after careful planning, manpower buildup and thorough study of international and supplier country's regulations. Regulation making is not recommended before experienced manpower has been accumulated. With an option that the supplier country's regulations may be used in the interim, the lack of complete national regulatory requirements should not deter introduction of nuclear power in developing countries. (author)

  6. Nuclear safety culture and nuclear safety supervision

    International Nuclear Information System (INIS)

    Chai Jianshe

    2013-01-01

    In this paper, the author reviews systematically and summarizes up the development process and stage characteristics of nuclear safety culture, analysis the connotation and characteristics of nuclear safety culture, sums up the achievements of our country's nuclear safety supervision, dissects the challenges and problems of nuclear safety supervision. This thesis focused on the relationship between nuclear safety culture and nuclear safety supervision, they are essential differences, but there is a close relationship. Nuclear safety supervision needs to introduce some concepts of nuclear safety culture, lays emphasis on humanistic care and improves its level and efficiency. Nuclear safety supervision authorities must strengthen nuclear safety culture training, conduct the development of nuclear safety culture, make sure that nuclear safety culture can play significant roles. (author)

  7. Nuclear safety in France

    International Nuclear Information System (INIS)

    Tanguy, P.

    1979-01-01

    A brief description of the main safety aspects of the French nuclear energy programme and of the general safety organization is followed by a discussion on the current thinking in CEA on some important safety issues. As far as methodology is concerned, the use of probabilistic analysis in the licensing procedure is being extensively developed. Reactor safety research is aimed at a better knowledge of the safety margins involved in the present designs of both PWRs and LMFBRs. A greater emphasis should be put during the next years in the safety of the nuclear fuel cycle installations, including waste disposals. Finally, it is suggested that further international cooperation in the field of nuclear safety should be developed in order to insure for all countries the very high safety level which has been achieved up till now. (author)

  8. Prioritization of generic safety issues

    International Nuclear Information System (INIS)

    Emrit, R.; Minners, W.; VanderMolen, H.

    1983-12-01

    This report presents the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The report focuses on the prioritization of generic safety issues. Issues primarily concerned with the licensing process or environmental protection and not directly related to safety have been excluded from prioritization. The prioritized issues include: TMI Action Plan items under development; previously proposed issues covered by Task Action Plans, except issues designated at Unresolved Safety Issues (USIs) which had already been assigned high priority; and newly-proposed issues. Future supplements to this report will include the prioritization of additional issues. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative

  9. Uncertainty representation and combination: new results with application to nuclear safety issues

    International Nuclear Information System (INIS)

    Destercke, S.

    2008-10-01

    It often happens that the value of some parameters or variables of a system are imperfectly known, either because of the variability of the modelled phenomena, or because the available information is imprecise or incomplete. Classical probability theory is usually used to treat these uncertainties. However, recent years have witnessed the appearance of arguments pointing to the conclusion that classical probabilities are inadequate to handle imprecise or incomplete information. Other frameworks have thus been proposed to address this problem: the three main are probability sets, random sets and possibility theory. There are many open questions concerning uncertainty treatment within these frameworks. More precisely, it is necessary to build bridges between these three frameworks to advance toward a unified handling of uncertainty. Also, there is a need of practical methods to treat information, as using these frameworks can be computationally costly. In this work, we propose some answers to these two needs for a set of commonly encountered problems. In particular, we focus on the problems of: 1) Uncertainty representation 2) Fusion and evaluation of multiple source information 3) Independence modelling, the aim being to give tools (both of theoretical and practical nature) to treat uncertainty. Some tools are then applied to some problems related to nuclear safety issues. (author)

  10. Information report on nuclear safety and radiation protection of MELOX - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2014 and perspectives for 2015. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2014 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2015. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  11. Information report on nuclear safety and radiation protection of MELOX - Issue 2013

    International Nuclear Information System (INIS)

    2014-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2013 and perspectives for 2014. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2013 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2014. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  12. Information report on nuclear safety and radiation protection of MELOX - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2012 and perspectives for 2013. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2012 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2013. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  13. New Nuclear Safety Regulations

    International Nuclear Information System (INIS)

    Novosel, N.; Prah, M.; Cizmek, A.

    2008-01-01

    Beside new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06), based on Nuclear Safety Act (Official Gazette No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of announcing the intention to perform nuclear activity, submitting an application for the issue of a license to perform nuclear activity, and the procedure for adoption a decision on issuing a nuclear activity license. The Ordinance also regulates the contents of the application form for the announcement of the intention to perform nuclear activity, as well as of the application for the issue of a nuclear activity license and the method of keeping a nuclear activity register. The Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, SONS finalized the text of new Ordinance on nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance regulates nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance defines facilities in which nuclear activity is

  14. Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2014

    International Nuclear Information System (INIS)

    2015-01-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: general considerations on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  15. Information report on nuclear safety and radiation protection of the Romans site - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  16. Information report on nuclear safety and radiation protection of the Romans site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  17. Information report on nuclear safety and radiation protection of the Romans site - Issue 2013

    International Nuclear Information System (INIS)

    2014-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  18. Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: generalities on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  19. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

    International Nuclear Information System (INIS)

    2013-01-01

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  20. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

    International Nuclear Information System (INIS)

    2014-01-01

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  1. Information report on nuclear safety and radiation protection of the La Hague AREVA site- Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basis nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2012, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  2. Materials-related issues in the safety and licensing of nuclear fusion facilities

    Science.gov (United States)

    Taylor, N.; Merrill, B.; Cadwallader, L.; Di Pace, L.; El-Guebaly, L.; Humrickhouse, P.; Panayotov, D.; Pinna, T.; Porfiri, M.-T.; Reyes, S.; Shimada, M.; Willms, S.

    2017-09-01

    Fusion power holds the promise of electricity production with a high degree of safety and low environmental impact. Favourable characteristics of fusion as an energy source provide the potential for this very good safety and environmental performance. But to fully realize the potential, attention must be paid in the design of a demonstration fusion power plant (DEMO) or a commercial power plant to minimize the radiological hazards. These hazards arise principally from the inventory of tritium and from materials that become activated by neutrons from the plasma. The confinement of these radioactive substances, and prevention of radiation exposure, are the primary goals of the safety approach for fusion, in order to minimize the potential for harm to personnel, the public, and the environment. The safety functions that are implemented in the design to achieve these goals are dependent on the performance of a range of materials. Degradation of the properties of materials can lead to challenges to key safety functions such as confinement. In this paper the principal types of material that have some role in safety are recalled. These either represent a potential source of hazard or contribute to the amelioration of hazards; in each case the related issues are reviewed. The resolution of these issues lead, in some instances, to requirements on materials specifications or to limits on their performance.

  3. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 5, September 2007

    International Nuclear Information System (INIS)

    2007-09-01

    This newsletter reports on the denial of shipments of radioactive materials, the IAEA,s illicit trafficking database, the knowledge management conference and the IAEA Response Assistance network (RANET). Radioactive material needs to be transported for use in public health and industry. Transport of radioactive material is governed by national and international regulations which are based on the IAEA's Regulations for the Safe Transport of Radioactive Material. These Regulations, developed by experts around the world, ensure high standards of safety. However, even when complying with the Regulations, there continue to be instances where shipments have been denied or delayed. Denying or delaying a shipment of radioactive material for medical use can result in hardships to patients. In addition, radioactive materials for other activities such as sterilization or power generation are also affected. In 2006, to increase transparency, seek effective solutions and permit participation of interested parties, the IAEA Director General created a senior level International Steering Committee on Denials of Shipments of Radioactive Material, which includes representatives from IAEA Member States, international governmental and nongovernmental organizations and industry. The Committee's mandate is to coordinate international efforts at determining solution of issues related to the denial of shipments and facilitate the coordination of a comprehensive international work plan of activities. In the early 1990s a number of trafficking cases in the Czech Republic, Germany and the Russian Federation involved highly enriched uranium (HEU) and Plutonium, some in kilogram quantities. These cases raised serious concerns over the threat posed by nuclear materials which were apparently available for sale on the black market. In response, States asked the IAEA to establish a data base on illicit trafficking incidents. First established in the mid-1990s, this work was greatly accelerated and

  4. Databases on safety issues for WWER and RBMK reactors. Users' manual. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    At the beginning of the IAEA Extrabudgetary Programme on the safety of WWER reactors a great number of findings and recommendations (safety items) were collected as a result of design review and safety review missions of the WWER-440/230 type reactors. On the basis of these findings a technical database containing more than 1300 records was established to support the consolidation of the information obtained and to help in identification of safety issues. After the scope of the WWER extrabudgetary programme was extended similar data sets were prepared for the WWER-440/213, WWER-1000 and RBMK nuclear power plants. This publication describes the structure of the databases on safety issues of WWER and RBMK NPPs, the information sources used in the databases and interrogation capabilities for users to obtain the necessary information. 14 refs, 9 figs, 5 tabs

  5. Evaluation of safety issues on newly regulated nuclear power plant by tsunami-level 1 PRA

    International Nuclear Information System (INIS)

    Tsuji, Yutaro; Miwa, Shuichiro; Mori, Michitsugu

    2014-01-01

    The tsunami caused by the Great East Japan Earthquake triggered severe accidents involving the units 1 to 4 at the Fukushima Dai-ichi nuclear power station (NPS). In order to re-operate existing nuclear power plants it should be necessary to reduce the core damage frequency on risk by tsunami. In this work, effects of the off-site power supply installation on resuming operation of nuclear power plants were investigated by utilizing the Tsunami-Level 1 Probability Risk Assessment (PRA). Unit 2 of the Onagawa nuclear power station, which resembled units 2 and 3 of Fukushima Dai-ichi, was selected for PRA. First, event-tree was created for the units of the Onagawa nuclear power station with the safety systems such as Emergency Core Cooling System (ECCS), investigating the plant situation at the time of the earthquake and tsunami occurrences. It was assumed that the magnitude of the tsunami was equivalent to the Great East Japan Earthquake. The accident-analytical progression-time was 36 hours, determined from the core-damage occurrence of the unit 3 of Fukushima Dai-ichi nuclear power station. Failure probabilities were calculated by the fault tree, which was created from the elements listed in the event tree. For the calculation, failure rates reported by the NUCIA (NUClear Information Archives) were primarily utilized. Then, obtained failure probabilities were embedded to the event tree. Core damage probabilities were evaluated by calculating success and failure rates for each accidental progression and scenarios. Restoration of the failed equipment and machineries was not considered in the analysis. Installation of the power supply vehicles at the nuclear power plant site reduced the core damage probability from 2.58×10 -6 to 8.56×10 -7 . However, continued addition of the power supply vehicles could not lower the core damage probability further more. In the case of Unit 2 of Onagawa nuclear power station, there could be a limit to lower the core damage

  6. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  7. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 2, January 2007

    International Nuclear Information System (INIS)

    2006-08-01

    This newsletter reports on the training of cardiologists in radiation protection, IAEA's safety review services and the operational safety assessment review team (OSART), the international conference on management of spent fuel and the recent INSAG (International Nuclear Safety Group) publications. The IAEA has begun a major international initiative to train interventional cardiologists in radiation protection. Starting with the first course in May 2004, so far 6 regional and 3 national training courses have been conducted with the participation of over 400 health professionals putting the IAEA in a leading role in this area. A programme of two days' training has been developed, covering possible and observed radiation effects among patients and staff, international standards, dose management techniques, examples of good and bad practice and examples indicating prevention of possible injuries as a result of good practice in radiation protection. The training material is freely available on CD and will be placed on the Radiological Protection of Patients website at http://rpop.iaea.org/

  8. Hualong One's nuclear reactor core design and relative safety issues research

    Energy Technology Data Exchange (ETDEWEB)

    Yu, H., E-mail: yuhong_xing@126.com [Nuclear Power Inst. of China, Design and Research Sub-Inst., Chengdu, Sichuan (China)

    2015-07-01

    'Full text:' Hualong One, a third generation 1000MWe-class pressurized water reactor, is developed by China National Nuclear Cooperation (CNNC), based on the self-reliant technologies and experiences from China 40 years designing, construction, operation and maintenance of NPPs. In China, it has been approved to construct at Fuqing 5&6 and Fangchenggang 3&4. The Hualong One adopts advanced design features to dramatically enhance plant safety, economic efficiency and convenience of operation and maintenance. It consists of three loops with nominal thermal power output 3060 MWt and a 60-year design life. Its reactor core has 177 fuel assemblies, 18 month refueling interval (after initial cycle), and more than 15% thermal margin. It adopts low leakage loading pattern which can achieve better economy of the neutron, higher reactivity and lower radiation damage of pressure vessel. For the safety design, incorporating the feedback of Fukushima accident, the Hualong One has a combination of active and passive safety systems, a single station layout, double containment structure, and comprehensive implementation of defence-in-depth design principles. The new design features has been successfully evaluated to ensure that they enhance the performance and safety of Hualong One. Several experimental activates have been conducted, such as cavity injection and cooling system testing, passive containment heat removal system testing, and passive residual heat removal system of secondary side testing. The future improvements of Hualong reactor will focus on better economic core design and more reliable safety system. (author)

  9. A digest of the Nuclear Safety Division report on the Fukushima Dai-ichi accident seminar (4). Issues identified by the accident

    International Nuclear Information System (INIS)

    Moriyama, Kumiaki; Abe, Kiyoharu

    2013-01-01

    AESJ Nuclear Safety Division published 'Report on the Fukushima Dai-ichi Accident Seminar - what was wrong and what should been down in future-' which would be published as five special articles of the AESJ journal. The Fukushima Dai-ichi accident identified issues of several activities directly related with nuclear safety in the areas of safety design, severe accident management and safety regulations. PRA, operational experiences and safety research could not always contribute safety assurance of nuclear power plant so much. This article (4) summarized technical issues based on related facts of the accident as much as possible and discussed' what was wrong and what should be down in future'. Important issues were identified from defense-in-depth philosophy and lessons learned on safety design were obtained from accident progression analysis. Activities against external events and continuous improvements of safety standards based on latest knowledge were most indispensable. Strong cooperation among experts in different areas was also needed. (T. Tanaka)

  10. Framework of nuclear safety and safety assessment

    International Nuclear Information System (INIS)

    Furuta, Kazuo

    2007-01-01

    Since enormous energy is released by nuclear chain reaction mainly as a form of radiation, a great potential risk accompanies utilization of nuclear energy. Safety has been continuously a critical issue therefore from the very beginning of its development. Though the framework of nuclear safety that has been established at an early developmental stage of nuclear engineering is still valid, more comprehensive approaches are required having experienced several events such as Three Mile Island, Chernobyl, and JCO. This article gives a brief view of the most basic principles how nuclear safety is achieved, which were introduced and sophisticated in nuclear engineering but applicable also to other engineering domains in general. (author)

  11. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 3, April 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This newsletter reports on the manual for first responders to a radiological emergency, the IAEA's testing laboratory for radiation measurement, monitoring and protection, which is the first UN laboratory accredited to the international standard ISO17025, and the International Conference on Lessons Learned fro the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. The IAEA, in recognition of this critical need, has developed a Manual for First Responders to a Radiological Emergency with the objective to provide practical guidance for those responding within the first few hours of a radiological emergency. This guidance document is co-sponsored by the Comite technique international de prevention et d'extinction du feu (CTIF), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). The Manual for First Responders provides guidance in the form of action guides, instructions, and supporting data that can be easily applied by a State to build a basic capability to respond to a radiological emergency. The guidance also contains practical procedures and tools on the response to a radiological emergency again easily and quickly adaptable by Member States to prepare first responders to respond adequately to a radiological emergency. The Manual can be used for training purposes at the preparedness stage as well as during the response. The Policy and Programme Support Section (PPSS) within the Division of Radiation, Transport and Waste Security (NSRW) has been operating, for many years, a laboratory (the Testing Laboratory) for radiation safety monitoring of individuals and workplaces. The establishment of a quality management system, as required in the International Basic Safety Standards (the BSS), started in 2000 to cover all measurement methods of the laboratory. This system is based on the international standard ISO17025 (General requirements for the competence of testing and calibration laboratories). PPSS

  12. Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

    International Nuclear Information System (INIS)

    Little, C.A.

    1995-01-01

    The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author's responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A

  13. Issues and relationships among software standards for nuclear safety applications. Version 2.0

    International Nuclear Information System (INIS)

    Scott, J.A.; Preckshot, G.G.; Lawrence, J.D.; Johnson, G.L.

    1996-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the development of draft regulatory guides for selected software engineering standards. This report describes the results of the initial task in this work. The selected software standards and a set of related software engineering standards were reviewed, and the resulting preliminary elements of the regulatory positions are identified in this report. The importance of a thorough understanding of the relationships among standards useful for developing safety-related software is emphasized. The relationship of this work to the update of the Standard Review Plan is also discussed

  14. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  15. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  16. WNA's worldwide overview on front-end nuclear fuel cycle growth and health, safety and environmental issues.

    Science.gov (United States)

    Saint-Pierre, Sylvain; Kidd, Steve

    2011-01-01

    This paper presents the WNA's worldwide nuclear industry overview on the anticipated growth of the front-end nuclear fuel cycle from uranium mining to conversion and enrichment, and on the related key health, safety, and environmental (HSE) issues and challenges. It also puts an emphasis on uranium mining in new producing countries with insufficiently developed regulatory regimes that pose greater HSE concerns. It introduces the new WNA policy on uranium mining: Sustaining Global Best Practices in Uranium Mining and Processing-Principles for Managing Radiation, Health and Safety and the Environment, which is an outgrowth of an International Atomic Energy Agency (IAEA) cooperation project that closely involved industry and governmental experts in uranium mining from around the world. Copyright © 2010 Health Physics Society

  17. Nuclear power and nuclear safety 2009

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Nystrup, P.E.; Thorlaksen, B.

    2010-05-01

    The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

  18. Nuclear power and safety

    International Nuclear Information System (INIS)

    Chidambaram, R.

    1992-01-01

    Some aspects of safety of nuclear power with special reference to Indian nuclear power programme are discussed. India must develop technology to protect herself from the adverse economic impact arising out of the restrictive regime which is being created through globalization of safety and environmental issues. Though the studies done and experience gained so far have shown that the PHWR system adopted by India has a number of superior safety features, research work is needed in the field of operation and maintenance of reactors and also in the field of reactor life extension through delaying of ageing effects. Public relations work must be pursued to convince the public at large of the safety of nuclear power programme. The new reactor designs in the second stage of evolution are based on either further improvement of existing well-proven designs or adoptions of more innovative ideas based on physical principles to ensure a higher level of safety. The development of Indian nuclear power programme is characterised by a balanced approach in the matter of assuring safety. Safety enforcement is not just looked upon as a pure administrative matter, but experts with independent minds are also involved in safety related matters. (M.G.B.)

  19. International Conference on Topical Issues in Nuclear Installation Safety: Defence in Depth — Advances and Challenges for Nuclear Installation Safety. Proceedings of an International Conference held in Vienna, Austria, 21-24 October 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-10-15

    The fifth International Conference on Topical Issues in Nuclear Installation Safety was dedicated to the defence in depth (DID) concept which is fundamental to the safety of nuclear installations. The main focus of the conference was to foster the exchange of information on the implementation of DID and the associated challenges. This CD-ROM contains the papers presented at the conference as well as the summary and conclusions, including recommendations for further actions to strengthen DID and its implementation.

  20. International conference on topical issues in nuclear installation safety: Continuous improvement of nuclear safety in a changing world. Book of contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Papers presented at this conference where devoted to the following NPP safety related topical issues: Changing environments - coping with diversity and globalisation; Operating experience - managing changes effectively; Regulatory management systems - adapting to changes in the environment; Long term operations - maintaining safety margins while extending plant lifetime.

  1. Nuclear safety and regulation

    International Nuclear Information System (INIS)

    Kim, Hho Jung

    2000-03-01

    This book contains 12 chapters, which are atom and radiation, nuclear reactor and kinds of nuclear power plant, safeguard actuation system and stability evaluation for rock foundation of nuclear power plant, nuclear safety and principle, safety analysis and classification of incident, probabilistic safety assessment and major incident, nuclear safety regulation, system of nuclear safety regulation, main function and subject of safety regulation in nuclear facilities, regulation of fuel cycle and a nuclear dump site, protection of radiation and, safety supervision and, safety supervision and measurement of environmental radioactivity.

  2. Progress of nuclear safety research. 2001

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-10-01

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

  3. Nuclear power and nuclear safety 2006

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2007-04-01

    The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

  4. Nuclear power and nuclear safety 2004

    International Nuclear Information System (INIS)

    2005-03-01

    The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  5. Nuclear power and nuclear safety 2005

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampman, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2006-03-01

    The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  6. Nuclear power and nuclear safety 2008

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.

    2009-06-01

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  7. Nuclear safety management at the Wolsong NGS

    Energy Technology Data Exchange (ETDEWEB)

    Bong-Seob, Han [Korea Electric Power Corp., Wolson NPP no. 1 and 2 (Korea, Republic of)

    1997-12-01

    Nuclear safety management at the Wolsong nuclear power plant is described, including the following issues: site selection; plant history; operational goals; operational guidelines; reactor safety; safety training; plant maintenance; management of plant equipment lifetime; future tasks.

  8. Nuclear safety management at the Wolsong NGS

    International Nuclear Information System (INIS)

    Han Bong-Seob

    1997-01-01

    Nuclear safety management at the Wolsong nuclear power plant is described, including the following issues: site selection; plant history; operational goals; operational guidelines; reactor safety; safety training; plant maintenance; management of plant equipment lifetime; future tasks

  9. Transient analysis for resolving safety issues

    International Nuclear Information System (INIS)

    Chao, J.; Layman, W.

    1987-01-01

    The Nuclear Safety Analysis Center (NSAC) has a Generic Safety Analysis Program to help resolve high priority generic safety issues. This paper describes several high priority safety issues considered at NSAC and how they were resolved by transient analysis using thermal hydraulics and neutronics codes. These issues are pressurized thermal shock (PTS), anticipated transients without scram (ATWS), steam generator tube rupture (SGTR), and reactivity transients in light of the Chernobyl accident

  10. Seismic qualification of equipment in operating nuclear power plants: Unresolved Safety Issue A-46

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46. In addition, the collection and review of seismic experience data and existing seismic test data are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experienced data base. The principal technical finding of USI A-46 is that seismic experience data, supplemented by existing seismic test data, applied in accordance with the guidelines developed, can be used to verify the seismic adequacy of mechanical and electrical equipment in operating nuclear plants. Explicit seismic qualification should be required only if seismic experience data or existing test data on similar components cannot be shown to apply

  11. Nuclear Safety. 1997

    International Nuclear Information System (INIS)

    1998-01-01

    A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

  12. Stakeholder Involvement in nuclear issues. INSAG-20. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    in the nuclear enterprise. We believe that full and open engagement among the various stakeholders will serve to improve decision making, as well as advance the common interest in assuring the safety of nuclear installations

  13. Nuclear safety. Improvement programme

    International Nuclear Information System (INIS)

    2000-01-01

    In this brochure the improvement programme of nuclear safety of the Mochovce NPP is presented in detail. In 1996, a 'Mochovce NPP Nuclear Safety Improvement Programme' was developed in the frame of unit 1 and 2 completion project. The programme has been compiled as a continuous one, with the aim to reach the highest possible safety level at the time of commissioning and to establish good preconditions for permanent safety improvement in future. Such an approach is in compliance with the world's trends of safety improvement, life-time extension, modernisation and nuclear station power increase. The basic document for development of the 'Programme' is the one titled 'Safety Issues and their Ranking for WWER 440/213 NPP' developed by a group of IAEA experts. The following organisations were selected for solution of the safety measures: EUCOM (Consortium of FRAMATOME, France, and SIEMENS, Germany); SKODA Prague, a.s.; ENERGOPROJEKT Prague, a.s. (EGP); Russian organisations associated in ATOMENERGOEXPORT; VUJE Trnava, a.s

  14. Nuclear safety

    International Nuclear Information System (INIS)

    Arnott, D.

    1981-01-01

    Dr Arnott, scientific consultant to PANDORA, emphasises our lack of knowledge of the behaviour of highly active radioactive wastes, particularly effluents, and their characteristics. He proposes that they should be stored, preferably in a solidified state, until our knowledge allows their safe disposal. Political aspects and government policies are discussed and human fallibility is stressed. The nuclear establishment and nuclear power programme are severely criticised. (U.K.)

  15. Nuclear power and nuclear safety 2011

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Aage, H.K.; Kampmann, D.; Nystrup, P.E.; Thomsen, J.

    2012-07-01

    The report is the ninth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2011 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the Fukushima accident. (LN)

  16. Nuclear power and nuclear safety 2012

    International Nuclear Information System (INIS)

    Lauritzen, B.; Nonboel, E.; Israelson, C.; Kampmann, D.; Nystrup, P.E.; Thomsen, J.

    2013-11-01

    The report is the tenth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is prepared in collaboration between DTU Nutech and the Danish Emergency Management Agency. The report for 2012 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the results of the EU stress test. (LN)

  17. Nuclear Safety Review for 2014

    International Nuclear Information System (INIS)

    2014-07-01

    The Nuclear Safety Review 2014 focuses on the dominant nuclear safety trends, issues and challenges in 2013. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: strengthening safety in nuclear installations; improving radiation, transport and waste safety; enhancing emergency preparedness and response (EPR); improving regulatory infrastructure and effectiveness; and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards, and activities relevant to the Agency’s safety standards. The global nuclear community has made steady and continuous progress in strengthening nuclear safety in 2013, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”) and reported in Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2013/8-GC(57)/INF/5), and the Supplementary Information to that report and Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2014/2). • Significant progress continues to be made in several key areas, such as assessments of safety vulnerabilities of nuclear power plants (NPPs), strengthening of the Agency’s peer review services, improvements in EPR capabilities, strengthening and maintaining capacity building, and protecting people and the environment from ionizing radiation. The progress that has been made in these and other areas has contributed to the enhancement of the global nuclear safety framework. • Significant progress has also been made in reviewing the Agency’s safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on vitally important areas such as design and operation of NPPs, protection of NPPs against severe accidents, and EPR. • The Agency continued to

  18. Managing nuclear safety at Point Lepreau

    Energy Technology Data Exchange (ETDEWEB)

    Paciga, J [New Brunswick Power, Point Lepreau NGS, PQ (Canada)

    1997-12-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance).

  19. Managing nuclear safety at Point Lepreau

    International Nuclear Information System (INIS)

    Paciga, J.

    1997-01-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance)

  20. Uranium and nuclear issues

    International Nuclear Information System (INIS)

    1983-01-01

    This seminar focussed on the major issues affecting the future of the entire nuclear fuel cycle. In particular it covered issues bearing on the formation of public policy in relation to the use of uranium as an energy source: economic risk, industrial risks, health effects, site selection, environmental issues, and public acceptance

  1. Assessment of basic safety issues

    International Nuclear Information System (INIS)

    Queniart, D.

    1996-01-01

    Work on the French-German common safety approach for future nuclear power plants continued in 1994 to allow for more detailed discussion of some major issues, taking into account the options provided by the industry for the EPR (European Pressurized water Reactor) project, as described in the document entitled 'Conceptual Safety Features Review File'. Seven meetings of a GPR/RSK advisory experts subgroup, six GPR/RSK plenary sessions and six meetings of the safety authorities (DFD) dealt with the following topics: design of the systems and use of probabilistic approaches, application of a 'break preclusion' approach to the main primary pipings, protection against external hazards (aircraft crashes, explosions, earthquakes), provisions with respect to accidents involving core melt and to containment design, radiological consequences of reference accidents and accidents involving core melt at low pressure. The important aspects of the joint policy are recalled in the presentation. The whole set of GPR/RSK recommendations were agreed by the French and German safety authorities during the DFD meetings of 1994 and early 1995. The utilities decided to begin the basic design phase in February, 1995. Work is now continuing to develop the common French-German approach for future nuclear power plants, in the same way as before. In 1995, this mainly covers the design of the containment and of the systems, but also new issues such as the protection against secondary side overpressurization, radiological protection of workers and radioactive wastes. (J.S.). 3 figs., 1 tab

  2. On the road to new nuclear safety

    International Nuclear Information System (INIS)

    Kovacs, Zoltan; Novakova, Helena; Spenlinger, Robert

    2013-01-01

    The article describes the issue of nuclear safety of nuclear power plants and major factors affecting nuclear safety, discusses the consequences of the Fukushima-Daiichi accident, and outlines the advanced concept of nuclear safety which extends the current regulatory requirements for plant safety. This new concept should be adopted globally to prevent occurrences having similar consequences worldwide. The tasks of this new nuclear safety concept are discussed. (orig.)

  3. Safety culture issues and perspectives

    International Nuclear Information System (INIS)

    Dahlgren Persson, K.

    1999-01-01

    Strong economic performance in the nuclear business must be driven by excellence in nuclear operation and uncompromising safety. If this balance is not maintained then the ability of the utility to manage this technology safely will justifiably be challenged by the public and the nuclear safety regulator. Experience has shown that once nuclear installation performance has deteriorated to a level at which there are serious regulatory concerns about the adequacy of nuclear safety, then the magnitude and difficulty of the effort required to recover performance are such that continued viability of the organisation comes into question. Thus from both the perspective of individual utilities and the nuclear industry as a whole, it is extremely important to be able to detect shortcomings and deterioration in safety management performance before it becomes a serious concern, and to put effective corrective actions in place to restore and maintain performance at high levels. Following this theme and stimulated by the Canadian Government, senior representatives of utilities and regulators from Canada, United States, Sweden and Agency staff discussed common factors from recent cases involving safety management problems and subsequent recovery processes with a view to determining the need for further work to help prevent such difficulties in the future. From the working group discussion it was concluded that in most cases considered, the utility senior executives from, in some cases the Board of Directors and Chief Executive Officer, to senior nuclear site executives, did not have the nuclear business acumen or provide the leadership necessary for the management of a successful nuclear programme. Nuclear business acumen is the insight, knowledge and ability to manage the unique interaction between the technology, economics, human factors and safety in a changing nuclear generation environment. Senior utility management failed to recognize, within their suite of performance

  4. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 13, December 2009

    International Nuclear Information System (INIS)

    2009-12-01

    The current issue presents information about the following activities: Highlights of the 53rd IAEA General Conference, 14-18 September 2009. Current status of the Building, Testing and Using the Response Assistance Network (RANET). 10th Meeting of the ANSN Steering Committee. The document also gives an overview on International Physical Protection Advisory Service (IPPAS)

  5. Nuclear criticality safety guide

    International Nuclear Information System (INIS)

    Pruvost, N.L.; Paxton, H.C.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators

  6. Nuclear criticality safety guide

    Energy Technology Data Exchange (ETDEWEB)

    Pruvost, N.L.; Paxton, H.C. [eds.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

  7. Safety of nuclear installations

    International Nuclear Information System (INIS)

    1991-01-01

    In accordance with the Nuclear Energy Act, a Licence may only be issued if the precautions required by the state of the art have been taken to prevent damage resulting from the construction and operation of the installation. The maximum admissible body doses in the area around the installation which must be observed in planning constructional and other technical protective measures to counter accidents in or at a nuclear power station (accident planning values, are established). According to the Radiological Protection Ordinance the Licensing Authority can consider these precautions to have been taken if, in designing the installation against accidents, the applicant has assumed the accidents which, according to the Safety Criteria and Guidelines for Nuclear Power Stations published in the Federal Register by the Federal Minister of the Interior after hearing the competent senior state authorities, must determine the design of a nuclear power station. On the basis of previous experience from safety analysis, assessment and operation of nuclear power stations, the accident guidelines published here define which accidents are determinative for the safety-related design of PWR power stations and what verification -particularly with regard to compliance with the accident planning values of the Radiological Protection Ordinance -must be provided by the applicant. (author)

  8. Hydrogen safety in nuclear power - issues and measures. Preparing 'handbook for improved hydrogen safety in nuclear power'

    International Nuclear Information System (INIS)

    Ogawa, Tooru; Nakajima, Kiyoshi; Hino, Ryutaro

    2015-01-01

    In response to hydrogen explosion at the reactor building of TEPCO Fukushima Daiichi Nuclear Power Station, the common understanding among researchers in various fields has been required for the chain of various events surrounding hydrogen in case of the accident of a light water reactor. The group composed of specialists of nuclear power and gas combustion/explosion from universities, nuclear power equipment manufacturers, business interests, and nuclear power institutes is promoting the preparation work of 'Handbook for upgrading the safety of hydrogen measures related to nuclear power,' which is scheduled to be published in the end of 2015. The main themes dealt with in the handbook are as follows; (1) severe accident management and hydrogen control, (2) hydrogen combustion phenomena to be considered, (3) behavior of air - water vapor - hydrogen system, (4) passive autocatalytic recombiner (PAR) / igniter / containment spray, and (5) water-containing waste management. This paper introduces the outline of these movements and latest achievements. (A.O.)

  9. NRC program for the resolution of generic issues related to nuclear power plants. (Includes plans for the resolution of ''unresolved safety issues'' pursuant to Section 210 of the Energy Reorganization Act of 1974, as amended)

    International Nuclear Information System (INIS)

    1977-12-01

    This report provides a description of the Nuclear Regulatory Commission's Program for the Resolution of Generic Issues Related to Nuclear Power Plants. The NRC program is of considerably broader scope than the ''Unresolved Safety Issues Plan'' required by Section 210. The NRC program does include plans for the resolution of ''Unresolved Safety Issues''; however, in addition, it includes generic tasks for the resolution of environmental issues, for the development of improvements in the reactor licensing process and for consideration of less conservative design criteria or operating limitations in areas where over conservatisms may be unnecessarily restrictive or costly

  10. Nuclear safety in Spain

    International Nuclear Information System (INIS)

    Caro, R.

    1988-01-01

    Control and monitoring of all Spanish nuclear facilities was first carried out by the Department of Nuclear Safety of the Junta de Energia Nuclear established by the Nuclear Energy Act in 1964. Later, following the example of other Western countries, it was concluded that regulations and monitoring of nuclear energy on one hand and its promotion and development on the other should not be done by the same national body. Therefore, the Consejo de Seguridad Nuclear (CSN) was created in 1980, as the sole national body responsible for controlling the safety of nuclear installations, and radiological protection. The CSN has five members, one chairman and four comissioners, required to be independent and therefore with politically objective criteria, internationally acknowledged technical capability, and free from other duties and responsibilities. For this purpose the Chairman has been given the status of Minister and the commissioners that of Secretary of State. They serve for six years, after being accepted by Parliament by a majority of at least 3/5 of the votes, and are called upon to report to Parliament at least twice a year on nuclear safety and radiological protection in the country. A complete report on those issues is presented to Parliament, becoming a politic document as from that moment. To prepare that report (basically a summary of CSN activities) and, in general, to fulfill all its tasks, the CSN has a staff of some 300, about 50% being technical. CSN activities cover: 1. Standards; 2. Licences; 3. Research; 4. Environment; 5. Information; and 6. International Relations

  11. Improving versus maintaining nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted. Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

  12. Safety and licensing issues for Indian PHWRs

    International Nuclear Information System (INIS)

    Srinivasan, G.R.; Das, M.

    1997-01-01

    India has achieved competency in design, construction, commissioning and operation of Pressurized Heavy Water Reactor based Nuclear Power Plants and has completed more than 120 reactor operating years with an extremely satisfactory safety record. In this paper, the safety management in NPCIL and operational safety aspects are discussed, licensing and regulatory approach is described and some of the main safety issues for Indian PHWRs are brought out. (author)

  13. International Aspects of Nuclear Safety

    International Nuclear Information System (INIS)

    Lash, T.R.

    2000-01-01

    Even though not all the world's nations have developed a nuclear power industry, nuclear safety is unquestionably an international issue. Perhaps the most compelling proof is the 1986 accident at Chornobyl nuclear power plant in what is now Ukraine. The U.S. Department of Energy conducts a comprehensive, cooperative effort to reduce risks at Soviet-designed nuclear power plants. In the host countries : Armenia, Ukraine, Russia, Bulgaria, the Czech Republic, Hungary, Lithuania, Slovakia, and Kazakhstan joint projects are correcting major safety deficiencies and establishing nuclear safety infrastructures that will be self-sustaining.The U.S. effort has six primary goals: 1. Operational Safety - Implement the basic elements of operational safety consistent with internationally accepted practices. 2. Training - Improve operator training to internationally accepted standards. 3. Safety Maintenance - Help establish technically effective maintenance programs that can ensure the reliability of safety-related equipment. 4. Safety Systems - Implement safety system improvements consistent with remaining plant lifetimes. 5. Safety Evaluations - Transfer the capability to conduct in-depth plant safety evaluations using internationally accepted methods. 6. Legal and Regulatory Capabilities - Facilitate host-country implementation of necessary laws and regulatory policies consistent with their international treaty obligations governing the safe use of nuclear power

  14. Hydrogen peroxide safety issues

    International Nuclear Information System (INIS)

    Conner, W.V.

    1993-01-01

    A literature survey was conducted to review the safety issues involved in handling hydrogen peroxide solutions. Most of the information found in the literature is not directly applicable to conditions at the Rocky Flats Plant, but one report describes experimental work conducted previously at Rocky Flats to determine decomposition reaction-rate constants for hydrogen peroxide solutions. Data from this report were used to calculate decomposition half-life times for hydrogen peroxide in solutions containing several decomposition catalysts. The information developed from this survey indicates that hydrogen peroxide will undergo both homogeneous and heterogeneous decomposition. The rate of decomposition is affected by temperature and the presence of catalytic agents. Decomposition of hydrogen peroxide is catalyzed by alkalies, strong acids, platinum group and transition metals, and dissolved salts of transition metals. Depending upon conditions, the consequence of a hydrogen peroxide decomposition can range from slow evolution of oxygen gas to a vapor, phase detonation of hydrogen peroxide vapors

  15. Global nuclear safety culture

    International Nuclear Information System (INIS)

    1997-01-01

    As stated in the Nuclear Safety Review 1996, three components characterize the global nuclear safety culture infrastructure: (i) legally binding international agreements; (ii) non-binding common safety standards; and (iii) the application of safety standards. The IAEA has continued to foster the global nuclear safety culture by supporting intergovernmental collaborative efforts; it has facilitated extensive information exchange, promoted the drafting of international legal agreements and the development of common safety standards, and provided for the application of safety standards by organizing a wide variety of expert services

  16. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  17. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission's dispositions

    International Nuclear Information System (INIS)

    Watanabe, Norio; Suzudo, Tomoaki

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission's (USNRC's) responses to the recommendations made by the NRC's study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC's dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  18. 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.)

  19. Nuclear safety in France

    International Nuclear Information System (INIS)

    Servant, J.

    1979-12-01

    The main areas of nuclear safety are considered in this paper, recalling the laws and resolutions in force and also the appropriate authority in each case. The following topics are reviewed: radiological protection, protection of workers, measures to be taken in case of an accident, radioactive effluents, impact on the environment of non-nuclear pollution, nuclear plant safety, protection against malicious acts, control and safeguard of nuclear materials, radioisotopes, transport of radioactive substances, naval propulsion, waste management, nuclear plant decommissioning and export of nuclear equipment and materials. Finally, the author describes the role of the general Secretariat of the Interdepartmental Committee on Nuclear Safety

  20. Nuclear safety in France

    International Nuclear Information System (INIS)

    Queniart, D.

    1989-12-01

    This paper outlines the organizational and technical aspects of nuclear safety in France. From the organization point of view, the roles of the operator, of the safety authority and of the Institute for Protection and Nuclear Safety are developed. From the technical viewpoint, the evolution of safety since the beginning of the French nuclear programme, the roles of deterministic and probabilistic methods and the severe accident policy (prevention and mitigation, venting containment) in France are explained

  1. Status of National Nuclear Infrastructure Development (NG-T-3.2). Basis for Evaluation - Legal, safety, security, safeguards issues

    International Nuclear Information System (INIS)

    Yllera, Javier

    2010-01-01

    A framework for achieving high levels of nuclear safety and security worldwide Builds upon: Legal Instruments; Use of IAEA SSs and security guidance; Harmonization of national regulations; Exchange of knowledge, experiences & regulatory practices and Multinational cooperation and safety reviews. The IAEA is the depository of many key international conventions and legal agreements. All countries with operating nuclear power plants are now parties to the Convention. The main objective of Convention on Nuclear Safety is to achieve and maintain a high level of nuclear safety worldwide through the enhancement of national measures and international cooperation including, where appropriate, safety related technical co-operation. All practical efforts must be made to prevent and mitigate nuclear or radiation accidents. The primary means of preventing and mitigating the consequences of accidents is “defence in depth”. Safety assessments are to be carried out and documented by the organization responsible for operating the facility, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorization process. Licensing process must be well-defined, clear, transparent and traceable. The public should be given an opportunity to provide their views during certain steps of the licensing process

  2. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    1999-01-01

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  3. A prioritization of generic safety issues

    International Nuclear Information System (INIS)

    Emrit, R.; Riggs, R.; Milstead, W.; Pittman, J.

    1991-07-01

    This report presents the priority rankings for generic safety issues and related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The report focuses on the prioritization of generic safety issues. Issues primarily concerned with the licensing process or environmental protection and not directly related to safety have been excluded from prioritization. The prioritized issues include: TMI Action Plan items under development; previously proposed issues covered by Task Action Plans, except issues designated as Un-resolved Safety Issues (USIs) which had already been assigned high priority; and newly-proposed issues. Future supplements to this report will include the prioritization of additional issues. The safety priority rankings are High, Medium, Low, and Drop and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. 1310 refs

  4. Nuclear health and safety

    International Nuclear Information System (INIS)

    1991-04-01

    Numerous environmental, safety, and health problems found at other Department of Energy (DOE) defense nuclear facilities precipitated a review of these conditions at DOE's contractor-operated Pantex Plant, where our nation's nuclear weapons are assembled. This book focuses the review on examining key safety and health problems at Pantex and determining the need for external safety oversight of the plant

  5. Nuclear criticality safety guide

    International Nuclear Information System (INIS)

    Ro, Seong Ki; Shin, Hee Seong; Park, Seong Won; Shin, Young Joon.

    1997-06-01

    Nuclear criticality safety guide was described for handling, transportation and storage of nuclear fissile materials in this report. The major part of the report was excerpted frp, TID-7016(revision 2) and nuclear criticality safety written by Knief. (author). 16 tabs., 44 figs., 5 refs

  6. Progress of nuclear safety research-2004

    International Nuclear Information System (INIS)

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

    2005-03-01

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

  7. Evaluation on safety issues of SMART

    International Nuclear Information System (INIS)

    Kim, W. S.; Seol, K. W.; Yoon, Y. K.; Lee, J. H.

    2001-01-01

    Safety issues on the SMART were evaluated in the light of the compliance with the Ministerial Ordinance of Technical Requirements applying to Nuclear Installations, which was recently revised. Evaluation concludes that regulatory requirements associated with following items have to be developed as the licensing criteria for the SMART: (1) proving the safety of design or materials different form existing reactors; (2) coping with beyond design basis accidents; (3) rulemaking on the safety of reactor safeguard vessel ; (4) ensuring integrity of steam generator tubes; and (5) classifying equipment based on their safety significance. Appropriate actions including implementation of new requirements under development should be taken for safety issues such as diversity of reactivity control and in-service inspection of steam generator tubes that are not complied with the current Technical Requirements. Safety level of the SMART design will be evaluated further by the more detailed assessment according to the Technical Requirements, and additional safety issues will be identified and resolved, if it necessary

  8. Nuclear waste issue

    International Nuclear Information System (INIS)

    Ryhanen, V.

    2000-01-01

    A prerequisite for future use of nuclear energy in electricity production is safe management of the radioactive wastes generated by nuclear power industry. A number of facilities have been constructed for different stages of nuclear waste management around the world, for example for conditioning of different kind of process wastes and for intermediate storage of spent nuclear fuel. Difficulties have often been encountered particularly when trying to advance plans for final stage of waste management, which is permanent disposal in stable geological formations. The main problems have not been technical, but poor public acceptance and lack of necessary political decisions have delayed the progress in many countries. However, final disposal facilities are already in operation for low- and medium-level nuclear wastes. The most challenging task is the development of final disposal solutions for long-lived high-level wastes (spent fuel or high-level reprocessing waste). The implementation of deep geological repositories for these wastes requires persistent programmes for technology development, siting and safety assessments, as well as for building public confidence in long-term safety of the planned repositories. Now, a few countries are proceeding towards siting of these facilities, and the first high-level waste repositories are expected to be commissioned in the years 2010 - 2020. (author)

  9. Canada's domestic nuclear issues

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The Interfaith Program for Public Awareness of Nuclear Issues (IPPANI) is a committee of representatives of religious groups in Toronto, a group of people concerned about the moral and ethical implications of the operation of Canada's nuclear industry and of its exports to other countries. The faith groups represented are the Anglican Diocese of Toronto, the Baha'i Community of Canada, the Jewish Community of Toronto, the Roman Catholic Archdiocese of Toronto and the United Church of Canada Toronto Conference. Wishing to encourage the Canadian government to enquire into this broad question, the faith groups established IPPANI and assigned to it the task of enhancing their knowledge of the nuclear industry. IPPANI was to develop an effective set of questions to be placed before governments and to promote public discussion so that governments might become more responsive to these issues

  10. Enhancing operational nuclear safety

    International Nuclear Information System (INIS)

    Sengoku, Katsuhisa

    2008-01-01

    Since Chernobyl, the dictum A n accident anywhere is an accident everywhere i s a globally shared perception. The paper presents challenges to the international nuclear community: globalization, sustainable and dynamic development, secure, safe and clean energy supply, nuclear r enaissance , public concern for nuclear safety, nuclear security, and technology and management. Strong national safety infrastructures and international cooperation are required to maintain a high level of nuclear safety and security worldwide. There is an increasing number of countries thinking of going nuclear: Morocco, Indonesia, Iran, Poland, Turkey, Bangladesh, Egypt, Vietnam, Chile, Nigeria, Malaysia, Thailand, Uruguay, Tunisia, Algeria. Another serious incident will jeopardize the prospect of nuclear renaissance. Safety and security are preconditions for countries newly introducing NPP as well as for those with mature nuclear programmes. The Global Nuclear Safety Regime (GNSR) is referred to as the institutional, legal and technical framework to achieve worldwide implementation of the safety of nuclear installations. At the top of the framework is the Convention on Nuclear Safety which covers the nuclear power plants. The convention has 56 contracting parties which meet triennially where national reports are presented and subject to the review of peers. The International Atomic Energy Agency (IAEA) undertakes a programme to foster the GNSR through the establishment of IAEA safety standards and related publications. The programme provides for the application of standards for the (1) safety of nuclear installations, (2) safety of radioactive sources, (3) safe transport of radioactive material and (4) management of radioactive waste. It also provides for the security of nuclear installations, nuclear material and radioactive material. The safety standards hierarchy is as follows: safety fundamental, safety requirements and safety guides. The safety fundamentals are the bases for IAEA

  11. 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

  12. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1982-06-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the Office of Resource Management. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  13. Report of the review of WWER-1000 safety issues resolution at Temelin nuclear power plant, Temelin, Czech Republic 11 to 15 March 1996

    International Nuclear Information System (INIS)

    Almeida, C.; Hoehn, J.; Seiberling, R.; Chambon, J.L.; Fil, N.S.; Munoz, A.; Roennberg, G.; Wenk, W.

    1996-01-01

    At the request of the Government of the Czech Republic, the IAEA conducted, in the period of 11-15 March 1996, a mission to review the resolution of WWER-1000 safety issues at Temelin NPP. These safety issues have been identified for WWER-1000 model 320 reactors and ranked according to their importance to safety in the frameworks of the IAEA Extrabudgetary Programme on Safety of WWER and RBMK Nuclear Power Plants. The Temelin NPP is a WWER-1000 and was originally designed according to standards of the former Soviet Union. After a series of reviews in the 1980s, a decision was taken by the Temelin NPP management to upgrade the design of Temelin, including the supply of fuel and instrumentation and control by a western company. The objective of the mission was to review the response of Temelin to the safety issues identified by the IAEA. The mission assessed the current Temelin design, including proposed modifications and plans for operation at Temelin, in the light of the IAEA recommendations for each relevant issue. The present report contains the mission's general conclusions and recommendations and an overview of the review performed in each topical area. The attachment contains a brief summary of the discussions on each individual safety issue and associated conclusions and recommendations. 3 refs

  14. Radiation safety in nuclear medicine procedures

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

    2017-03-15

    Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

  15. Radiation safety in nuclear medicine procedures

    International Nuclear Information System (INIS)

    Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun

    2017-01-01

    Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed

  16. Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

    International Nuclear Information System (INIS)

    1991-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  17. Teaching nuclear issues

    International Nuclear Information System (INIS)

    Hicks, D.W.

    1986-01-01

    This paper is based on the assumption that the nuclear debate, both globally and within Britain, is one of critical importance in the late twentieth century and that it should therefore, at some juncture, be explored as part of the school curriculum. An essential part of 'good education' in a democratic society is to teach young people how to think about such an issue, but not what to think about it. This paper attempts to set out some of the key issues and dilemmas in relation to what we may call 'nuclear education'. It perhaps asks more questions than it gives answers, but they are all essential questions which teachers must ask themselves if they are to teach sensitively about these matters. Some of these questions are given as examples. (author)

  18. Safety goals for nuclear power

    International Nuclear Information System (INIS)

    Fischhoff, B.

    1984-02-01

    The key policy question in managing hazardous technologies is often some variant of How safe is safe enough. The US Nuclear Regulatory Commission has recently broached this topic by adopting safety goals defining acceptable risk levels for nuclear power plants. These goals are analyzed here with a general theory of standard setting (Fischhoff, 1983) which asks: (1) Are standards an appropriate policy tool in this case. (2) Can the Commission's safety philosophy be defended. (3) Do the operational goals capture that philosophy. The anlaysis shows the safety goals proposal to be sophisticated in some respects, incomplete in others. More generally, it points to difficulties with the concept of acceptable risk and any attempt to build policy instruments around it. Although focused on the NRC's safety goals, the present analysis is a prototype of what can be learned by similarly detailed consideration of other standards, not only for nuclear power but also for other hazardous technologies, as well as for issues unrelated to safety

  19. Status of Nuclear Safety evaluation in China

    International Nuclear Information System (INIS)

    Tian Jiashu

    1999-01-01

    Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

  20. Recent Activities on Global Nuclear Safety Regime

    International Nuclear Information System (INIS)

    Cho, Kun-Woo; Park, Jeong-Seop; Kim, Do-Hyoung

    2006-01-01

    Recently, rapid progress on the globalization of the nuclear safety issues is being made in IAEA (International Atomic Energy Agency) and its member states. With the globalization, the need for international cooperation among international bodies and member states continues to grow for resolving these universal nuclear safety issues. Furthermore, the importance of strengthening the global nuclear safety regime is emphasized through various means, such as efforts in application of IAEA safety standards to all nuclear installations in the world and in strengthening the code of conduct and the convention on nuclear safety. In this regards, it is important for us to keep up with the activities related with the global nuclear safety regime as an IAEA member state and a leading country in nuclear safety regulation

  1. Evaluation of water-hammer experience in nuclear power plants. Technical findings relevant to Unresolved Safety Issue A-1

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1983-05-01

    This report summarizes key technical findings relevant to the Unresolved Safety Issue A-1, Water Hammer. These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer occurrences. It should also be noted that this report does not represent a substitute for current rules and regulations

  2. Evaluation of water hammer occurrence in nuclear power plants: technical findings relevant to unresolved safety issue A-1

    International Nuclear Information System (INIS)

    1984-03-01

    This report, which includes responses to public comments, summarizes key technical findings relevant to the Unresolved Safety Issue A-1, Water Hammer. These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer occurrences. This report does not represent a substitute for current rules and regulations

  3. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013

    International Nuclear Information System (INIS)

    2014-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  4. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for environment protection). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  5. Nuclear safety in perspective

    DEFF Research Database (Denmark)

    Andersson, K.; Sjöberg, B.M.D.; Lauridsen, Kurt

    2003-01-01

    The aim of the NKS/SOS-1 project has been to enhance common understanding about requirements for nuclear safety by finding improved means of communicat-ing on the subject in society. The project, which has been built around a number of seminars, wassupported by limited research in three sub......-projects: Risk assessment Safety analysis Strategies for safety management The report describes an industry in change due to societal factors. The concepts of risk and safety, safety management and systems forregulatory oversight are de-scribed in the nuclear area and also, to widen the perspective, for other...

  6. History of nuclear power plants safety in France (1945-2000) - Engineer techniques, expert evaluation, topical issue

    International Nuclear Information System (INIS)

    Foasso, Cyrille

    2003-01-01

    This doctoral dissertation relates the history of the mastery of risks in civil nuclear plants in France. Since 1960, it's known as the 'surete nucleaire'. Over a fifty-year period separating the discovery or the atomic fission and its industrial application on a large scale this PhD shows which technical means were used over the years by engineers to handle this risk which is said to be huge. It also studies the various processes in expert evaluation and in decision making elaborated to evaluate if the risk was acceptable or not. Beyond the conflicts between nuclear advocates and opponents, this thesis shows how ever among nuclear engineer the growing distinction between roles (promoters, experts and controlling authorities) and the various jobs (designers, builders and plant operators) triggered different estimations as far as the methods to obtain a satisfactory safety. Thanks to the progress of knowledge through research programs, thanks to the lessons drawn from the functioning or dysfunction of nuclear plants, thanks to the reinforcement of regulations (which more or less reflects the public's opinion concerning this industry) the safety has progressively improved. Thus, this historical study is multiple: a technical history of technology, a history of scientific, industrial and administrative organization, a social history and finally an international and comparative history since the nuclear energy history quickly developed beyond national boundaries. (author) [fr

  7. Safety of nuclear ships

    International Nuclear Information System (INIS)

    1978-01-01

    Interest in the utilization of nuclear steam supply systems for merchant ships and icebreakers has recently increased considerably due to the sharp rise in oil prices and the continuing trend towards larger and faster merchant ships. Canada, for example, is considering construction of an icebreaker in the near future. On the other hand, an accident which could result in serious damage to or the sinking of a nuclear ship is potentially far more dangerous to the general public than a similar accident with a conventional ship. Therefore, it was very important to evaluate in an international forum the safety of nuclear ships in the light of our contemporary safety philosophy, taking into account the results of cumulative operating experience with nuclear ships in operation. The philosophy and safety requirement for land-based nuclear installations were outlined because of many common features for both land-based nuclear installations and nuclear ships. Nevertheless, essential specific safety requirements for nuclear ships must always be considered, and the work on safety problems for nuclear ships sponsored by the NEA was regarded as an important step towards developing an international code of practice by IMCO on the safety of nuclear merchant ships. One session was devoted to the quantitative assessment of nuclear ship safety. The probability technique of an accident risk assessment for nuclear power plants is well known and widely used. Its modification, to make it applicable to nuclear propelled merchant ships, was discussed in some papers. Mathematical models for describing various postulated accidents with nuclear ships were developed and reported by several speakers. Several papers discussed a loss-of-coolant accident (LOCA) with nuclear steam supply systems of nuclear ships and engineering design features to prevent a radioactive effluence after LOCA. Other types of postulated accidents with reactors and systems in static and dynamic conditions were also

  8. RBMK safety issues

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  9. Introduction into the nuclear safety technologies

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.M.; Pavlenko, A.A.; Pis'mennyj, E.N.; Shirokov, S.V.

    2006-01-01

    The theoretical and practical issues of the power and research nuclear reactor safety existing on the territory of Ukraine, the radwaste and nuclear material management objects, as well as the 'Shelter' object, the aspects of the nuclear and radiation safety regulation are considered

  10. China's nuclear safety regulatory body: The national nuclear safety administration

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1991-04-01

    The establishment of an independent nuclear safety regulatory body is necessary for ensuring the safety of nuclear installations and nuclear fuel. Therefore the National Nuclear Safety Administration was established by the state. The aim, purpose, organization structure and main tasks of the Administration are presented. At the same time the practical examples, such as nuclear safety regulation on the Qinshan Nuclear Power Plant, safety review and inspections for the Daya Bay Nuclear Power Plant during the construction, and nuclear material accounting and management system in the nuclear fuel fabrication plant in China, are given in order to demonstrate the important roles having been played on nuclear safety by the Administration after its founding

  11. The internationalization of nuclear safety

    International Nuclear Information System (INIS)

    Rosen, M.

    1989-01-01

    Nuclear safety is interlinked in many ways with the themes of this conference. In searching for co-operative activities that touch on global energy and environmental problems and on initiatives that relieve international tensions, the ongoing developments in nuclear power safety offer a number of successful examples. Commercial nuclear power has been with us for more than 30 years, and with 26 countries operating plants in addition to 6 more constructing their first, there has been an ongoing global co-operation, coinciding of Chernobyl with Glasnost, along with the increasing awareness of the benefits of common solutions to safety issues, have brought about an internationalization of nuclear safety. Although the main responsibility for safety rests with each operator and its government, a primary driving force expanding international co-operation is the transboundary aspects of nuclear energy, as vividly demonstrated by Chernobyl accident. In this presentation we focus on the mechanisms already in place that foster cooperation in the nuclear safety area

  12. Identification of new unresolved safety issues relating to nuclear power plants - special report to Congress. Congressional report

    International Nuclear Information System (INIS)

    1981-03-01

    As a result of NRC staff review and extended collegial consultations and investigations within the NRC, the Commission has designated four new Unresolved Safety Issues (USIs). This report describes the process used to evaluate the large number of concerns and recommendations which resulted from the major investigations of the Three Mile Island-2 accident as well as other events and investigations of the past year, and the report identifies the four new USIs selected as follows: (1) Shutdown decay heat removal requirements (Task A-45); (2) Seismic qualification of equipment in operating plants (Task A-46); (3) Safety implications of control systems (Task A-47); and (4) Hydrogen control measures and effects of hydrogen burns on safety equipment (Task A-48). Appendix A of the report presents an expanded discussion of each new USI including issue definition, a preliminary discussion of the action plan and a basis for continued plant operations and licensing. Appendix B of the report provides a brief discussion of each of the candidate safety issues not designated as an USI

  13. 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

  14. Nuclear power and safety

    International Nuclear Information System (INIS)

    Saunders, P.; Tasker, A.

    1991-01-01

    Nuclear power currently provides about a fifth of both Britain's and the world's electricity. It is the largest single source of electricity in Western Europe; in France three quarters of electricity is generated by nuclear power stations. This booklet is about the safety of those plants. It approaches the subject by outlining the basic principles and approaches behind nuclear safety, describing the protective barriers and safety systems that are designed to prevent the escape of radioactive material, and summarising the regulations that govern the construction and operation of nuclear power stations. The aim is to provide a general understanding of the subject by explaining the general principles of the Advanced Gas Cooled Reactor and setting out the UKAEA strategy for nuclear safety, the objective being always to minimize risk. (author)

  15. Safety issues and their ranking for WWER-440 model 213 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    The objective of this report is to present a consolidated list of generic safety concerns, called safety issues, ranked according to their safety significance and the corrective measures to improve safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. Section 2 provides and overview of the impact of all relevant issues on the main safety functions and other aspects important to overall plant safety. Section 3 presents safety issues identified in design according to the structure described below. Section 4 presents the safety issues in the area of operation, according to the same structure except that no ranking is given. At the end of Section 2, Tables 1 and 2 present a summary of all safety issues in a tabular form. 138 refs, tabs

  16. Pantex Plant final safety analysis report, Zone 4 magazines. Staging or interim storage for nuclear weapons and components: Issue D

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This Safety Analysis Report (SAR) contains a detailed description and evaluation of the significant environmental, safety, and health (ES&H) issues associated with the operations of the Pantex Plant modified-Richmond and steel arch construction (SAC) magazines in Zone 4. It provides (1) an overall description of the magazines, the Pantex Plant, and its surroundings; (2) a systematic evaluations of the hazards that could occur as a result of the operations performed in these magazines; (3) descriptions and analyses of the adequacy of the measures taken to eliminate, control, or mitigate the identified hazards; and (4) analyses of potential accidents and their associated risks.

  17. National nuclear safety report 1998. Convention on nuclear safety

    International Nuclear Information System (INIS)

    1998-01-01

    The Argentine Republic subscribed the Convention on Nuclear Safety, approved by a Diplomatic Conference in Vienna, Austria, in June 17th, 1994. According to the provisions in Section 5th of the Convention, each Contracting Party shall submit for its examination a National Nuclear Safety Report about the measures adopted to comply with the corresponding obligations. This Report describes the actions that the Argentine Republic is carrying on since the beginning of its nuclear activities, showing that it complies with the obligations derived from the Convention, in accordance with the provisions of its Article 4. The analysis of the compliance with such obligations is based on the legislation in force, the applicable regulatory standards and procedures, the issued licenses, and other regulatory decisions. The corresponding information is described in the analysis of each of the Convention Articles constituting this Report. The present National Report has been performed in order to comply with Article 5 of the Convention on Nuclear Safety, and has been prepared as much as possible following the Guidelines Regarding National Reports under the Convention on Nuclear Safety, approved in the Preparatory Meeting of the Contracting Parties, held in Vienna in April 1997. This means that the Report has been ordered according to the Articles of the Convention on Nuclear Safety and the contents indicated in the guidelines. The information contained in the articles, which are part of the Report shows the compliance of the Argentine Republic, as a contracting party of such Convention, with the obligations assumed

  18. Safety and nuclear power

    International Nuclear Information System (INIS)

    Gittus, John; Gunning, Angela.

    1988-01-01

    Representatives of the supporters and opponents of civil nuclear power put forward the arguments they feel the public should consider when making up their mind about the nuclear industry. The main argument in favour of nuclear power is about the low risk in comparison with other risks and the amount of radiation received on average by the population in the United Kingdom from different sources. The aim is to show that the nuclear industry is fully committed to the cause of safety and this has resulted in a healthy workforce and a safe environment for the public. The arguments against are that the nuclear industry is deceitful, secretive and politically motivated and thus its arguments about safety, risks, etc, cannot be trusted. The question of safety is considered further - in particular the perceptions, definitions and responsibility. The economic case for nuclear electricity is not accepted. (U.K.)

  19. Nuclear regulation and safety

    International Nuclear Information System (INIS)

    Hendrie, J.M.

    1982-01-01

    Nuclear regulation and safety are discussed from the standpoint of a hypothetical country that is in the process of introducing a nuclear power industry and setting up a regulatory system. The national policy is assumed to be in favor of nuclear power. The regulators will have responsibility for economic, reliable electric production as well as for safety. Reactor safety is divided into three parts: shut it down, keep it covered, take out the afterheat. Emergency plans also have to be provided. Ways of keeping the core covered with water are discussed

  20. Enhancement of nuclear safety culture

    International Nuclear Information System (INIS)

    Anderson, Stanley J.

    1996-01-01

    Throughout the 40-year history of the commercial nuclear power industry, improvements have continually been made in the design of nuclear power plants and the equipment in them. In one sense, we have reached an enviable point -- in most plants, equipment failures have become relatively rare. Yet events continue to occur. Regardless of how much the plants are improved, that equipment is operated by people -- highly motivated, well-trained people -- but people nonetheless. And people occasionally make mistakes. By setting the right climate and by setting high standards, good plant management can reduce the number of mistakes made ? and also reduce their potential consequences. Another way to say this is that the proper safety culture must be established and continually improved upon in our nuclear plants. Safety culture is defined by the International Atomic Energy Agency as 'that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance.' In short, we must make safety our top priority

  1. Current safety issues of CANDU licensing

    International Nuclear Information System (INIS)

    Lee, Y.; Natalizio, A.

    1994-01-01

    As requested by Korea Institute of Nuclear Safety(KINS), the status of five generic licensing issues has been examined and their potential impact on a new plant that would be constructed in Canada has been evaluated. The results and conclusions of this evaluation are summarized as follows: steam explosion in calandria, hydrogen explosion in containment, use of PSA in reactor licensing, human factors, safety critical software

  2. Examination of issues related to the development and implementation of real-time operational safety monitoring tools in the nuclear power industry

    International Nuclear Information System (INIS)

    Puglia, William J.; Atefi, Bahman

    1995-01-01

    In recent years, risk and reliability techniques have been increasingly used to optimize deterministic requirements and to improve the operational safety of nuclear power stations. This paper discusses the historical development and current status of implementation of real-time operational safety monitoring tools in the nuclear power industry worldwide. A safety monitor is defined as a PC-based risk management tool, based on a plant specific PSA, which can be used to manage plant safety during the day-to-day operation of a nuclear power plant by planning maintenance activities and providing advisory information to plant operational staff in order to avoid high risk plant configurations. As this technique has only been applied in a few plants worldwide, the technology is still evolving and there are several technical and implementation-related issues which still need to be resolved. This paper attempts to summarize all such issues and describe how they have been addressed in several different applications of this technology around the world

  3. Comments on nuclear reactor safety in Ontario

    International Nuclear Information System (INIS)

    1987-08-01

    The Chalk River Technicians and Technologists Union representing 500 technical employees at the Chalk River Nuclear Laboratories of AECL submit comments on nuclear reactor safety to the Ontario Nuclear Safety Review. Issues identified by the Review Commissioner are addressed from the perspective of both a labour organization and experience in the nuclear R and D field. In general, Local 1568 believes Ontario's CANDU nuclear reactors are not only safe but also essential to the continued economic prosperity of the province

  4. Nuclear power systems: Their safety

    International Nuclear Information System (INIS)

    Myers, L.C.

    1993-01-01

    Mankind utilizes energy in many forms and from a variety of sources. Canada is one of a growing number of countries which have chosen to embrace nuclear-electric generation as a component of their energy systems. As of August 1992 there were 433 power reactors operating in 35 countries and accounting for more than 15% of the world's production of electricity. In 1992, thirteen countries derived at least 25% of their electricity from nuclear units, with France leading at nearly 70%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 68 power reactors are under construction in 16 countries, enough to expand present generating capacity by close to 20%. No human endeavour carries the guarantee of perfect safety and the question of whether or not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor in the USSR has irrevocably changed all that. This disaster brought the matter of nuclear safety back into the public mind in a dramatic fashion. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents which have occurred to date. (author). 7 refs

  5. Safety of nuclear power reactors

    International Nuclear Information System (INIS)

    MacPherson, H.G.

    1982-01-01

    Safety is the major public issue to be resolved or accommodated if nuclear power is to have a future. Probabilistic Risk Analysis (PRA) of accidental releases of low-level radiation, the spread and activity of radiation in populated areas, and the impacts on public health from exposure evolved from the earlier Rasmussen Reactor Safety Study. Applications of the PRA technique have identified design peculiarities in specific reactors, thus increasing reactor safety and establishing a quide for evaluating reactor regulations. The Nuclear Regulatory Commission and reactor vendors must share with utilities the responsibility for reactor safety in the US and for providing reasonable assurance to the public. This entails persuasive public education and information that with safety a top priority, changes now being made in light water reactor hardware and operations will be adequate. 17 references, 2 figures, 2 tables

  6. Nuclear power safety economics

    International Nuclear Information System (INIS)

    Legasov, V.A.; Demin, V.F.; Shevelev, Ya.V.

    1984-01-01

    The existing conceptual and methodical basis for the decision-making process insuring safety of the nuclear power and other (industrial and non-industrial) human activities is critically analyzed. Necessity of development a generalized economic safety analysis method (GESAM) is shown. Its purpose is justifying safety measures. Problems of GESAM development are considered including the problem of costing human risk. A number of suggestions on solving them are given. Using the discounting procedure in the assessment of risk or detriment caused by harmful impact on human health is substantiated. Examples of analyzing some safety systems in the nuclear power and other spheres of human activity are given

  7. Interrelationship between nuclear safety, safeguards and nuclear security

    International Nuclear Information System (INIS)

    Irie, Kazutomo

    2007-01-01

    As preventive activities against danger within nuclear systems, three major areas exist; nuclear safety, safeguards and nuclear security. Considering the purpose of these activities, to prevent non-peaceful use is common in nuclear security in general and safeguards. At the same time, measures against sabotage, one of the subcategory in nuclear security, is similar to nuclear safety in aiming at preventing nuclear accidents. When taking into account the insider issues in nuclear security, the distinction between measures against sabotage and nuclear safety becomes ambiguous. Similarly, the distinction between measures against theft, another subcategory in nuclear security, and safeguards also becomes vague. These distinctions are influenced by psychological conditions of members in nuclear systems. Members who have the intention to make nuclear systems dangerous to human society shall be the 'enemy' to nuclear systems and thus be the target for nuclear security. (author)

  8. Nuclear safety: risks and regulation

    International Nuclear Information System (INIS)

    Wood, W.C.

    1983-01-01

    Taking a fresh look at nuclear safety regulations, this study finds that the mandate and organization of the Nuclear Regulatory Commission (NRC) militate against its making sound decisions. The author criticizes failures to make hard decisions on societal risk, to clarify responsibility, and to implement cost-effective safety measures. Among his recommendations are reorganization of the NRC under a single authoritative administrator, separation of technical issues from social ones, and reform of the Price-Anderson Act. The author concludes that the worst eventuality would be to continue the current state of indecision. 161 references, 6 figures, 4 tables

  9. Nuclear Safety Project

    International Nuclear Information System (INIS)

    1983-12-01

    The semiannual progress report 1983/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1983 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. (orig./RW) [de

  10. Nuclear safety project

    International Nuclear Information System (INIS)

    1982-06-01

    The Annual Report 1981 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1981 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on - work completed - results obtained - plans for future work. This report was compiled by the project management. (orig.) [de

  11. Project Nuclear Safety

    International Nuclear Information System (INIS)

    1981-11-01

    The semiannual progress report 1981/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1981 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics, work performed, results obtained, plans for future work. This report was compiled by the project management. (orig.) [de

  12. Nuclear safety project

    International Nuclear Information System (INIS)

    1984-11-01

    The semiannual progress report 1984/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1984 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./RW) [de

  13. Nuclear safety project

    International Nuclear Information System (INIS)

    Anon.

    1980-11-01

    The 17th semi-annual report 1980/1 is a description of work within the Nuclear Safety Project performed in the first six months of 1980 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics - work performed, results obtained, plans for future work. (orig.) [de

  14. Nuclear Safety Project

    International Nuclear Information System (INIS)

    1978-11-01

    The 13th semi-annual report 1/78 is a description of work within the Nuclear Safety Project performed in the first six months of 1978 in the nuclear safety field by KFK institutes and departments and by external institutions on behalf of KfK. It includes for each individual research activity short summaries on - work completed, - essential results, - plans for the near future. (orig./RW) [de

  15. Nuclear safety review for the year 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-01

    The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. The final version of the Nuclear Safety Review for the Year 2002 was prepared in the light of the discussion by the Board of Governors in March 2002. This report presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety at the end of 2002. This overview is supported by a more detailed factual account of safety-related events and issues worldwide during 2002. National authorities and the international community continued to reflect and act upon the implications of the events of II September 2001 for nuclear, radiation, transport and waste safety. In the light of this, the Agency has decided to transfer the organizational unit on nuclear security from the Department of Safeguards to the Department of Nuclear Safety (which thereby becomes the Department of Nuclear Safety and Security). By better exploiting the synergies between safety and security and promoting further cross-fertilization of approaches, the Agency is trying to help build up mutually reinforcing global regimes of safety and security. However, the Nuclear Safety Review for the Year 2002 addresses only those areas already in the safety programme. This short analytical overview is supported by a second part (corresponding to Part I of the Nuclear Safety Reviews of previous years), which describes significant safety-related events and issues worldwide during 2002. A Draft Nuclear Safety Review for the Year 2002 was submitted to the March 2003 session of the Board of Governors in document GOV/2003/6.

  16. Nuclear safety review for the year 2002

    International Nuclear Information System (INIS)

    2003-08-01

    The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. The final version of the Nuclear Safety Review for the Year 2002 was prepared in the light of the discussion by the Board of Governors in March 2002. This report presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety at the end of 2002. This overview is supported by a more detailed factual account of safety-related events and issues worldwide during 2002. National authorities and the international community continued to reflect and act upon the implications of the events of II September 2001 for nuclear, radiation, transport and waste safety. In the light of this, the Agency has decided to transfer the organizational unit on nuclear security from the Department of Safeguards to the Department of Nuclear Safety (which thereby becomes the Department of Nuclear Safety and Security). By better exploiting the synergies between safety and security and promoting further cross-fertilization of approaches, the Agency is trying to help build up mutually reinforcing global regimes of safety and security. However, the Nuclear Safety Review for the Year 2002 addresses only those areas already in the safety programme. This short analytical overview is supported by a second part (corresponding to Part I of the Nuclear Safety Reviews of previous years), which describes significant safety-related events and issues worldwide during 2002. A Draft Nuclear Safety Review for the Year 2002 was submitted to the March 2003 session of the Board of Governors in document GOV/2003/6

  17. Progress of nuclear safety research. 2003

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

    2004-03-01

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

  18. Unresolved safety issues summary. Aqua Book. Volume 6, No. 3

    International Nuclear Information System (INIS)

    Butts, J.

    1984-01-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the national laboratories and is prepared by the Office of Nuclear Reactor Regulation

  19. Organization and Nuclear Safety: Safety culture

    International Nuclear Information System (INIS)

    Martin Marquinez, A.

    1998-01-01

    This book presents the experience in nuclear safety and its influence in the exploitation on nuclear power plants. The safety organization and quality management before and after Chernobylsk and three mile island accidents

  20. Elements of nuclear safety

    CERN Document Server

    Libmann, Jacques

    1996-01-01

    This basically educational book is intended for all involved in nuclear facility safety. It dissects the principles and experiences conducive to the adoption of attitudes compliant with what is now known as "safety culture". This book is accessible to a wide range of readers.

  1. Nuclear safety research

    International Nuclear Information System (INIS)

    1999-01-01

    The NNSA checked and coordinated in 1999 the research project of the Surveillance Technology on Nuclear Installations under the National 9th-Five-Year Program to promote the organizations that undertake the research work on schedule and lay a foundation of obtaining achievements and effectiveness for the 9th-five-year plan on nuclear safety research

  2. Nuclear power plant safety

    International Nuclear Information System (INIS)

    Otway, H.J.

    1974-01-01

    Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

  3. Approaches to nuclear safety

    International Nuclear Information System (INIS)

    Watkins, J.D.

    1990-01-01

    This article examines the factors which affect the safe operation of a nuclear power plant. Some of these are an organizational and individual dedication to safety and excellence in every aspect of plant functions, international cooperation, and advanced reactor design. These are in addition to excellence in management of nuclear plants and the training of key operations personnel. The author feels all of these are necessary to restore public confidence in nuclear power

  4. Nuclear safety chains

    International Nuclear Information System (INIS)

    Robbins, M.C.; Eames, G.F.; Mayell, J.R.

    1981-01-01

    An original scheme has been developed for expressing the complex interrelationships associated with the engineered safeguards provided for a nuclear power station. This management tool, based upon network diagrams called Nuclear Safety Chains, looks at the function required of a particular item of safety plant, defines all of the vital supplies and support features necessary for successful operation, and expresses them in visual form, to facilitate analysis and optimisation for operations and maintenance staff. The safety chains are confined to manual schemes at present, although they are designed to be compatible with modern computer techniques. Their usefulness with any routine maintenance planning application on high technology plant is already being appreciated. (author)

  5. Safety issues at the defense production reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors - the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. This report examines the safety objective established by the Department of Energy for the production reactors and the process the Department of its contractors use to implement the objective; focuses on a variety of uncertainties concerning the production reactors, particularly those related to potential vulnerabilities to severe accidents; and identifies ways in which the DOE approach to management of the safety of the production reactors can be improved

  6. Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1985-08-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

  7. Nuclear safety in perspective

    International Nuclear Information System (INIS)

    Andersson, K.; Sjoeberg, B.M.D.; Lauridsen, K.; Wahlstroem, B.

    2002-06-01

    The aim of the NKS/SOS-1 project has been to enhance common understanding about requirements for nuclear safety by finding improved means of communicating on the subject in society. The project, which has been built around a number of seminars, was supported by limited research in three sub-projects: 1) Risk assessment, 2) Safety analysis, and 3) Strategies for safety management. The report describes an industry in change due to societal factors. The concepts of risk and safety, safety management and systems for regulatory oversight are described in the nuclear area and also, to widen the perspective, for other industrial areas. Transparency and public participation are described as key elements in good risk communication, and case studies are given. Environmental Impact Assessment and Strategic Environmental Assessment are described as important overall processes within which risk communication can take place. Safety culture, safety indicators and quality systems are important concepts in the nuclear safety area are very useful, but also offer important challenges for the future. They have been subject to special attention in the project. (au)

  8. Evaluation of Station Blackout accidents at nuclear power plants. Technical findings related to Unresolved Safety Issue A-44. Draft report for comment

    International Nuclear Information System (INIS)

    Baranowsky, P.W.

    1985-05-01

    ''Station Blackout,'' which is the complete loss of alternating current (ac) electrical power in a nuclear power plant, has been designated as Unresolved Safety Issue A-44. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on ac power, the consequences of a station blackout could be severe. This report documents the findings of technical studies performed as part of the program to resolve this issue. The important factors analyzed include: the frequency of loss of offsite power; the probability that emergency or onsite ac power supplies would be unavailable; the capability and reliability of decay heat removal systems independent of ac power; and the likelihood that offsite power would be restored before systems that cannot operate for extended periods without ac power fail, thus resulting in core damage. This report also addresses effects of different designs, locations, and operational features on the estimated frequency of core damage resulting from station blackout events

  9. Concerning safety issue associated with approval of modification of plan for reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation (reply to inquiry)

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    In response to an inquiry on the title issue received on Sept. 16, 1988, the Nuclear Safety Commission made an adequate study and submitted the findings to the Prime Minister on Oct. 20. the relevant modifications include the installation of combustion facilities comprising two furnaces to replace the existing facilities, and the addition of uranyl nitrate solution receiving equipment to the existing facilities for plutonium conversion technology development. The study addressed the effect of the modifications on the safety of the facilities and the environment. The combustion facilities, equipment and underground seepage water tank are designed in accordance with the applicable anti-earthquake standards. The facilities will be constructed of incombustible of flame-retardant materials. Equipment in the facilities will be used under negative pressure to prevent counterflow. Adequate measures will be taken for shielding, exposure control, waste disposal, etc. It is concluded that the modifications will not affect the safety of the reprocessing facilities. (Nogami, K.).

  10. Concerning safety issue associated with approval of modification of plan for reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation (reply to inquiry)

    International Nuclear Information System (INIS)

    1989-01-01

    In response to an inquiry on the title issue received on Sept. 16, 1988, the Nuclear Safety Commission made an adequate study and submitted the findings to the Prime Minister on Oct. 20. the relevant modifications include the installation of combustion facilities comprising two furnaces to replace the existing facilities, and the addition of uranyl nitrate solution receiving equipment to the existing facilities for plutonium conversion technology development. The study addressed the effect of the modifications on the safety of the facilities and the environment. The combustion facilities, equipment and underground seepage water tank are designed in accordance with the applicable anti-earthquake standards. The facilities will be constructed of incombustible of flame-retardant materials. Equipment in the facilities will be used under negative pressure to prevent counterflow. Adequate measures will be taken for shielding, exposure control, waste disposal, etc. It is concluded that the modifications will not affect the safety of the reprocessing facilities. (Nogami, K.)

  11. Practicing industrial safety - issues involved

    International Nuclear Information System (INIS)

    Gunasekaran, P.

    2016-01-01

    Industrial safety is all about measures or techniques implemented to reduce the risk of injury, loss to persons, property or the environment in any industrial facility. The issue of industrial safety evolved concurrently with industrial development as a shift from compensation to prevention as well. Today, industrial safety is widely regarded as one of the most important factors that any business, large or small, must consider in its operations, as prevention of loss is also a part of profit. Factories Act of Central government and Rules made under it by the state deals with the provisions on industrial safety legislation. There are many other acts related to safety of personnel, property and environment. Occupational health and safety is also of primary concern. The aim is to regulate health and safety conditions for all employers. It includes safety standards and health standards. These acts encourage employers and employees to reduce workplace hazards and to implement new or improve existing safety and health standards; and develop innovative ways to achieve them. Maintain a reporting and record keeping system to monitor job-related injuries and illnesses; establish training programs to increase the number and competence of occupational safety and health personnel

  12. Nuclear ships and their safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-04-15

    Several aspects of nuclear ship propulsion, with special reference to nuclear safety, were discussed at an international symposium at Taormina, Italy, from 14-18 November 1960. Discussions on specific topics are conducted, grouped under the following headings: Economics and National Activities in Nuclear Ship Propulsion; International Problems and General Aspects of Safety for Nuclear Ships; Nuclear Ship Projects from the Angle of Safety; Ship Reactor Problems; Sea Motion and Hull Problems; Maintenance and Refuelling Problems; and Safety Aspects of Nuclear Ship Operation.

  13. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-03-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking. 73 refs, 3 tabs

  14. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-04-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking

  15. Key issues for passive safety

    International Nuclear Information System (INIS)

    Hayns, M.R.

    1996-01-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ''review paper'' as such and only record the highlights. (author)

  16. Key issues for passive safety

    Energy Technology Data Exchange (ETDEWEB)

    Hayns, M R [AEA Technology, Harwell, Didcot (United Kingdom). European Institutions; Hicken, E F [Forschungszentrum Juelich GmbH (Germany)

    1996-12-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ``review paper`` as such and only record the highlights. (author).

  17. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-11-01

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

  18. NRC - regulator of nuclear safety

    International Nuclear Information System (INIS)

    1997-01-01

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations

  19. Nuclear Safety Charter

    International Nuclear Information System (INIS)

    2008-01-01

    The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and subcontractors are treated

  20. Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

    Science.gov (United States)

    Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

    1993-01-01

    An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

  1. 3. French national report on implementation of the obligations of the Convention on nuclear safety - Issued for the 2005 Peer review meeting

    International Nuclear Information System (INIS)

    2004-01-01

    The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 with the aim of proposing binding international obligations regarding nuclear safety. France signed the Convention on 20 September 1994, on the first day it was opened for signature on the occasion of the General Conference of the IAEA. France approved the Convention on 13 September 1995 and it entered into force on 24 October 1996. For many years, France has been participating in international initiatives to enhance nuclear safety and considers the Convention on Nuclear Safety to be an important step in this direction. The areas covered by the Convention have long been part of the French approach to nuclear safety. This report, the third one of its kind, is issued in compliance with Article 5 of the Convention on Nuclear Safety and presents the measures taken by France to meet each of the obligations of the Convention. As such, the Convention on Nuclear Safety applies to nuclear power reactors and so most of this report deals with measures taken to ensure their safety. However, for this third report, a number of considerations led France also to present the measures taken concerning all research reactors, with a 'graded approach' tailored to their size where appropriate. First of all, research reactors are subject to the same general regulations as power reactors with regard to nuclear safety and radiation protection. Furthermore, the most powerful research reactor, which is also intended for producing power, was already included in the previous French report. Secondly, within the first report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, to which France is a party, the measures taken for research reactors in these areas were already presented. Finally the IAEA Board of Governors, on which France has a seat, in March 2004 approved the Code of

  2. Discussion on nuclear issues

    International Nuclear Information System (INIS)

    Andrlova, Z.

    2012-01-01

    Treatment of the radioactive waste and utilisation of the ionisation radiation. Interesting contributions to two topics appeared in conference of Slovak Nuclear Society in Casta-Papiernicka in May 2012. The members from the female section 'Women in nuclear sector; were discussing in particular of the mind-set of Europeans to radioactive waste and novelties in nuclear medicine. (author)

  3. Nuclear safety philosophy in the United Kingdom

    International Nuclear Information System (INIS)

    Anthony, R.D.

    1986-01-01

    Development of the United Kingdom (UK) nuclear safety philosophy is described in the context of the UK nuclear power program since 1959 and of its legislative framework. Basic to the philosophy is that the licensee is wholly responsible for nuclear safety. The licensing process and safety assessment principles used by the Nuclear Installations Inspectorate are discussed, and examples from the assessment of the proposed UK pressurized-water reactor are used to illustrate how the approach works in practice. The UK siting policy and regulatory developments since 1979 are also discussed. Recent, current, and future issues of interest to the regulatory authority are described against the development nuclear scene in the UK

  4. Progress of nuclear safety research - 2005

    International Nuclear Information System (INIS)

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

    2006-03-01

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

  5. 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)

  6. Nuclear safety infrastructure

    International Nuclear Information System (INIS)

    Moffitt, R.L.

    2010-01-01

    The introduction of nuclear power in any country requires the early establishment of a long term nuclear safety infrastructure. This is necessary to ensure that the siting, design, construction, commissioning, operation and dismantling of the nuclear power plant and any other related installations, as well as the long term management of radioactive waste and spent fuel, are conducted in a safe and secure manner. The decision to undertake a nuclear power program is a major commitment requiring strict attention to nuclear safety. This commitment is a responsibility to not only the citizens of the country developing such a program, but also a responsibility to the international community. Nobody can take on this responsibility or make the critical decisions except the host country. It is important to make sure that the decision making process and the development activities are done in as open a manner as possible allowing interested stakeholders the opportunity to review and comment on the actions and plans. It cannot be overemphasized that everyone involved in a program to develop nuclear power carries a responsibility for ensuring safety. While it is clear that the key decisions and activities are the responsibility of the host country, it is also very important to recognize that help is available. The IAEA, OECD-NEA, WANO and other international organizations along with countries with established nuclear power programs are available to provide information and assistance. In particular, the IAEA and OECD-NEA have published several documents regarding the development of a nuclear power program and they have been and continue to support many meetings and seminars regarding the development of nuclear power programs

  7. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  8. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  9. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  10. Nuclear and radiological safety, 1980-1993

    International Nuclear Information System (INIS)

    1994-06-01

    This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Safety, issued during the period 1980-1993. It gives an abstract of these publications along with contents and prices in Austrian Schillings

  11. Nuclear Safety Review for the Year 2012

    International Nuclear Information System (INIS)

    2012-07-01

    The Nuclear Safety Review for the Year 2012 contains an analytical overview of the dominant trends, issues and challenges worldwide in 2011 and the Agency's efforts to strengthen the global nuclear safety framework. This year's report also highlights issues and activities related to the accident at the Fukushima Daiichi nuclear power plant. The analytical overview is supported by the Appendix at the end of this document, entitled: The IAEA Safety Standards: Activities during 2011. A draft version of the Nuclear Safety Review for the Year 2012 was submitted to the March 2012 session of the Board of Governors in document GOV/2012/6. The final version of the Nuclear Safety Review for the Year 2012 was prepared in light of the discussions held during the Board of Governors and also of the comments received.

  12. Safety design of Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ouyang Yu; Zhang Lian; Du Shenghua; Zhao Jiayu

    1984-01-01

    Safety issues have been greatly emphasized through the design of the Qinshan Nuclear Power Plant. Reasonable safety margine has been taken into account in the plant design parameters, the design incorporated various safeguard systems, such as engineering safety feature systems, safety protection systems and the features to resist natural catastrophes, e. g. earthquake, hurricanes, tide and so on. Preliminary safety analysis and environmental effect assessment have been done and anti-accident provisions and emergency policy were carefully considered. Qinshan Nuclear Power Plant safety related systems are designed in accordance with the common international standards established in the late 70's, as well as the existing engineering standard of China

  13. Nuclear safety in France

    International Nuclear Information System (INIS)

    Laverie, M.

    1981-02-01

    The principles and rules governing the safety of nuclear installations are defined as from three fundamental principles and three practical rules as follows: First principle: the operator is responsible and of the highest order. Second principle: the public authorities exercise their control responsibility with respect to the design, construction and running of the installations. Third principle: nuclear safety, this is to accept that man and his technique are not infallible and that one must be prepared to control the unpredictable. First rule: the installations must include several 'lines of defence' in succession and to the extent where this is possible these must be independent of each other. Second rule: procedures are required and supervised by the Government Departments. Third rule: nuclear safety requires that any incident or anomaly must undergo an analysis in depth and is also based on a standing 'clinical' examination of the installations. The definition is given as to how the public authorities exercise their intervention: terms and conditions of the intervention by the safety authorities, authorization procedures, surveillance of the installations, general technical regulations. Two specific subjects are presented in the addendum, (a) the choice of nuclear power station sites in France and (b) the storage of radioactive wastes [fr

  14. Global Nuclear Safety and Security Network

    International Nuclear Information System (INIS)

    Guo Lingquan

    2013-01-01

    The objectives of the Regulatory Network are: - to contribute to the effectiveness of nuclear regulatory systems; - to contribute to continuous enhancements, and - to achieve and promote radiation and nuclear safety and security by: • Enhancing the effectiveness and efficiency of international cooperation in the regulation of nuclear and radiation safety of facilities and activities; • Enabling adequate access by regulators to relevant safety and security information; • Promoting dissemination of information on safety and security issues as well as information of good practices for addressing and resolving these issues; • Enabling synergies among different web based networks with a view to strengthening and enhancing the global nuclear safety framework and serving the specific needs of regulators and international organizations; • Providing additional information to the public on international regulatory cooperation in safety and security matters

  15. 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

  16. The nuclear controversy and nuclear safety techniques

    International Nuclear Information System (INIS)

    Ragnarson, P.

    1979-09-01

    Survey interviews with 125 Swedish nuclear safety engineers are summarized and commented upon. A short historical background is given, claiming that the major safety issues of nuclear energy have been debated continously during the 50's and 60's in a way that could well have been watched and interpreted by a political, democratic system involving political parties, government departments, etc. With a few exceptions, these 125 engineers represent 10 - 20 years experience in nuclear research and development. By definition they belong to a professional group of about 800 in Sweden (1978). The main aim of the study is to find out if (how and why) a public debate can bring about changes in an industrially established technology by influencing the attitudes and technical judgements of the individuals and/or organizations involved. Examples are given in which the nuclear specialists themselves admit or claim that direct or indirect impacts from the public debate have been important. A common experience is that the scientists and engineers have been forced to broaden their professional scope through a time-consuming but - on the whole - 'positive' process. A year after the interviews started, a serious reactor accident occured near Harrisburg, Pennsylvania. The group has been used for a survey of the immediate reactions in order to see if it could cause sudden changes of attitudes among the experts. A minority demonstrated clear changes towards a more cautious attitude regarding nuclear risks. (author)

  17. Nuclear safety research

    International Nuclear Information System (INIS)

    1996-01-01

    The topics 'Large-sized PWR-NPP Safety Techniques Research',and 'The Key Techniques Research on the Safety Supervision and Control for Operation of Nuclear Installations' have been adopted as an apart of 'the National 9th five Year Programs for Tacking the Key Scientific and Technical Topics' which are organized by the State Planning Commission (SPC) and State Science and Technology Commission (SSTC) respectively, and have obtained a financial support from them. To play a better role with the limited fund, the NNSA laid special stress on selecting key sub-topics on nuclear safety, and carefully choosing units which would undertake sub-topics and signing technical contracts with them

  18. Understanding the nuclear issues

    International Nuclear Information System (INIS)

    Mooradian, A.J.

    1976-06-01

    Nuclear power is presented as a necessary power source for the transition from fossil fuels to a no-growth society of the future. It is already economic and on-stream all over the world. Radiation is a very tractable hazard. New fuel cycles would provide extraordinary increases in our nuclear fuel reserves. (E.C.B.)

  19. Nuclear issues in Australia

    International Nuclear Information System (INIS)

    Switkowski, Z.

    2007-01-01

    Full text: After a twenty year pause in discussion of nuclear power in Australia, the public debate has resumed in this past year - partly in search for clean, non fossil fuel energy alternatives, and partly from the different political strategies in the lead up to this year's federal election. Although there is evidence of a revival of interest in the nuclear power globally, countries considering installing their first nuclear reactor confront formidable obstacles including community concerns and long lead times. This presentation will describe the Climate Change context which shapes political and corporate strategies, possible nuclear scenarios for Australia, solutions to the still long list of reservations, and likely milestones ahead. It concludes that if we are to decarbonise our economy, and continue on a path of improving standards of living and prosperity, then any strategy for adding the required base-load electricity generation capacity must consider nuclear power for Australia

  20. Nordic nuclear safety research program 1994-1997. Project coordination incl. SAM-4 general information issues. Report 1996. Plans for 1997

    International Nuclear Information System (INIS)

    1997-04-01

    NKS (Nordic Nuclear Safety Research) is a cooperative body in nuclear safety, radiation protection and emergency preparedness. Its purpose is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, recommendations, manuals etc., to be used by decision makers and other concerned staff members at authorities and within the nuclear industry. This is the annual report for 1996, the third year of the fifth four-year NKS program (1994-1997). The report also contains plans for the rest of the program period, including budget proposals. The following major fields of research have been identified: reactor safety; radioactive waste; radioecology; emergency preparedness; and information issues. A total of nine projects are now under way within that framework. One project (RAK-1) is dedicated to reactor safety strategies: how to avoid serious accidents. A parallel project (RAK-2) deals with minimizing releases in case of an accident. When can an overheated reactor core still be water-cooled? What might be the consequences of the cooling? All Nordic countries have long-lived low and medium level radioactive waste that requires final disposal. One project (AFA-1) addresses that issue. Environmental impact of radioactive releases is studied in two radioecology projects. The project on marine radioecology, including sediment research (EKO-1), encompasses sampling, analysis and modeling. These are also key issues in the project on long ecological half-lives in semi-natural systems (EKO-2). The transfer of radioactive cesium and strontium in the chains soil - vegetation - sheep and mushroom - roe deer is studied, along with freshwater systems. Long-term doses to main is the ultimate output from the obtained models. Another aspect of environmental impact is emergency preparedness. A recently started project, EKO-5, addresses the issue of early planning for cleanup operations following a fallout. 'Early' in this context means within the

  1. Nuclear Safety Review for 2015

    International Nuclear Information System (INIS)

    2015-06-01

    The Nuclear Safety Review 2015 focuses on the dominant nuclear safety trends, issues and challenges in 2014. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: improving radiation, transport and waste safety; strengthening safety in nuclear installations; enhancing emergency preparedness and response (EPR); and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the Agency’s safety standards. The global nuclear community continued to make steady progress in improving nuclear safety throughout the world in 2014; and, the Agency and its Member States continued to implement the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”), which was endorsed by the General Conference in 2011 after the Fukushima Daiichi accident in March 2011. • Significant progress has been made in reviewing and revising various Agency’s safety standards in areas such as management of radioactive waste, design basis hazard levels, protection of nuclear power plants (NPPs) against severe accidents, design margins to avoid cliff edge effects, multiple facilities at one site, and strengthening the prevention of unacceptable radiological consequences to the public and the environment, communications and EPR. In addition, the Guidelines for Drafting IAEA Safety Standards and Nuclear Security Series Publications was issued in July 2014.• The Agency continued to analyse the relevant technical aspects of the Fukushima Daiichi accident and to share and disseminate lessons learned to the wider nuclear community. In 2014, the Agency organized two international experts’ meetings (IEMs), one on radiation protection and one on severe accident management. Reports from previous IEMs were also published in 2014: IAEA Report on Human and Organizational Factors in Nuclear

  2. Investigation of nuclear power safety objects

    International Nuclear Information System (INIS)

    2003-09-01

    It is a report of ground and concept of nuclear safety objects and future issues in Japan, which has investigated by the Committee of Experts on Investigation of Nuclear Safety Objects in the Nuclear Safety Research Association. The report consisted of member of committee, main conclusions and five chapters. The first chapter contains construction of safety objects and range of object, the second chapter qualitative safety objects, the third chapter quantitative safety objects, the forth subsiding objects and the fifth other items under consideration. The qualitative safety objects on individual and society, the quantitative one on effects on health and social cost, aspect of safety objects, relation between radiation protection and safety objects, practical objective values and earthquake are stated. (S.Y.)

  3. The juridical issues of nuclear activities

    International Nuclear Information System (INIS)

    Guillaume, M.; Kerever, A.; Pasquier, J.L.; Brillanceau, F.; Besson, J.P.; Chaumette, L.; Niel, J.C.; Reculeau, Y.; Treflez, M.; Pezennec, D.; Cochaud, J.F.; Phan Van, L.; Cormis, F. de; Galmot, Y.; Saint-Raymond, P.; Blanchard, P.; Robert, J.H.

    1997-01-01

    This issue is dedicated to the juridical aspects of civil nuclear activities. It comprises 3 parts and 16 papers. Radiation protection law is dealt with in part 1: prevention of risks due to ionizing radiations in occupational environment; sources and men; the regulation of radioactive materials transport; the regulation of the rejection of gaseous and liquid radioactive effluents. Part 2 tackles the question of checking the pacific uses of nuclear energy, that is the juridical consequences of the non-proliferation and physical protection policies are reviewed: international efforts that aim to limit the military uses of nuclear energy; the juridical and practical aspects of non-proliferation rules and international controls; the national control of radioactive materials. The juridical framing of nuclear activities, nuclear civil liability and infraction of the law are gathered in part 3: the CIINB and its contribution to the safety of nuclear installations; the mining law; the control of nuclear installations safety; the influence of the realization of the nuclear program on the evolution of the French law; the intervention of the administrative judge in nuclear affairs; the protection of population against nuclear risk - statement of existing provisions and new trends; the special regime of the civil nuclear responsibility - at the time of change; the penal infractions of the nuclear law. (J.S.)

  4. Strengthening of nuclear power plant construction safety management

    International Nuclear Information System (INIS)

    Yu Jun

    2012-01-01

    The article describes the warning of the Fukushima nuclear accident, and analyzes the major nuclear safety issues in nuclear power development in China, problems in nuclear power plants under construction, and how to strengthen supervision and management in nuclear power construction. It also points out that the development of nuclear power must attach great importance to the safety, and nuclear power plant construction should strictly implement the principle of 'safety first and quality first'. (author)

  5. Safety of nuclear installations: Future direction

    International Nuclear Information System (INIS)

    1990-04-01

    The Workshop presentations were divided into sessions devoted to the following topics: Environmental impact of fossil fuel energy technologies (5 papers), Future needs for nuclear power (7 papers), Safety objectives (10 papers), Safety aspects of the next generation of current-type nuclear power plants (8 papers), Safety aspects of new designs and concepts for nuclear power plants (6 papers), Special safety issues: Safety aspects of new designs and concepts for nuclear power plants (5 papers), Safety aspects of new designs and processes for the nuclear fuel cycle (5 papers), Closing panel (3 papers), 12 poster presentations and a Summary of the Workshop. A separate abstract was prepared for each of these papers. Refs, figs and tabs

  6. Nuclear power and greenhouse - twin issues

    International Nuclear Information System (INIS)

    Row, R.W.

    1990-01-01

    It is shown that nuclear electric power generation has been widely vilified in recent years. Its detractors have gained ascendancy over its proponents in guiding the political processes that control the approval of new civilian nuclear power stations for electricity generation in many countries. As a consequence, worldwide nuclear capacity growth is slowing to about 2.5% per year through the 1990s with a potential decline in nuclear capacity thereafter. This is occurring despite nuclear power's excellent record of safety and economy in comparison with other means of producing electricity, and while technical developments to improve this record continue. Proponents hope that its virtue of being the only proven means of generating electricity worldwide on a large scale that does not produce any greenhouse gases will appeal to environmentalists and help lead to a renewed nuclear age. This paper suggests that more than hope and rational argument based on scientific facts are needed to persuade the public to revise its opinion of nuclear power. A widespread nuclear fear based in part on ignorance, misinformation, and nuclear mythology, encouraged by nuclear opponents and ineptly countered by nuclear advocates, has had an important role in creating this situation. The greenhouse issues, closely resembling the nuclear issues in a number of ways, are also discussed. 23 refs

  7. Light Water Reactor Generic Safety Issues Database (LWRGSIDB). User's manual

    International Nuclear Information System (INIS)

    1999-01-01

    The IAEA Conference on 'The Safety of Nuclear Power: Strategy for the Future' in 1991 was a milestone in nuclear safety. The objective of this conference was to review nuclear power safety issues for which achieving international consensus would be desirable, to address concerns on nuclear safety and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. Some of the publications related to these two items that have been issued subsequent to this conference are: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-8 (1995), the IAEA Safety Guide 50-SG-O12, Periodic Safety Review of Operational Nuclear Power Plants (1994) and IAEA Safety Reports Series No. 12, Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards: A Common Basis for Judgement (1998). Some of the findings of the 1991 conference have not yet been fully addressed. An IAEA Symposium on Reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review those operating nuclear power plants which do not reach the high safety levels of the vast majority of plants and to undertake improvements with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear Safety and its implementation. In order to perform safety reviews and to reassess the safety of operating nuclear power plants in a uniform manner, it is imperative to have an internationally accepted reference. Existing guidance needs to be complemented by a list of safety issues which have been encountered and

  8. Safety issues on advanced fuel

    International Nuclear Information System (INIS)

    Gross, H.; Krebs, W.D.

    1998-01-01

    In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [de

  9. Status of nuclear safety research - 2000

    International Nuclear Information System (INIS)

    Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

    2000-11-01

    The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

  10. Characterization report for the ferrocyanide safety issue

    International Nuclear Information System (INIS)

    Pulsipher, B.A.; Burger, L.L.; Liebetrau, A.M.; Scheele, R.D.

    1997-06-01

    Recently PNNL was tasked by DOE to develop and demonstrate a risk-based strategic approach to characterizing Hanford's Nuclear Waste Tanks. This strategic approach was documented in a report entitled ''A Risk-Based Focused Decision-Management Approach for Justifying Characterization of Hanford Tank Waste''. In support of the general approach, a specific strategy for addressing each of the several safety issues associated with the tanks was developed. This report documents the approach for the Ferrocyanide Safety Issue. The purpose of this report is to describe a structured logic diagram (SLD) for determining the risk associated with the ferrocyanide tank safety issue and provide the supporting information for the SLD. The SLD addresses the resolution of risks resulting from the presence of ferrocyanide layers within the Hanford tanks. The informational requirements for determining risk from any reaction stemming from ferrocyanide are outlined in the SLD. This report will describe the potential paths to a successful resolution of the ferrocyanide safety issue. Complete development of the intervention pathway is outside the scope of this current activity. General descriptions of the approach, key components of the SLD, and conclusions are provided in the body of this report. The complete SLD, descriptions of each box shown in the SLD, a discussion on how to fill data needs, and a list of contributors is provided in the appendices

  11. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    verification' are used differently in different countries. The way that these terms have been used in this Safety Guide is explained in Section 2. The term 'design' as used here includes the specifications for the safe operation and management of the plant. This Safety Guide identifies the key recommendations for carrying out the safety assessment and the independent verification. It provides detailed guidance in support of IAEA, Safety of Nuclear Power Plants: Design, Safety Standards Series No. NS-R-1 (2000), particularly in the area of safety analysis. However, this does not include all the technical details which are available and reference is made to other IAEA publications on specific design issues and safety analysis methods. Specific deterministic or probabilistic safety targets or radiological limits can vary in different countries and are the responsibility of the regulatory body. This Safety Guide provides some references to targets and limits established by international organizations. Operators, and sometimes designers, may also set their own safety targets which may be more stringent than those set by the regulator or may address different aspects of safety. In some countries operators are expected to do this as part of their 'ownership' of the entire safety case. This Safety Guide does not include specific recommendations for the safety assessment of those plant systems for which dedicated Safety Guides exist. Section 2 defines the terms 'safety assessment', 'safety analysis' and 'independent verification' and outlines their relationship. Section 3 gives the key recommendations for the safety assessment of the principal and plant design requirements. Section 4 gives the key recommendations for safety analysis. It describes the identification of postulated initiating events (PIEs), which are used throughout the safety assessment including the safety analysis, the deterministic transient analysis and severe accident analysis, and the probabilistic safety analysis

  12. Nuclear installations sites safety

    International Nuclear Information System (INIS)

    Barber, P.; Candes, P.; Duclos, P.; Doumenc, A.; Faure, J.; Hugon, J.; Mohammadioun, B.

    1988-11-01

    This report is divided into ten parts bearing: 1 Safety analysis procedures for Basis Nuclear Installations sites (BNI) in France 2 Site safety for BNI in France 3 Industrial and transport activities risks for BNI in France 4 Demographic characteristics near BNI sites in France 5 Meteorologic characteristics of BNI sites in France 6 Geological aspects near the BNI sites in France 7 Seismic studies for BNI sites in France 8 Hydrogeological aspects near BNI sites in France 9 Hydrological aspects near BNI sites in France 10 Ecological and radioecological studies of BNI sites in France [fr

  13. Promotion of nuclear safety culture in Korea

    International Nuclear Information System (INIS)

    Eun, Youngsoo

    1996-01-01

    The term 'nuclear safety culture' was first introduced by the IAEA after the Chernobyl accident in the former USSR and subsequently defined in the IAEA's Safety Series No. 75-IMSAG-4 'Safety Culture' as follows : 'Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establish that establish that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance.' INSAG-4 deals with the concept of 'Safety Culture' as it relates to organizations and individuals engaged in nuclear power activities, and is intended for use by governmental authorities and by the nuclear industry and its supporting organizations. The IAEA's Assessment of Safety Culture in Organizations Team (ASCOT) developed ASCOT Guidelines that can be used in the assessment of the safety culture level of the organizations and their individual workers concerned, with a view to the tangible manifestations of safety culture that has intangible characteristics in nature. The IAEA provides the nuclear safety culture assessment service on the request of the Member States. Safety culture can not be achieved by the effort of the nuclear industry and its involved individuals alone. Rather, it requires a well concerted effort among various organizations engaged in nuclear activities including regulatory organizations

  14. Convention on nuclear safety

    International Nuclear Information System (INIS)

    1994-01-01

    The Convention on Nuclear Safety was adopted on 17 June 1994 by Diplomatic Conference convened by the International Atomic Energy Agency at its Headquarters from 14 to 17 June 1994. The Convention will enter into force on the ninetieth day after the date of deposit with the Depository (the Agency's Director General) of the twenty-second instrument of ratification, acceptance or approval, including the instruments of seventeen States, having each at leas one nuclear installation which has achieved criticality in a reactor core. The text of the Convention as adopted is reproduced in the Annex hereto for the information of all Member States

  15. 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

  16. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  17. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  18. Alternate approaches to nuclear safety

    International Nuclear Information System (INIS)

    Crane, A.T.

    1985-01-01

    For the US nuclear power industry to expand, a greatly increased portion of the public must come to share the industry's confidence in reactor safety. Major obstacles to establishing this confidence are frequent incidents with potential safety implications and a lack of incontrovertible proof that the risk of a major accident is very low. The most important step toward overcoming these obstacles would be for each utility to operate, maintain, and evaluate its reactors according to far higher standards. With improvements in reliability and safety margins, existing plants would be a stimulus for building new ones rather than an impediment. If changes to the operation of existing plants and improvements to the design of future ones were inadequate, the only hope for a revival of the nuclear industry would be an alternative reactor so obviously safe that risk would no longer be an issue. Three possible concepts are the modular high-temperature gas reactor, the process inherent ultimate safety reactor, and the liquid-metal fast reactor. All three have inherent safety features that should make a meltdown essentially impossible. They cannot know just how great the advantage of these alternate reactors would be, but the benefits of developing one or more of the concepts appear great

  19. Refinement of nuclear safety education reinforcing technical succession

    International Nuclear Information System (INIS)

    Yokobori, Seiichi

    2008-01-01

    In April 2008, Musashi Institute of Technology established another faculty, the Faculty of Nuclear Safety Engineering, to educate students for nuclear engineering to meet the demands of personnel for nuclear business. At this new faculty, students mainly obtain professional knowledge and skills related to nuclear safety issues. This article described refinement of nuclear safety education by reinforcing technical succession topics, such as Rankine cycle, fission, two-phase flow, defense in depth in safety. LOCA/ECCS, seismic effects, reactor maintenance. (T. Tanaka)

  20. Safety issues at the defense production reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors endash the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. The report is necessarily based on a limited review of the defense production reactors. It does not address whether any of the reactors are ''safe,'' because such an analysis would involve a determination of acceptable risk endash a matter of obvious importance, but one that was beyond the purview of the committee. It also does not address whether the safety of the production reactors is comparable to that of commercial nuclear power stations, because even this narrower question extended beyond the charge to the committee and would have involved detailed analyses that the committee could not undertake

  1. 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)

  2. Nuclear Safety Review for the Year 2003

    International Nuclear Information System (INIS)

    2004-08-01

    The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. In line with the suggestions made by the Board of Governors in March 2002, the first part is more analytical and less descriptive. This short analytical overview is supported by a second part, which describes significant safety related events and issues worldwide during 2003. A Draft Nuclear Safety Review for the Year 2003 was submitted to the March 2004 session of the Board of Governors in document GOV/2004/3. The final version of the Nuclear Safety Review for the Year 2003 was prepared in the light of the discussion by the Board.

  3. Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues

    International Nuclear Information System (INIS)

    1993-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  4. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues. Supplement 4

    International Nuclear Information System (INIS)

    1994-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30, 1994. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  5. Nuclear safety review for the year 2001

    International Nuclear Information System (INIS)

    2002-07-01

    The Nuclear Safety Review for the Year 2001 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts. Part 1 describes those events in 2001 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety. Part 2 describes some of the IAEA's efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2001. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2001. Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2001 was presented to the March 2002 session of IAEA's Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2002 that were considered pertinent to the discussion of events during 2001

  6. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  7. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  8. Nuclear liability, nuclear safety, and economic efficiency

    International Nuclear Information System (INIS)

    Wood, W.C.

    1980-01-01

    This dissertation applies the methods of economic analysis to nuclear liability and Price-Anderson. First the legislative history is reviewed; in that history the economic role of liability in affecting safety and allocating risk was virtually ignored. Succeeding chapters reformulate issues from the policy debate and subject them to economic analysis. A persistent issue is whether nuclear utilities respond to their limited liability by allowing a higher probability of serious accident. Comparative-static analysis shows that limited liability does lead to a higher chance of accidents, though the effect may be small. The analysis also shows that safety is achieved in a more capital-intensive manner than is cost-minimizing and that limited liability causes reactor owners to favor more heavily populated sites for plants. Therefore, the siting decision makes potential loss greater even if there is no change in the probability of an accident. Citizens' preferences on nuclear liability are examined next, starting with the nature of coverage that would be just in the sense of contraction theories such as John Rawls' Theory of Justice. Citizens behind Rawls' veil of ignorance, forced to be fair because of their ignorance of whether they will be harmed, unanimously choose a high level of coverage. The just level of coverage is greater than the existing $560 million. Second, the nature of economically efficient liability coverage is determined and contrasted with coverage that would emerge from a democratic system of public choice. Population and expected damage profiles indicate that majorities could easily be formed among groups of citizens expecting to suffer little of the damage of a nuclear accident. Thus, majority voting on liability arrangements is likely to produce an inefficiently low level of coverage

  9. ISSUES OF FETUS DRUG SAFETY

    Directory of Open Access Journals (Sweden)

    A.V. Ostrovskaya

    2010-01-01

    Full Text Available The article is focused on the issue of fetus drug safety. Development of a child’s health depends both on hereditary information and environment factors. The reason for deviation from the process of normal prenatal development could be any xenobiotics, physical factors and some medications having a pathogenic effect during pregnancy on the embryo and fetus. Due to that, the physician’s preventive work based on the knowledge of embryogenesis processes and critical development periods. Key words: teratogenic action, medications, prenatal development, congenital malformation, newborns, children.(Pediatric Pharmacology. – 2010; 7(1:25-28

  10. Corrosion issues in nuclear industry today

    International Nuclear Information System (INIS)

    Cattant, F.; Crusset, D.; Feron, D.

    2008-01-01

    In the context of global warming, nuclear energy is a carbon-free source of power and so is a meaningful option for energy production without CO 2 emissions. Currently, there are more than 440 commercial nuclear reactors, accounting for about 15% of electric power generation in the world, and there has not been a major accident in over 20 years. The world's fleet of nuclear power plants is, on average, more than 20 years old. Even though the design life of a nuclear power plant is typically 30 or 40 years, it is quite feasible that many nuclear power plants will be able to operate for longer than this. The re-emergence of nuclear power today is founded on the present generation of nuclear reactors meeting the demands of extended service life, ensuring the cost competitiveness of nuclear power and matching enhanced safety requirements. Nuclear power plant engineers should be able to demonstrate such integrity and reliability of their system materials and components as to enable nuclear power plants to operate beyond their initial design life. Effective waste management is another challenge for sustainable nuclear energy today; more precisely, a solution is needed for the management of high-level and long-lived intermediate-level radioactive waste over the very long term. Most nuclear countries are currently gathering the data needed to assess the feasibility of a deep geological waste repository, including the prediction of the behaviour of materials over several thousands of years. The extended service life of nuclear power plants and the need for permanent disposal for nuclear waste are today's key issues in the nuclear industry. We focus here on the major role that corrosion plays in these two factors, and on the French approaches to these two issues. (authors)

  11. Approaches that use seismic hazard results to address topics of nuclear power plant seismic safety, with application to the Charleston earthquake issue

    International Nuclear Information System (INIS)

    Sewell, R.T.; McGuire, R.K.; Toro, G.R.; Stepp, J.C.; Cornell, C.A.

    1990-01-01

    Plant seismic safety indicators include seismic hazard at the SSE (safe shut-down earthquake) acceleration, seismic margin, reliability against core damage, and reliability against offsite consequences. This work examines the key role of hazard analysis in evaluating these indicators and in making rational decisions regarding plant safety. The paper outlines approaches that use seismic hazard results as a basis for plant seismic safety evaluation and applies one of these approaches to the Charleston earthquake issue. This approach compares seismic hazard results that account for the Charleston tectonic interpretation, using the EPRI-Seismicity Owners Group (SOG) methodology, with hazard results that are consistent with historical tectonic interpretations accepted in regulation. Based on hazard results for a set of 21 eastern U.S. nuclear power plant sites, the comparison shows that no systematic 'plant-to-plant' increase in hazard accompanies the Charleston hypothesis; differences in mean hazards for the two interpretations are generally insignificant relative to current uncertainties in seismic hazard. (orig.)

  12. Interface between radiation protection and nuclear safety

    International Nuclear Information System (INIS)

    Bengtsson, G.; Hoegberg, L.

    1991-01-01

    Interface issues concern the character and management of overlaps between radiation protection and nuclear safety in nuclear power plants. Typical examples include the selection of inspection and maintenance volumes in order to balance occupational radiation doses versus the safety status of the plant, and the intentional release to the environment in the course of an accident in order to secure better plant control. The paper discusses whether it is desirable and possible to employ a consistent management of interface issues with trade-offs between nuclear safety and radiation protection. Illustrative examples are quoted from a major Nordic research programme on risk analysis and safety rationale. These concern for instance in-service inspections, modifications of plant systems and constructions after the plant has been taken into operation, and studies on the limitations of probabilistic safety assessment. They indicate that in general there are no simple rules for such trade-offs

  13. Safety of WWER type nuclear power plants - viewing from Hungary

    International Nuclear Information System (INIS)

    Voeroess, L.

    1991-01-01

    An evaluation of WWER type nuclear power plants operating in Hungary is given, relative to the safety requirements accepted internationally; how safe can they be regarded and what can be done to assure a high level of safety in all case. After an overview of general safety criteria, an overall description of WWER-440 type nuclear reactors is presented. Design safety, operational safety issues are treated in detail. Safety inspection and safety-related research and development is discussed. Regarding the future, five different issues associated with nuclear reactor safety should be considered. (R.P.) 20 refs.; 12 figs.; 3 tabs

  14. Progress of nuclear safety research, 1990

    International Nuclear Information System (INIS)

    1990-07-01

    Since the Japan Atomic Energy Research Institute (JAERI) was founded as a nonprofit, general research and development organization for the peaceful use of nuclear energy, it has actively pursued the research and development of nuclear energy. Nuclear energy is the primary source of energy in Japan where energy resources are scarce. The safety research is recognized at JAERI as one of the important issues to be clarified, and the safety research on nuclear power generation, nuclear fuel cycle, waste management and environmental safety has been conducted systematically since 1973. As of the end of 1989, 38 reactors were in operation in Japan, and the nuclear electric power generated in 1988 reached 29 % of the total electric power generated. 50 years have passed since nuclear fission was discovered in 1939. The objective of the safety research at JAERI is to earn public support and trust for the use of nuclear energy. The overview of the safety research at JAERI, fuel behavior, reliability of reactor structures and components, reactor thermal-hydraulics during LOCA, safety assessment of nuclear power plants and nuclear fuel cycle facilities, radioactive waste management and environmental radioactivity are reported. (K.I.)

  15. HSE Nuclear Safety Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Bagley, M.J. [Health and Safety Executive, Sheffield (United Kingdom)

    1995-12-31

    HSE funds two programmes of nuclear safety research: a programme of {approx} 2.2M of extramural research to support the Nuclear Safety Division`s regulatory activities and a programme of {approx} 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author).

  16. HSE Nuclear Safety Research Program

    International Nuclear Information System (INIS)

    Bagley, M.J.

    1995-01-01

    HSE funds two programmes of nuclear safety research: a programme of ∼ 2.2M of extramural research to support the Nuclear Safety Division's regulatory activities and a programme of ∼ 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author)

  17. Nuclear fusion: The issues

    International Nuclear Information System (INIS)

    Griffin, R.D.

    1993-01-01

    The taming of fusion energy, has proved one of the most elusive quests of modern science. For four decades, the United States has doggedly pursued energy's holy grail, pumping more than $9 billion into research and reactor prototypes. This year, the federal government is slated to spend $339 million on fusion, more than the combined amount the government will spend for research on oil, natural gas, solar power, wind power, geothermal energy, biofuels and conservation. This article summarizes the technical, political in terms of international cooperation, economic, planning, etc. issues surrounding the continued development of fusion as a possible power source for the next century. Brief descriptions of how fusion works and of the design of a tokamak fusion machine are included

  18. Progress in Nuclear Safety Reform of TEPCO

    International Nuclear Information System (INIS)

    Kawano, A.

    2016-01-01

    On March 29, 2014, TEPCO issued the Nuclear Safety Reform Plan describing the background cause of our Fukushima Nuclear Accident and our plan to challenge organizational and cultural change to avoid recurrence of such a tragic accident and to pursue the excellence in safety. This report will reflect that background cause with some specific examples and introduce how we are currently implementing this reform plan.

  19. Nuclear Cyber Security Issues and Policy Recommendations

    International Nuclear Information System (INIS)

    Lee, Cheol-Kwon; Lee, Dong-Young; Lee, Na-Young; Hwang, Young-Soo

    2015-01-01

    The cyber-attack against computer systems causes the loss of function which brings about the big economic loss, and it becomes a national-wide issue. In recent days the cyber threat has occurred in the national critical infrastructure around the world. In the nuclear industry, while discussing responses to various threats against nuclear facilities since 2006, cyber-terrorism was also discussed. But at that time, cyber-attacks against control networks in nuclear facilities were not seriously considered because those networks were isolated from the Internet thoroughly and it was evaluated that cyber penetration would not be possible. However Stuxnet worm virus which attacked Iran's nuclear facilities confirmed that the cyber security problem could occur even in other nuclear facilities. The facilities were isolated from the Internet. After the cyber incident, we began to discuss the topic of NPP cyber security. It is very difficult to predict whether or when or how the cyber-attack will be occurred, which is a characteristic of cyber-attack. They could be always detected only after when an incident had occurred. This paper summarizes the report, 'Nuclear Cyber Security Issues and Policy Recommendations' by issue committee in the Korea Nuclear Society, which reviewed the cyber security framework for nuclear facilities in the Republic of Korea being established to prevent nuclear facilities from cyber-attacks and to respond systematically. As a result this paper proposes several comments to improve the security and furthermore safety of nuclear facilities Digital technology will be used more widely at the national critical infrastructure including nuclear facilities in the future, and moreover wireless technologies and mobile devices will be soon introduced to nuclear industry. It is therefore anticipated that the rapid advance in digital technology will accelerate the opportunity of hacking these facilities

  20. Nuclear Cyber Security Issues and Policy Recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Cheol-Kwon; Lee, Dong-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Na-Young; Hwang, Young-Soo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2015-10-15

    The cyber-attack against computer systems causes the loss of function which brings about the big economic loss, and it becomes a national-wide issue. In recent days the cyber threat has occurred in the national critical infrastructure around the world. In the nuclear industry, while discussing responses to various threats against nuclear facilities since 2006, cyber-terrorism was also discussed. But at that time, cyber-attacks against control networks in nuclear facilities were not seriously considered because those networks were isolated from the Internet thoroughly and it was evaluated that cyber penetration would not be possible. However Stuxnet worm virus which attacked Iran's nuclear facilities confirmed that the cyber security problem could occur even in other nuclear facilities. The facilities were isolated from the Internet. After the cyber incident, we began to discuss the topic of NPP cyber security. It is very difficult to predict whether or when or how the cyber-attack will be occurred, which is a characteristic of cyber-attack. They could be always detected only after when an incident had occurred. This paper summarizes the report, 'Nuclear Cyber Security Issues and Policy Recommendations' by issue committee in the Korea Nuclear Society, which reviewed the cyber security framework for nuclear facilities in the Republic of Korea being established to prevent nuclear facilities from cyber-attacks and to respond systematically. As a result this paper proposes several comments to improve the security and furthermore safety of nuclear facilities Digital technology will be used more widely at the national critical infrastructure including nuclear facilities in the future, and moreover wireless technologies and mobile devices will be soon introduced to nuclear industry. It is therefore anticipated that the rapid advance in digital technology will accelerate the opportunity of hacking these facilities.

  1. White paper on nuclear safety in 1981

    International Nuclear Information System (INIS)

    1981-01-01

    The measures to research, develop and utilize atomic energy in Japan have been strengthened since the Atomic Energy Act was instituted in 1955, always on the major premise of securing the safety. The Nuclear Safety Commission established in October, 1978, has executed various measures to protect the health and safety of the nation as the center of the atomic energy safety regulation administration in Japan. Now, the Nuclear Safety Commission has published this annual report on atomic energy safety, summarizing various activities for securing the safety of atomic energy since its establishment to the end of March, 1981. This report is the inaugural issue, and the course till the Nuclear Safety Commission has made its start is also described. The report is composed of general remarks, response to the TMI accident, the safety regulation and security of nuclear facilities, the treatment and disposal of radioactive wastes, the investigation of environmental radioactivity, the countermeasures for preventing disasters around nuclear power stations and others, the research on the safety of atomic energy, international cooperation, and the improvement of the basis for securing the safety. Various related materials are attached. (Kako, I.)

  2. No nuclear safety without security

    International Nuclear Information System (INIS)

    Anon.

    2016-01-01

    ead of Health and Safety - Nuclear Safety and Corporate Security at ENGIE Benelux, Pierre Doumont has the delicate job of defining and implementing measures, including cybersecurity, to prevent the risk of malevolent acts against tangible and intangible assets. He gives some hints on the contribution of nuclear security to safety.

  3. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  4. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  5. Nuclear and radiation safety policy

    International Nuclear Information System (INIS)

    Mikus, T; Strycek, E.

    1998-01-01

    Slovenske elektrarne (SE) is a producer of electricity and heat, including from nuclear fuel source. The board of SE is ultimately responsible for nuclear and radiation safety matters. In this leaflet main principles of maintaining nuclear and radiation safety of the Company SE are explained

  6. 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)

  7. 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).

  8. Food control concept: Food safety/ingestion issues

    International Nuclear Information System (INIS)

    Armstrong, B.

    1995-01-01

    This talk outlines the issues in food safety/ingestion in the case of radiation accidents at nuclear power plants and how emergency preparedness plans can/should be tailored. The major topics are as follows: In Washington: food safety/ingestion issues exist at transition between response and regulatory worlds; agricultural concerns; customer concerns; Three Mile Island: detailed maps; development of response procedures; development of tools; legal issues

  9. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1983-06-01

    The unresolved safety issues summary is designed to provide the management of the nuclear regulatory commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to congress pursuant to section 210 of the Energy Reorganization Act of 1974 as amended. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  10. Nuclear safety in EU candidate countries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    Nuclear safety in the candidate countries to the European Union is a major issue that needs to be addressed in the framework of the enlargement process. Therefore WENRA members considered it was their duty to offer their technical assistance to their Governments and the European Union Institutions. They decided to express their collective opinion on nuclear safety in those candidate countries having at least one nuclear power plant: Bulgaria, the Czech Republic, Hungary, Lithuania, Romania, Slovakia and Slovenia. The report is structured as follows: A foreword including background information, structure of the report and the methodology used, General conclusions of WENRA members reflecting their collective opinion, For each candidate country, an executive summary, a chapter on the status of the regulatory regime and regulatory body, and a chapter on the nuclear power plant safety status. Two annexes are added to address the generic safety characteristics and safety issues for RBMK and VVER plants. The report does not cover radiation protection and decommissioning issues, while safety aspects of spent fuel and radioactive waste management are only covered as regards on-site provisions. In order to produce this report, WENRA used different means: For the chapters on the regulatory regimes and regulatory bodies, experts from WENRA did the work. For the chapters on nuclear power plant safety status, experts from WENRA and from French and German technical support organisations did the work. Taking into account the contents of these chapters, WENRA has formulated its general conclusions in this report.

  11. Nuclear safety in EU candidate countries

    International Nuclear Information System (INIS)

    2000-10-01

    Nuclear safety in the candidate countries to the European Union is a major issue that needs to be addressed in the framework of the enlargement process. Therefore WENRA members considered it was their duty to offer their technical assistance to their Governments and the European Union Institutions. They decided to express their collective opinion on nuclear safety in those candidate countries having at least one nuclear power plant: Bulgaria, the Czech Republic, Hungary, Lithuania, Romania, Slovakia and Slovenia. The report is structured as follows: A foreword including background information, structure of the report and the methodology used, General conclusions of WENRA members reflecting their collective opinion, For each candidate country, an executive summary, a chapter on the status of the regulatory regime and regulatory body, and a chapter on the nuclear power plant safety status. Two annexes are added to address the generic safety characteristics and safety issues for RBMK and VVER plants. The report does not cover radiation protection and decommissioning issues, while safety aspects of spent fuel and radioactive waste management are only covered as regards on-site provisions. In order to produce this report, WENRA used different means: For the chapters on the regulatory regimes and regulatory bodies, experts from WENRA did the work. For the chapters on nuclear power plant safety status, experts from WENRA and from French and German technical support organisations did the work. Taking into account the contents of these chapters, WENRA has formulated its general conclusions in this report

  12. Some Major Issues Influencing Nuclear Energy Prospective

    International Nuclear Information System (INIS)

    Feretic, D.

    2012-01-01

    The presentation analyses some issues which are of particular importance for future nuclear power application. These include duration of uranium reserves and high level radioactive waste decay period in function of uranium reserves (determined, assumed and speculative) and type of fuel cycle used. Public acceptance during essential historical milestones of nuclear power use, influence of safety and compatibility evaluations, quantified risk, externalities and nuclear accidents. Short review of major accidents, causes, consequences, impact of LNT and hormesis hypothesis. Particular problem for future of nuclear power is potential shortage of experienced personnel due to long period without plants construction. To address some of problems which may face future investors a brief review of specific events experienced during construction of NPP Krsko is presented. Such events could be of interest to countries planning to construct nuclear power plant.(author).

  13. Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Applications - Workshop Proceedings, CFD4NRS-3 - Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues

    International Nuclear Information System (INIS)

    2012-01-01

    related to nuclear reactor safety issues. The conference consisted of 14 technical sessions. Among the topics included were containment, advanced reactors, multiphase flows, flow in a rod bundle, fire analysis, flows in dry casks, thermal analysis, mixing flows and pressurized thermal shock (PTS). About 1/3 of the papers were concerned with two-phase flow issues and the rest were devoted to single-phase CFD validation. South Korea is a candidate to host a follow-up meeting scheduled in 2012, organized by KAERI. KAERI also volunteered to sponsor and organize the second OECD/NEA CFD benchmark exercise. In the closure meeting after the panel session discussion, the representative from the Paul Scherrer Institut (PSI) proposed to host a future workshop scheduled for 2014, and to organize and sponsor the third OECD/NEA benchmark exercise based on a stratification experiment in the PANDA facility at PSI. The great majority of participants were interested in attending a follow-up workshop within two years. Comments were made during the panel session on the content of CFD4NRS-3. Two of the comments are that experiments can provide insight into the physics, and that CFD is now an accepted analysis tool, though it is very important to follow BPGs. There was a consensus on the need to maintain the high quality of the papers. The promotion of international benchmarking exercises for CFD was strongly encouraged. Another comment suggested that such workshops should be a forum to discuss novel approaches, but that one must also keep in mind that the end users are people from the nuclear safety community. The CFD4NRS, XCFD4NRS and CFD4NRS-3 workshops have proved to be very valuable means to assess the status of CFD code capabilities and validation, to exchange experiences in CFD code applications, and to monitor future progress

  14. Perspectives on managing nuclear safety at Cernavoda NPP past, present and future

    International Nuclear Information System (INIS)

    Serban, M.

    1997-01-01

    The presentation considers the following issues: background of Romanian nuclear programme; 1990 management issues involved in Cernavoda project, nuclear safety perspectives; Cernavoda U1 operating organization today (safety related issues); good practices at Cernavoda NPP

  15. Perspectives on managing nuclear safety at Cernavoda NPP past, present and future

    Energy Technology Data Exchange (ETDEWEB)

    Serban, M [Technical Safety Directorate, Unit 1., Cernavoda Nuclear Power Plant (Romania)

    1997-12-01

    The presentation considers the following issues: background of Romanian nuclear programme; 1990 management issues involved in Cernavoda project, nuclear safety perspectives; Cernavoda U1 operating organization today (safety related issues); good practices at Cernavoda NPP.

  16. White paper on nuclear safety in 2009

    International Nuclear Information System (INIS)

    2009-06-01

    It deals with a general introduction of nuclear safety like general safety, safety regulation and system law and standard. It indicates of nuclear energy facility safety about general safety, safety regulation of operating nuclear power plant safety regulation under constructing nuclear power plant. It deals with radiation facility safety, monitoring of environmental radiation, radiation protection, radiation control, international cooperating on nuclear energy safety and establishment of safety regulation.

  17. Safety issues on advanced fuel

    Energy Technology Data Exchange (ETDEWEB)

    Gross, H.; Krebs, W.D. [Siemens AG, Bereich Energieerzeugug (KWU), Erlangen (Germany). Geschaeftsgebiet Nukleare Energieerzeugung

    1998-05-01

    In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [Deutsch] In den letzten Jahren hat eine allgemeine Diskussion begonnen, ob mit fortgeschrittenen Brennelementen (BE) ungeklaerte Sicherheitsprobleme verbunden sind. Dabei ist `Fortgeschrittene Brennelemente` ein Sammelbegriff fuer hohe Abbraende, verbesserte Huellrohrmaterialien, Low-leakage-Einsatzplanungen mit hohen Heissstellenfaktoren usw. Die Auslegungsstoerfaelle RIA und Loca sind in dieser Diskussion von besonderer Bedeutung. Aus der Sicht von Siemens ist der RIA kein Sicherheitsproblem. Zwischen den mit modernen 3D-Methoden berechneten Enthalpieerhoehungen und den in RIA-Experimenten aufgetretenen Brennstabdefekten bestehen ausreichende Abstaende, wenn der Einfluss der Pulsbreite beruecksichtigt wird. Die Untersuchung eventueller Unsicherheiten bei hohen

  18. Nuclear reactor safety

    International Nuclear Information System (INIS)

    Buhl, A.R.

    1979-01-01

    Dr. Buhl feels that nuclear-energy issues are too complex to be understood as single topics, and can only be understood in relationship to broader issues. In fact, goals and risks associated with all energy options must be seen as interrelated with other broad issues, and it should be understood that there are presently no clearcut criteria to ensure that the best decisions are made. The technical community is responsible for helping the public to understand the basic incompatibility of hard and soft technologies and that there is no risk-free energy source. Four principles are outlined for assessing the risks of various energy technologies: (1) take a holistic view; (2) compare the risk with the unit energy output; (3) compare the risk with those of everyday activities; and (4) identify unusual risks associated with a particular option. Dr. Buhl refers to the study conducted by Dr. Inhaber of Canada who used this approach and concluded that nuclear power and natural gas have the lowest overall risk

  19. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

  20. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

  1. Prospects for nuclear safety research

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-04-01

    This document is the text of a paper presented by Eric S. Beckjord (Director, Nuclear Regulatory Research/NRC) at the 22nd Water Reactor Safety Meeting in Bethesda, MD in October 1994. The following topics are briefly reviewed: (1) Reactor vessel research, (2) Probabilistic risk assessment, (3) Direct containment heating, (4) Advanced LWR research, (5) Nuclear energy prospects in the US, and (6) Future nuclear safety research. Subtopics within the last category include economics, waste disposal, and health and safety.

  2. Reperes, the information magazine of the Institute for Radiation Protection and Nuclear Safety - IRSN, No. 12 - January 2012, Special issue Fukushima - First lessons from the accident

    International Nuclear Information System (INIS)

    2012-01-01

    A first set of articles addresses the nuclear crisis in Japan (description of the accident, information mission sent by France, and support actions undertaken by France in Japan in the fields of education, civilian security, culture, sailing, media, dosimeters, robotics). A second set discusses lessons learned in terms of nuclear safety (complementary safety assessments, stress test in Gravelines), radiological consequences (impact on Japanese population, the Symbiose software, the Teleray network), crisis management, and research

  3. 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.)

  4. File: nuclear safety and transparency

    International Nuclear Information System (INIS)

    Martinez, J.P.; Etchegoyen, A.; Jeandron, C.

    2001-01-01

    Several experiences of nuclear safety and transparency are related in this file. Public information, access to documents, transparency in nuclear regulation are such subjects developed in this debate. (N.C.)

  5. Nuclear Safety in Central and Eastern Europe

    International Nuclear Information System (INIS)

    2001-04-01

    Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union. In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the ''Performance Evaluation Guide'', which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body. Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary

  6. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-06-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the third volume of a three-volume series, addresses the status of generic safety issues (GSIs) at licensed plants. Volume 1 addressed the status of Three Mile Island Action Plan requirements and was published in March 1991. Volume 2 addressed the status of implementation and verification of unresolved safety issues and was published in May 1991. The annual NUREG report will combine these three areas in a single volume to be published in late 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 34 GSIs and sub-issues that have been resolved by the NRC and involve implementation of an action or actions by licensees. This NUREG report also serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until a request for action by licensees is issued by NRC. 3 figs., 6 tabs

  7. Research of beryllium safety issues

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Dolan, T.J.; Hankins, M.R.; Pawelko, R.J.

    1993-01-01

    Beryllium has been identified as a leading contender for the plasma-facing material in ITER. Its use has some obvious advantages, but there are also a number of safety concerns associated with it. The Idaho National Engineering Laboratory (INEL) has undertaken a number of studies to help resolve some of these issues. One issue is the response of beryllium to neutron irradiation. We have tested samples irradiated in the Advanced Test Reactor (ATR) and are currently preparing to make measurements of the change in mechanical properties of beryllium samples irradiated at elevated temperatures in the Fast Flux Test Facility (FFTF) and the Experimental Breeder Reactor II (EBR-II) at the INEL. Mechanical tests will be conducted at the irradiation temperatures of 375-550 C. Other experiments address permeation and retention of implanted tritium in plasma-sprayed beryllium. In one test the porosity of the material allowed 0.12% of implanted ions and 0.17% of atoms from background gas pressure to pass through the foil with essentially no delay. For comparison, similar tests on fully dense hot-rolled, vacuum melted or sintered powder foils of high purity beryllium showed only 0.001% of implanting ions to pass through the foil, and then only after a delay of several hours. None of the molecular gas appeared to permeate these latter targets. An implication is that plasma-sprayed beryllium may substantially enhance recycling of tritium to the plasma provided it is affixed to a relatively impermeable substrate. (orig.)

  8. Regulatory oversight on nuclear safety in Taiwan

    Energy Technology Data Exchange (ETDEWEB)

    Huang, T-T. [Atomic Energy Council, New Taipei City, Taiwan (China)

    2014-07-01

    Taiwan is a densely populated island and over 98% of its energy is imported, 16.5% of which is nuclear, in the form of materials and services. Ensuring that the most stringent nuclear safety standards are met therefore remains a priority for the government and the operator, Taiwan power Company (Taipower). There are eight nuclear power reactors in Taiwan, six of which are in operation and two are under construction. The first began operating nearly 40 years ago. For the time being the issue of whether to decommission or extend life of the operating units is also being discussed and has no conclusion yet. Nuclear energy has been a hot issue in debate over the past decades in Taiwan. Construction of Lungmen nuclear power plant, site selection of a final low-level waste disposal facility, installation of spent fuel dry storage facilities and safety of the currently operating nuclear power reactors are the issues that all Taiwanese are concerned most. In order to ensure the safety of nuclear power plant, the Atomic Energy Council (AEC) has implemented rigorous regulatory work over the past decades. After the Fukushima accident, AEC has conducted a reassessment program to re-evaluate all nuclear power plants in Taiwan, and asked Taipower to follow the technical guidelines, which ENSREG has utilized to implement stress test over nuclear power plants in Europe. In addition, AEC has invited two expert teams from OECD/NEA and ENSREG to conduct peer reviews of Taiwan's stress test national report in 2013. My presentation will focus on activities regulating safety of nuclear power programs. These will cover (A) policy of nuclear power regulation in Taiwan, (B)challenges of the Lungmen Plant, (C) post-Fukushima safety re-assessment, and (D)radioactive waste management. (author)

  9. Nuclear safety organisation in France

    International Nuclear Information System (INIS)

    1979-12-01

    This report outlines the public authorities responsible for the safety of nuclear installations in France. The composition and responsibilities of the Central Safety Service of Nuclear Installations within the Ministry of Industry, the Institute of Nuclear Protection and Safety within the CEA, the Central Service of Protection Against Ionising Radiation and the Interministerial Committee of Nuclear Safety are given. Other areas covered include the technical safety examination of large nuclear installations, the occurrence of accidents, treatment and control of release of radioactive wastes and decommissioning. The section on regulations covers the authorisation procedure, plant commissioning, release of radioactive effluents, surveillance and protection of workers exposed to ionising radiation. The situation is compared with the USA and the Federal Republic of Germany. A list of commercial nuclear installations in France is given

  10. Nuclear power: safety and prospects

    International Nuclear Information System (INIS)

    Miniere, D.

    2012-01-01

    Despite the Fukushima accident new countries are willing to use nuclear power and as a nuclear accident somewhere is a nuclear accident everywhere, all countries are concerned with nuclear safety. A big association that would gather all the national Safety Authorities would be an efficient tool to promote and improve safety at the world scale and may be the unique available tool as no country would let a foreign authority to drive its own nuclear industry. An important lesson from Fukushima and Chernobyl accidents is that the signature of a big nuclear accident is not the number of casualties (it will always be limited) but the importance of the radioactive contamination. The question is how to make this long-term and long-range contamination impossible to happen, it is the mission of nuclear safety. (A.C.)

  11. Site evaluation for nuclear installations. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

  12. Unresolved safety issues: where do we go from here

    International Nuclear Information System (INIS)

    Aycock, M.B.

    1980-01-01

    Section 210 of the Energy reorganization Act of 1974, as amended requires the NRC to develop a program for resolving Unresolved Safety Issues related to nuclear power plants. Seventeen Unresolved Safety Issues were identified by the NRC in 1978 and by early 1979 the NRC Unresolved Safety Issues Program was quickly becoming a well defined and manageable effort. Although, the Three Mile Island accident caused the momentum developed in early 1979 to be lost, efforts on ongoing generic tasks were continued by a special NRC Task Force established in June 1979. The momentum that was lost must be regained, however, if the Congressional mandate in Section 210 is to be met. With increased industry involvement and the marriage of the Unresolved Safety Issues Program with the improved and broader safety program development, audit and evaluation activities of the new NRR Division of Safety Technology, this should be possible

  13. Nuclear safety review for the year 1997

    International Nuclear Information System (INIS)

    1998-12-01

    The Nuclear Safety Review attempts to summarize the global nuclear safety scene during 1997. It starts with discussion of significant safety related events worldwide: International cooperation; reactor facilities; radioactive waste management; medical uses of radiation sources; events at other facilities and transport of radioactive material. This is followed by a description of principal IAEA activities that contributed to global nuclear safety, namely: legally binding international agreements; non-binding safety standards and their application. The third part highlights developments in Member States as they reported them. The review closes with a description of issues that are likely to be prominent in the coming year(s). A draft version was submitted to the March 1998 session of the IAEA Board of Governors, and this final version has been prepared in light of the discussion in the Board and was submitted for information to the 42nd session of the IAEA General Conference

  14. Nuclear Safety Review for the Year 2009

    International Nuclear Information System (INIS)

    2010-07-01

    The global nuclear community is experiencing a period of dynamic change. The introduction of new nuclear power plants, the rapid expansion of existing nuclear power programmes and the wider use of radioactive sources and ionizing radiation in general highlight the need for continued and improved international cooperation to address the associated challenges. The increasingly multinational nature of today's nuclear business and activities underscores this need. In this context, it is particularly important to note that the establishment of adequate safety infrastructure and capacity cannot be left to fall behind. The safety performance of the nuclear industry has remained at a high level. Various safety performance indicators, such as those related to unplanned reactor shutdowns, safety equipment availability, radiation exposures to workers, radioactive waste management and radioactive releases to the environment have shown steady improvement over the past two decades, with some levelling off in recent years. Nevertheless, it is necessary to avoid complacency and to continuously improve and strengthen the existing global nuclear safety and security regime so that nuclear technologies can be introduced or their use expanded in a safe and secure manner to meet the world's needs for human well-being and socio-economic development. The Agency continues to support and promote increased participation in the global nuclear safety and security regime as a framework for achieving high levels of safety in nuclear activities worldwide. Through consideration of the global trends, issues and challenges observed in 2009, four key themes in global nuclear safety were identified: 1) continuing international cooperation and emerging coordination for new and expanding nuclear power programmes; 2) improving the long term management of radioactive and nuclear materials; 3) capacity building for sustainable nuclear safety; and 4) strengthening global and regional networking activities

  15. Effectiveness of the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Schwarz, G.

    2016-01-01

    The Convention on Nuclear Safety (CNS) has been established after the Chernobyl accident with the primary objective of achieving and maintaining a high level of nuclear safety worldwide, through the enhancement of national measures and international cooperation. The CNS is an incentive convention. It defines the basic safety standard which shall be met by the Contracting Parties. The verification of compliance is based on a self-assessment by the Countries and a Peer Review by the other Contracting Parties. As of July 2015, there are 78 Contracting Parties. Among the Contracting Parties of the Convention are all countries operating nuclear power plants except the Islamic Republic of Iran and Taiwan, all countries constructing nuclear power plants, all countries having nuclear power plants in long term shutdown and all countries having signed contracts for the construction of nuclear power plants. The National Reports under the CNS therefore cover almost all nuclear power plants of the world. The peer review of reports, questions and answers that are exchanged in connection with the Review Meetings provided a unique overview of nuclear safety provisions and issues in countries planning or operating nuclear power plants. This is especially important for neighbouring countries to those operating nuclear power plants.

  16. Nuclear safety review for 1984

    International Nuclear Information System (INIS)

    1985-08-01

    This publication is based on the fourth Nuclear Safety Review prepared by the IAEA Secretariat for presentation to the Board of Governors. It discusses relevant international activities in 1984 and the current status of nuclear safety and radiation protection, and looks ahead to anticipated developments

  17. Nuclear safety legislation and supervision in China

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1991-02-01

    The cause for the urgent need of nuclear safety legislation and supervision in China is firstly described, and then a brief introduction to the basic principle and guideline of nuclear safety is presented. Finally the elaboration on the establishment of nuclear safety regulatory system, the enactment of a series of regulations and safety guides, and the implementation of licencing, nuclear safety supervision and research for ensuring the safety of nuclear energy, since the founding of the National Nuclear Safety Administration, are introduced

  18. Maintenance as a safety issue.

    Science.gov (United States)

    White, Jim

    2008-11-01

    Because safety is related to electrical power systems maintenance, it seems reasonable to assume there could be legal issues if maintenance is not performed. OSHA has not yet taken the stand that not performing maintenance as required by the manufacturer, NFPA 70B, or ANSI/NETA MTS-07 constitutes a willful violation. OSHA defines a willful citation as one where: "the employer knowingly commits with plain indifference to the law. The employer either knows that what he or she is doing constitutes a violation, or is aware that a hazardous condition existed and made no reasonable effort to eliminate it". However, NFPA 70E 2009 requires this maintenance, and OSHA has stated on its Web site that NFPA 70E is "a guide for meeting the requirements of the OSHA electrical regulations". In addition, federal courts have found that NFPA 70E is "standard industry practice." Once a company receives and accepts a willful citation, especially if received as the result of an accident investigation, its worker's compensation protection no longer shields it. One definition given by a trial attorney for a willful citation was that it is equal to negligent behavior. Be smart: Maintain that equipment and save yourself major problems, including unscheduled shutdowns and possible litigation.

  19. Organizational factors in nuclear safety

    International Nuclear Information System (INIS)

    Wilpert, Bernhard

    2000-01-01

    The overall picture of factors which contributed to the event presents a panorama of a NPP where organizational and managerial characteristics were intricately intertwined and emerged as crucial for a general deterioration of the plant's capabilities to continually correct its deficiencies and optimize its operations. In the following author shall attempt to first cover various important efforts to modeling organizational factors relevant to safety. The second part of my presentation will offer an attempt towards an integrative model. The third part concludes with an agenda for research and practice. Most of the twelve different approaches above attempt to consider safety relevant organizational factors by way of pragmatic classifications. Together with their sub-categories we can count close to 160 different factors on various levels of abstraction. This is tantamount to say that most approaches lack systematic theoretical underpinnings. Thus then arises the question whether we need to develop a generic model, which promises to encompass these three major approaches altogether. Practical issues emerge particularly in the domain of organizational development, i.e. the goal oriented efforts to change the structures and the functioning of nuclear operations in such a way that the desired outputs in terms safety and reliability result in a sustained fashion. Again, these practical concerns are intimately related to developments and advances in theory and methodology. Only a close cooperation among scientists from various disciplines and of practitioners holds the promise of adequately understanding and use of organizational factors in future improving the safety record of nuclear industry worldwide. (S.Y.)

  20. Japan reforms its nuclear safety

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    The Fukushima Daiichi NPP accident deeply questioned the bases of nuclear safety and nuclear safety regulation in Japan. It also resulted in a considerable loss of public confidence in the safety of nuclear power across the world. Although the accident was caused by natural phenomena, institutional and human factors also largely contributed to its devastating consequences, as shown by the Japanese Diet's and Government's investigation reports. 'Both regulators and licensees were held responsible and decided to fully reconsider the existing approaches to nuclear safety. Consequently, the regulatory system underwent extensive reform based on the lessons learned from the accident,' Yoshihiro Nakagome, the President of Japan Nuclear Energy Safety Organisation, an ETSON member TSO, explains. (orig.)

  1. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-05-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the second volume of a three-volume series, addresses the status of unresolved safety issues (USIs) at licensed plants. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 27 safety issues designated as USIs and to make this information available to other interested parties, including the public. A corollary purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants. 3 figs., 4 tabs

  2. Technical safety Organisations (TSO) contribute to European Nuclear Safety

    International Nuclear Information System (INIS)

    Repussard, J.

    2010-01-01

    Nuclear safety and radiation protection rely on science to achieve high level prevention objectives, through the analysis of safety files proposed by the licensees. The necessary expertise needs to be exercised so as to ensure adequate independence from nuclear operators, appropriate implementation of state of the art knowledge, and a broad spectrum of analysis, adequately ranking the positive and negative points of the safety files. The absence of a Europe-wide nuclear safety regime is extremely costly for an industry which has to cope with a highly competitive and open international environment, but has to comply with fragmented national regulatory systems. Harmonization is therefore critical, but such a goal is difficult to achieve. Only a gradual policy, made up of planned steps in each of the three key dimensions of the problem (energy policy at EU level, regulatory harmonization, consolidation of Europe-wide technical expertise capability) can be successful to achieve the required integration on the basis of the highest safety levels. TSO's contribute to this consolidation, with the support of the EC, in the fields of research (EURATOM-Programmes), of experience feedback analysis (European Clearinghouse), of training and knowledge management (European Training and Tutoring Institute, EUROSAFE). The TSO's network, ETSON, is becoming a formal organisation, able to enter into formal dialogue with EU institutions. However, nuclear safety nevertheless remains a world wide issue, requiring intensive international cooperation, including on TSO issues. (author)

  3. Special issue: the nuclear industry in Europe

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    This special issue contains papers on the following topics: French nuclear policy; nuclear energy development in Europe; nuclear diversification; Alsthom-Atlantique in the nuclear field; 1981 nuclear electricity generation; EDF siting policy; the N4 model of the 1300 MW series; Creys-Malville; the nuclear industry in Europe; pumps in the nuclear industry [fr

  4. 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.

  5. 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

  6. Nuclear Safety Review for the Year 2008

    International Nuclear Information System (INIS)

    2009-07-01

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

  7. Safety philosophy for nuclear power plants in egypt

    International Nuclear Information System (INIS)

    Mervat, S.A.; Hammad, F.H.

    1988-01-01

    This work establishes the basic principles of a safety philosophy for nuclear power plants in egypt. A number of deterministic requirements stemming the multiple barriers and the defense-in-depth concept are emphasised. other requirements in the areas of siting, operational safety, safety analysis, special issues, and experience feedback are also identified. The role of international cooperation in nuclear safety technology-transfer and nuclear emergencies is highlighted. In addition probabilistic ally based guidelines are set for acceptable risk and dose limits

  8. Operational safety of nuclear power plants

    International Nuclear Information System (INIS)

    Tanguy, P.

    1987-01-01

    The operational safety of nuclear power plants has become an important safety issue since the Chernobyl accident. A description is given of the various aspects of operational safety, including the importance of human factors, responsibility, the role and training of the operator, the operator-machine interface, commissioning and operating procedures, experience feedback, and maintenance. The lessons to be learnt from Chernobyl are considered with respect to operator errors and the management of severe accidents. Training of personnel, operating experience feedback, actions to be taken in case of severe accidents, and international cooperation in the field of operational safety, are also discussed. (U.K.)

  9. Nuclear safety review for the year 2000

    International Nuclear Information System (INIS)

    2001-06-01

    The nuclear safety review for the year 2000 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts: Part 1 describes those events in 2000 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety; Part 2 describes some of the IAEA efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2000. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2000; Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2000 was presented to the March 2001 session of the IAEA Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2001 that were considered pertinent to the discussion of events during 2000. In such cases, a note containing the more recent information has been provided in the form of a footnote

  10. Women and the nuclear issue

    International Nuclear Information System (INIS)

    Locke, David

    1989-01-01

    From the opinion surveys it was concluded that women do have different attitudes towards nuclear power compared to men. Women are more likely to be suspicious of nuclear power, mention the problem areas and less likely to mention benefits. The reasons for this are not difficult to understand, with, for example, the media highlighting the dangers of nuclear power, in particular the hazards of radiation as it affects people, especially children. The majority of women associate nuclear power with weapons and radiation, though specific fears about cancer including leukaemia are not as strong as might be expected. The major issue is still the disposal of waste, though for a time after Chernobyl the major nuclear accident superseded this. Women tend to be more confused by the wide range of issues presented to them and the contradictory attitudes. In our experience about twice as many women as men admit to being a d on't know . Women are more concerned with people and the environment than men. Men are more inclined to be brought up from an early age to be machine minded and they tend as a result to be more sympathetic towards the use of technology in society. It is not necessarily true that women are more 'anti-nuclear' although this does come out in many opinion polls. I think that women react to the leading question as to whether they are 'in favour' or 'not' of nuclear power by responding negatively because of their confusion. We have asked similar questions in our own opinion surveys but have given the opportunity for the respondent to declare a positive attitude towards nuclear power 'with reservations'. If they are allowed to express their reservations they often come to the conclusion in an intuitive way that nuclear power will be needed in the next century to provide energy for their children when the oil and gas run out and the coal is used to substitute for the hydrocarbons. A 'necessary evil' as one person put it. In the main our recommendation is that although

  11. Women and the nuclear issue

    Energy Technology Data Exchange (ETDEWEB)

    Locke, David [UKAEA (United Kingdom)

    1989-07-01

    From the opinion surveys it was concluded that women do have different attitudes towards nuclear power compared to men. Women are more likely to be suspicious of nuclear power, mention the problem areas and less likely to mention benefits. The reasons for this are not difficult to understand, with, for example, the media highlighting the dangers of nuclear power, in particular the hazards of radiation as it affects people, especially children. The majority of women associate nuclear power with weapons and radiation, though specific fears about cancer including leukaemia are not as strong as might be expected. The major issue is still the disposal of waste, though for a time after Chernobyl the major nuclear accident superseded this. Women tend to be more confused by the wide range of issues presented to them and the contradictory attitudes. In our experience about twice as many women as men admit to being a ''don't know''. Women are more concerned with people and the environment than men. Men are more inclined to be brought up from an early age to be machine minded and they tend as a result to be more sympathetic towards the use of technology in society. It is not necessarily true that women are more 'anti-nuclear' although this does come out in many opinion polls. I think that women react to the leading question as to whether they are 'in favour' or 'not' of nuclear power by responding negatively because of their confusion. We have asked similar questions in our own opinion surveys but have given the opportunity for the respondent to declare a positive attitude towards nuclear power 'with reservations'. If they are allowed to express their reservations they often come to the conclusion in an intuitive way that nuclear power will be needed in the next century to provide energy for their children when the oil and gas run out and the coal is used to substitute for the hydrocarbons. A 'necessary evil' as one person put it. In the main our recommendation is that

  12. Relevant safety issues in designing the HTR-10 reactor

    International Nuclear Information System (INIS)

    Sun Yuliang; Xu Yuanghui

    2001-01-01

    The HTR-10 is a 10 MWth pebble bed high temperature gas cooled reactor being constructed as a research facility at the Institute of Nuclear Energy Technology. This paper discusses design issues of the HTR-10 which are related to safety. It addresses the safety criteria used in the development and assessment of the design, the safety important systems, and the safety classification of components. It also summarises the results of safety analysis, including the approach used for the radioactive source term, as well as the approach to containment design. (author)

  13. Nuclear power: Siting and safety

    International Nuclear Information System (INIS)

    Openshaw, S.

    1986-01-01

    By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

  14. Radiological protection and nuclear safety postgraduate course

    International Nuclear Information System (INIS)

    Segado, R.C.; Menossi, C.A.

    1998-01-01

    Full text: The first Radiation Protection and Nuclear Safety Postgraduate Course was held in 1977, when the former Radioprotection and Nuclear Safety Branch of the National Atomic Energy Commission decided implement that course for the qualification of its professionals. After then, in 1980, by agreement between the CNEA, the National University of Buenos Aires and the Ministry of Health and Social Welfare got its present academic qualification as a Post-Graduate Course. Since then, it was sponsored by the IAEA. This Organization annually grants fellowships to fifteen students from different countries. Up to now, twenty consecutive courses have been delivered and more than five hundredth graduated, more than half of them coming from abroad. The aim of the course is the qualification and training in Radiological Protection and Nuclear Safety of those professionals involved in the design, construction, operation and decommissioning of Nuclear and Radioactive Installation and their related regulatory issues. (author) [es

  15. The role of nuclear law in nuclear safety after Fukushima

    International Nuclear Information System (INIS)

    Cardozo, Diva E. Puig

    2013-01-01

    The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor

  16. Nuclear safety and nuclear insurance

    International Nuclear Information System (INIS)

    Abramovitz, A.

    1983-01-01

    To an extent, public opinion is against Koeberg, inspite of the fact that Escom, Koeberg's prospective licensee, are liable for damages caused in the event of an accident, that they carry public liability insurance bought in the market place to the maximum of ten million rand, and if that is not enough the government will take over responsibility for the rest. A question is put that if this kind of protection carries on, won't there always be a minority of the public who will find nuclear power socially, psychologically and politically unacceptable

  17. Strategies for nuclear safety

    International Nuclear Information System (INIS)

    Cetto, A.M.; Taniguchi, T.

    2006-01-01

    Please Rarely in the history of the IAEA has radiation-based technology provided so much opportunity and presented such great risk. The harsh reality is that broader distribution of radioactive materials and sources makes more sources available to more people, thereby increasing the probability of incidents and accidents. As human beings derive greater benefit from ionizing radiation, they also stand a higher risk of being exposed to its harmful effects. Over the past ten years, the IAEA's technical cooperation programme undertook a massive effort to empower developing nations to realise social and economic goals through the application of radiation-based technologies. The Model Project on Upgrading Radiation Protection Infrastructure (the Model Project) represented a significant shift in priorities in that the aim was not to deliver technology per se, but rather to ensure that Member States acquired the capacity to self-manage all related aspects of radiation protection. Without question, the project keeps achieving a great deal. Virtually all participating countries are making significant progress in establishing a basic safety infrastructure; many also are developing the human resources required to tackle the issues of exposure control and emergency preparedness. This strengthened capacity enables Member States to realise more benefits from radiation-based technology more quickly. Moreover, through the knowledge and experience gained, more countries are reaching a level of maturity where they recognize that they hold responsibility for the radioactive sources and materials found within their borders

  18. Complementary safety assessments - Report by the French Nuclear Safety Authority

    International Nuclear Information System (INIS)

    2011-12-01

    As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

  19. Developing safety culture in nuclear power engineering

    International Nuclear Information System (INIS)

    Tevlin, S.A.

    2000-01-01

    The new issue (no. 11) of the IAEA publications series Safety Reports, devoted to the safety culture in nuclear engineering Safety culture development in the nuclear activities. Practical recommendations to achieve success, is analyzed. A number of recommendations of international experts is presented and basic general indicators of satisfactory and insufficient safety culture in the nuclear engineering are indicated. It is shown that the safety culture has two foundations: human behavior and high quality of the control system. The necessity of creating the confidence by the management at all levels of the enterprise, development of individual initiative and responsibility of the workers, which make it possible to realize the structural hierarchic system, including technical, human and organizational constituents, is noted. Three stages are traced in the process of introducing the safety culture. At the first stage the require,emts of scientific-technical documentation and provisions of the governmental, regional and control organs are fulfilled. At the second stage the management of the organization accepts the safety as an important direction in its activities. At the third stage the organization accomplishes its work, proceeding from the position of constant safety improvement. The general model of the safety culture development is considered [ru

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

    International Nuclear Information System (INIS)

    2006-01-01

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

  1. Managing nuclear wastes: an overview of the issues

    International Nuclear Information System (INIS)

    Cummings, R.G.; Utton, A.E.

    1981-01-01

    The issues involving nuclear waste management are reviewed. The author points out the need for a critical overview of research priorities concerning nuclear waste management (NWM), and he discusses the uncertainties surrounding the scope of the problem (i.e., the controversy concerning the extent of dangers to public health and safety associated with the transport and storage of nuclear wastes). This article, intended as a introdution to the other nuclear waste management papers in the journal, also briefly discusses the papers

  2. Nuclear Safety. 1997; Surete Nucleaire. 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-19

    A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

  3. Nuclear safety research master plan

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

    2001-06-01

    The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

  4. Nuclear Safety Review for the Year 2010

    International Nuclear Information System (INIS)

    2011-07-01

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

  5. Seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    Guerpinar, A.; Godoy, A.

    2001-01-01

    This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on 'Benchmark study for the seismic analysis and testing of WWER type nuclear power plants'. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

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

    International Nuclear Information System (INIS)

    2001-01-01

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

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

    International Nuclear Information System (INIS)

    2004-01-01

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

  8. Selecting of key safety parameters in reactor nuclear safety supervision

    International Nuclear Information System (INIS)

    He Fan; Yu Hong

    2014-01-01

    The safety parameters indicate the operational states and safety of research reactor are the basis of nuclear safety supervision institution to carry out effective supervision to nuclear facilities. In this paper, the selecting of key safety parameters presented by the research reactor operating unit to National Nuclear Safety Administration that can express the research reactor operational states and safety when operational occurrence or nuclear accident happens, and the interrelationship between them are discussed. Analysis shows that, the key parameters to nuclear safety supervision of research reactor including design limits, operational limits and conditions, safety system settings, safety limits, acceptable limits and emergency action level etc. (authors)

  9. Nuclear power plants: a unique challenge to fire safety

    International Nuclear Information System (INIS)

    Nowlen, S.P.

    1992-01-01

    The evaluation of fire safety in a nuclear power plant must include the consideration of the impact of a fire on the operability of plant safety equipment and systems. This issue is not typical of the life safety and property protection issues which dominate traditional fire safety concerns. This paper provides a general discussion of the issue of nuclear power plant fire safety as it currently exists in the USA. Included is a discussion of the past history of nuclear power plant fire events, the development of nuclear industry specific fire safety guidelines, the adverse experience associated with the inadvertent operation of fire suppression systems, and the anticipated direction of fire safety requirements for future reactor designs in the USA. (Author)

  10. Supervision of the safety culture in nuclear facilities

    International Nuclear Information System (INIS)

    2014-11-01

    This brochure issued by the Swiss Federal Nuclear Safety Inspectorate ENSI reports on safety culture aspects in nuclear facilities and ENSI’s activities as a supervisory instance. ENSI is the independent supervisory authority for the nuclear sector in Switzerland. A definition of safety culture is presented and the development of the concepts used in its monitoring are discussed. The main attributes of a good safety culture are discussed. Further, the conceptual basics and principles of such monitoring are looked at and the methods used for the supervision of safety culture in nuclear facilities are described

  11. Nuclear safety regulations in the Republic of Croatia

    International Nuclear Information System (INIS)

    Cizmek, A.; Horvatic, M.; Ilijas, B.; Medakovic, S.

    2009-01-01

    Based on Nuclear Safety Act (Official Gazette No. 173/03) in 2006 State Office for Nuclear Safety (SONS) adopted beside Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06) the new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08) and Ordinance on conditions for nuclear safety and protection with regard to the sitting, design, construction, use and decommissioning of a facility in which a nuclear activity is to be performed (Official Gazette No. 71/08). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a license to perform nuclear activity. The Ordinance also regulates the content of the form for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear conditions, whereas compliance is established by the decision passed by SONS. Ordinance on special conditions (requirements) for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned activities Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a licence to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance

  12. Evaluation of reliability assurance approaches to operational nuclear safety

    International Nuclear Information System (INIS)

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

    1984-01-01

    This report discusses the results of research to evaluate existing and/or recommended safety/reliability assurance activities among nuclear and other high technology industries for potential nuclear industry implementation. Since the Three Mile Island (TMI) accident, there has been increased interest in the use of reliability programs (RP) to assure the performance of nuclear safety systems throughout the plant's lifetime. Recently, several Nuclear Regulatory Commission (NRC) task forces or safety issue review groups have recommended RPs for assuring the continuing safety of nuclear reactor plants. 18 references

  13. 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)

  14. Safety criteria for siting a nuclear power plant

    International Nuclear Information System (INIS)

    2001-01-01

    The guide sets forth requirements for safety of the population and the environment in nuclear power plant siting. It also sets out the general basis for procedures employed by other competent authorities when they issue regulations or grant licences. On request STUK (Radiation and Nuclear Safety Authority of Finland) issues case-specific statements about matters relating to planning and about other matters relating to land use in the environment of nuclear power plants

  15. Nuclear power reactor safety

    International Nuclear Information System (INIS)

    Pon, G.A.

    1976-10-01

    This report is based on the Atomic Energy of Canada Limited submission to the Royal Commission on Electric Power Planning on the safety of CANDU reactors. It discusses normal operating conditions, postulated accident conditions, and safety systems. The release of radioactivity under normal and accident conditions is compared to the limits set by the Atomic Energy Control Regulations. (author)

  16. 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)

  17. Nuclear safety - Culture or obsession?

    International Nuclear Information System (INIS)

    Pereira Villar, Heldio

    2002-01-01

    Although nuclear activities are among the safest, having an enviable record in this respect, public perception is quite different. It is argued here that, regardless of the fact that environmental groups and the media in general look unfavourably towards the nuclear sector, the emphasis the sector places on safety matters is a liability rather than a asset. In short, public acceptance of a risky enterprise increases with the safety concerns shown by an entrepreneur up to a certain point. Beyond this threshold the enterprise is found too risky to be accepted, and it looks like the nuclear establishment has already crossed it. Ideas for further relationship with the public are then shown. (author)

  18. Nuclear safety research in France

    International Nuclear Information System (INIS)

    Tanguy, P.

    1976-01-01

    As a consequence of the decision of choosing light water reactors (PWR) for the French nuclear plants of the next ten years, a large safety program has been launched referring to three physical barriers against fission product release: the fuel element cladding, main primary system boundary and the containment. The parallel development of French-designed fast breeder reactors involved safety studies on: sodium boiling, accidental fuel behavior, molten fuel-sodium interaction, core accident and protection, and external containment. The rapid development of nuclear energy resulted in a corresponding development of safety studies relating to nuclear fuel facilities. French regulations also required a special program to be developed for the realistic evaluation of the consequences of external agressions, the French cooperation to multinational safety research being also intensive

  19. The safety of nuclear installations

    International Nuclear Information System (INIS)

    1993-01-01

    This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

  20. Hospital safety climate surveys: measurement issues.

    Science.gov (United States)

    Jackson, Jeanette; Sarac, Cakil; Flin, Rhona

    2010-12-01

    Organizational safety culture relates to behavioural norms in the workplace and is usually assessed by safety climate surveys. These can be a diagnostic indicator on the state of safety in a hospital. This review examines recent studies using staff surveys of hospital safety climate, focussing on measurement issues. Four questionnaires (hospital survey on patient safety culture, safety attitudes questionnaire, patient safety climate in healthcare organizations, hospital safety climate scale), with acceptable psychometric properties, are now applied across countries and clinical settings. Comparisons for benchmarking must be made with caution in case of questionnaire modifications. Increasing attention is being paid to the unit and hospital level wherein distinct cultures may be located, as well as to associated measurement and study design issues. Predictive validity of safety climate is tested against safety behaviours/outcomes, with some relationships reported, although effects may be specific to professional groups/units. Few studies test the role of intervening variables that could influence the effect of climate on outcomes. Hospital climate studies are becoming a key component of healthcare safety management systems. Large datasets have established more reliable instruments that allow a more focussed investigation of the role of culture in the improvement and maintenance of staff's safety perceptions within units, as well as within hospitals.

  1. Unresolved safety issues summary. Volume 3, Number 3. Aqua book

    International Nuclear Information System (INIS)

    1981-01-01

    The 'Unresolved Safety Issues' summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing Unresolved Safety Issues reported to Congress pursuant to section 210 of The Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the office of Management and Program Analysis. The definition of what constitutes completion of an unresolved safety issue (USI) has recently been expanded to include the implementation of the technical resolution. This is in acknowledgement of the fact that real safety benefits occur only after the implementation has taken place. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  2. Nuclear health and safety

    International Nuclear Information System (INIS)

    1990-04-01

    This report summarizes the responsiveness of DOE and contractors to findings contained in DOE technical safety appraisals and environmental surveys. These appraisals and surveys have been done at DOE facilities and sites to find out the extent of the environmental, safety, and health problems and to prioritize them for corrective action. As of January 1990, DOE computer data showed over 1,700 safety and health problems and almost 1,300 environmental problems. The majority of these problems, however, have not yet been corrected. GAO also looked at the extent to which DOE has developed a computerized tracking system to monitor the status of its environmental, safety, and health problems. GAO found that the computer system lacks important information, such as various field office and independent appraisals. Inclusion of this information would provide a more complete picture of the problems at the site

  3. Commercial truck parking and other safety issues.

    Science.gov (United States)

    2015-10-01

    Commercial truck parking is a safety issue, since trucks are involved in approximately 10% of all fatal accidents on interstates and : parkways in Kentucky. Drivers experience schedule demands and long hours on the road, yet they cannot easily determ...

  4. Safety of nuclear installations

    International Nuclear Information System (INIS)

    Esteves, R.G.

    1987-01-01

    The safety philosophy of a PWR type reactor distinguishing three levels of safety, is presented. At the first level, the concept of reactivity defining coefficients which measure the reactivity variation is introduced. At the second level, the reactor protection system establishing the design criteria to assure the high reliability, is defined. At the third level, the protection barriers to contain the consequences of accident evolution, are defined. (M.C.K.) [pt

  5. Basic safety principles for nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    Nuclear power plant safety requires a continuing quest for excellence. All individuals concerned should constantly be alert to opportunities to reduce risks to the lowest practicable level. The quest, however, is most likely to be fruitful if it is based on an understanding of the underlying objectives and principles of nuclear safety, and the way in which its aspects are interrelated. This report is an attempt to provide a logical framework for such an understanding. The proposed objectives and principles of nuclear safety are interconnected and must be taken as a whole; they do not constitute a menu from which selection can be made. The report takes account of current issues and developments. It includes the concept of safety objectives and the use of probabilistic safety assessment. Reliability targets for safety systems are discussed. The concept of a 'safety culture' is crucial. Attention has been paid to the need for planning for accident management. The report contains objectives and principles. The objectives state what is to be achieved; the principles state how to achieve it. In each case, the basic principle is stated as briefly as possible. The accompanying discussion comments on the reasons for the principle and its importance, as well as exceptions, the extent of coverage and any necessary clarification. The discussion is as important as the principle it augments. 4 figs

  6. Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

    International Nuclear Information System (INIS)

    Lyons, J.E.

    2012-01-01

    The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

  7. Nuclear plant safety

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The four-member New York Power Pool Panel concluded that, for a number of reasons, no nuclear power plant in New York State is prone to the type of accident that occurred at Three Mile Island (TMI). The Panel further concluded that changes in operating practices, both regulatory and voluntary, and heightened sensitivity to reactor-core-cooling requirements will substantially reduce the chances for another such accident anywhere. Panel members found that New York State utilities have taken a responsible attitude with regard to requirements set forth by the Nuclear Regulatory Commission (NRC) as a result of the TMI accident. In a cover letter that accompanied the report to Federal and New York state officials, New York Power Pool Executive Committee Chairman Francis E. Drake, Jr. expressed hope that the report will alleviate public fears of nuclear reactors and promote wider acceptance of nuclear energy as an economic and safe means of power production. 17 references

  8. Opening Address [5. International Conference on Topical Issues in Nuclear Installation Safety: Defence in Depth — Advances and Challenges for Nuclear Installation Safety, Vienna, Austria, 21-24 October 2013

    Energy Technology Data Exchange (ETDEWEB)

    Flory, D. [International Atomic Energy Agency, Department of Nuclear Safety and Security, Vienna (Austria)

    2014-10-15

    We anticipate that the working sessions of this conference will allow us to share experience and enhance our understanding on safety measures on the implementation of DID in siting, design and construction; commissioning and operation; accident management and emergency preparedness and response; as well as the cross cutting organizational, technical and human factors issues that underlie defence in depth. While substantial efforts and resources have been invested to gain an understanding of what happened and why in the Fukushima Daiichi accident and much progress has been made, additional lessons learned will need to be taken forward. Learning and sharing lessons learned, and implementing the activities necessary for progress to be ongoing, is a quest for improvement that must never cease.

  9. Nuclear safety and public debate

    International Nuclear Information System (INIS)

    Tanguy, P.

    1997-01-01

    In this article are evoked the question of nuclear safety and the public opinion, from the beginning of nuclear power plants in 1954 where a peaceful use of nuclear energy is developed in minds. If the aim was to avoid any important accident, the Three Miles Island accident and more recently the Chernobyl accident provoked a shock in public opinion and marked a peak of nuclear controversy. From this point, the policy of transparence and a best information of the public taken as a partner are necessary to maintain the dialogue. (N.C.)

  10. Review of Policy Documents for Nuclear Safety and Regulation

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  11. Review of Policy Documents for Nuclear Safety and Regulation

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  12. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-03-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG series report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. The data contained in this report are a product of the NRC's Safety Issues Management System database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by personnel in the NRC regions. This report has been prepared in order to provide a comprehensive description of the implementation and verification status of all the TMI Action Plan requirements at licensed reactors, and to make this information available to other interested parties, including the public. A corollary purpose of this report is for it to serve as a follow-on to NUREG-0933, ''A Prioritization of Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed facilities

  13. Road safety issues for bus transport management.

    Science.gov (United States)

    Cafiso, Salvatore; Di Graziano, Alessandro; Pappalardo, Giuseppina

    2013-11-01

    Because of the low percentage of crashes involving buses and the assumption that public transport improves road safety by reducing vehicular traffic, public interest in bus safety is not as great as that in the safety of other types of vehicles. It is possible that less attention is paid to the significance of crashes involving buses because the safety level of bus systems is considered to be adequate. The purpose of this study was to evaluate the knowledge and perceptions of bus managers with respect to safety issues and the potential effectiveness of various technologies in achieving higher safety standards. Bus managers were asked to give their opinions on safety issues related to drivers (training, skills, performance evaluation and behaviour), vehicles (maintenance and advanced devices) and roads (road and traffic safety issues) in response to a research survey. Kendall's algorithm was used to evaluate the level of concordance. The results showed that the majority of the proposed items were considered to have great potential for improving bus safety. The data indicated that in the experience of the participants, passenger unloading and pedestrians crossing near bus stops are the most dangerous actions with respect to vulnerable users. The final results of the investigation showed that start inhibition, automatic door opening, and the materials and internal architecture of buses were considered the items most strongly related to bus passenger safety. Brake assistance and vehicle monitoring systems were also considered to be very effective. With the exception of driver assistance systems for passenger and pedestrian safety, the perceptions of the importance of other driver assistance systems for vehicle monitoring and bus safety were not unanimous among the bus company managers who participated in this survey. The study results showed that the introduction of new technologies is perceived as an important factor in improving bus safety, but a better understanding

  14. Space nuclear reactor safety

    International Nuclear Information System (INIS)

    Damon, D.; Temme, M.; Brown, N.

    1990-01-01

    Definition of safety requirements and design features of the SP-100 space reactor power system has been guided by a mission risk analysis. The analysis quantifies risk from accidental radiological consequences for a reference mission. Results show that the radiological risk from a space reactor can be made very low. The total mission risk from radiological consequences for a shuttle-launched, earth orbit SP-100 mission is estimated to be 0.05 Person-REM (expected values) based on a 1 mREM/yr de Minimus dose. Results are given for each mission phase. The safety benefits of specific design features are evaluated through risk sensitivity analyses

  15. Nuclear criticality safety in Canada

    International Nuclear Information System (INIS)

    Shultz, K.R.

    1980-04-01

    The approach taken to nuclear criticality safety in Canada has been influenced by the historical development of participants. The roles played by governmental agencies and private industry since the Atomic Energy Control Act was passed into Canadian Law in 1946 are outlined to set the scene for the current situation and directions that may be taken in the future. Nuclear criticality safety puts emphasis on the control of materials called special fissionable material in Canada. A brief account is given of the historical development and philosophy underlying the existing regulations governing special fissionable material. Subsequent events have led to a change in emphasis in the regulatory process that has not yet been fully integrated into Canadian legislation and regulations. Current efforts towards further development of regulations governing the practice of nuclear criticality safety are described. (auth)

  16. The safety issues of medical robotics

    Energy Technology Data Exchange (ETDEWEB)

    Fei Baowei; Ng, W.S.; Chauhan, Sunita; Kwoh, Chee Keong

    2001-08-01

    In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound image-guided interstitial laser coagulation, radiation seed implantation, laser resection, and electrical resection of the prostate. Safety was always the key issue in the building of the robot. The HISIC strategies were adopted for safety enhancement in mechanical, electrical and software design. The initial test on URObot showed that HISIC had the potential ability to improve the safety of the system. Further safety experiments are being conducted in our laboratory.

  17. The safety issues of medical robotics

    International Nuclear Information System (INIS)

    Fei Baowei; Ng, W.S.; Chauhan, Sunita; Kwoh, Chee Keong

    2001-01-01

    In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound image-guided interstitial laser coagulation, radiation seed implantation, laser resection, and electrical resection of the prostate. Safety was always the key issue in the building of the robot. The HISIC strategies were adopted for safety enhancement in mechanical, electrical and software design. The initial test on URObot showed that HISIC had the potential ability to improve the safety of the system. Further safety experiments are being conducted in our laboratory

  18. Nuclear energy safety - new challenges

    Energy Technology Data Exchange (ETDEWEB)

    Rausch, Julio Cezar; Fonseca, Renato Alves da, E-mail: jrausch@cnen.gov.b, E-mail: rfonseca@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Fukushima accident in March this year, the second most serious nuclear accident in the world, put in evidence a discussion that in recent years with the advent of the 'nuclear renaissance' has been relegated in the background: what factors influence the use safe nuclear energy? Organizational precursor, latent errors, reduction in specific areas of competence and maintenance of nuclear programs is a scenario where the guarantee of a sustainable development of nuclear energy becomes a major challenge for society. A deep discussion of factors that influenced the major accidents despite the nuclear industry use of the so-called 'lessons learned' is needed. Major accidents continue to happen if a radical change is not implemented in the focus of safety culture. (author)

  19. Nuclear energy safety - new challenges

    International Nuclear Information System (INIS)

    Rausch, Julio Cezar; Fonseca, Renato Alves da

    2011-01-01

    Fukushima accident in March this year, the second most serious nuclear accident in the world, put in evidence a discussion that in recent years with the advent of the 'nuclear renaissance' has been relegated in the background: what factors influence the use safe nuclear energy? Organizational precursor, latent errors, reduction in specific areas of competence and maintenance of nuclear programs is a scenario where the guarantee of a sustainable development of nuclear energy becomes a major challenge for society. A deep discussion of factors that influenced the major accidents despite the nuclear industry use of the so-called 'lessons learned' is needed. Major accidents continue to happen if a radical change is not implemented in the focus of safety culture. (author)

  20. Nuclear energy safety - new challenges

    Energy Technology Data Exchange (ETDEWEB)

    Rausch, Julio Cezar; Fonseca, Renato Alves da, E-mail: jrausch@cnen.gov.b, E-mail: rfonseca@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Fukushima accident in March this year, the second most serious nuclear accident in the world, put in evidence a discussion that in recent years with the advent of the 'nuclear renaissance' has been relegated in the background: what factors influence the use safe nuclear energy? Organizational precursor, latent errors, reduction in specific areas of competence and maintenance of nuclear programs is a scenario where the guarantee of a sustainable development of nuclear energy becomes a major challenge for society. A deep discussion of factors that influenced the major accidents despite the nuclear industry use of the so-called 'lessons learned' is needed. Major accidents continue to happen if a radical change is not implemented in the focus of safety culture. (author)

  1. Editorial safety science special issue road safety management.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Hagezieker, M.P.

    2014-01-01

    The articles presented in this Special Issue on Road Safety Management represent an illustration of the growing interest in policy-related research in the area of road safety. The complex nature of this type of research combined with the observation that scientific journals pay limited attention to

  2. Nuclear Safety Review for the Year 2006

    International Nuclear Information System (INIS)

    2007-07-01

    As the Agency begins its 50th year of service to the peaceful uses of nuclear energy, there are clear signs of renewed interest in the nuclear power option. Around the world there are plans for both new and reinvigorated nuclear power development and other uses of nuclear technology. It is essential that future planning for applications of nuclear energy and related efforts are complemented with equally ambitious plans for the establishment and enhancement of sustainable safety infrastructures. Plans must be made to transfer knowledge effectively from experienced staff that will soon retire from vendors, regulatory bodies and operating organizations. Equally important are plans for the education and training of the next generation of individuals with the knowledge and expertise to support nuclear and radiation safety. In 2006, the International Nuclear Safety Group (INSAG) issued a report on the global nuclear safety regime which concludes that the regime is functioning at an effective level today, but its impact on improving safety could be enhanced by pursuing measured change. In 2006, the Board of Governors approved the Safety Fundamentals upon which the IAEA Safety Standards are based. The Safety Fundamentals establish that the prime responsibility for safety rests with the person or organization responsible for facilities and activities that give rise to radiation risks. The Safety Fundamentals also state that an effective legal and governmental framework for safety must be established and sustained. The challenge now is to ensure that the IAEA Safety Standards are applied in an appropriate manner by the entire nuclear community. Both in anticipation of expanding uses of nuclear energy and to conform to current international standards, legislative and regulatory reform is underway in a number of Member States. Most Member States now recognize that stakeholders need to be involved in decisions involving nuclear technology. The challenge remains on how to engage

  3. Nuclear power infrastructure - issues, strategy and possibilities

    International Nuclear Information System (INIS)

    Sokolov, Y.A.

    2009-01-01

    Full text: Today humanity faces daunting challenges: the pressing need for development in many parts of the world and the desire for a more effective system of international security. At the outset of the 21st century, the Millennium Development Goals and the Johannesburg Plan of Implementation have both set global objectives for sustainable development (SD) that give high priority to the eradication of poverty and hunger, environmental sustainability, universal access to plentiful fresh water and energy. In this context there are many expectations about Nuclear Renascence supported by many national and international studies, by discussions in the mass media and international forums, etc. The Agency has taken an integrated approach outlining all considerations that have to be taken into account for the introduction of a nuclear power programme, providing guiding documents, forums for sharing information, consultancies and technical meetings and sending multidisciplinary teams to countries requesting assistance with nuclear power infrastructure. The process also includes specific assistance and review services in the areas of infrastructure readiness, feasibility studies, draft nuclear law, regulatory frameworks and organization, siting issues, human resource development and planning, bid evaluation and technology assessment, owner/operator competence, and safety and security. It is important to support the decision making processes of States introducing nuclear power to ensure they can make informed choices on the role of nuclear power in their energy mixes. The IAEA helps countries prepare for the introduction or expansion of nuclear power by 1) helping them ensure that nuclear energy is used safely, securely and with minimal proliferation risk, and 2) meeting the need of developing countries to build capacity in terms of human resources, energy analysis, regulatory capabilities and other infrastructure necessary for nuclear power. The process also includes

  4. Nuclear materials facility safety initiative

    International Nuclear Information System (INIS)

    Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

    2000-01-01

    Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

  5. Realism in nuclear criticality safety

    International Nuclear Information System (INIS)

    McLaughlin, T. P.

    2009-01-01

    Commercial nuclear power plant operation and regulation have made remarkable progress since the Three Mile Island Accident. This is attributed largely to a heavy dose of introspection and self-regulation by the industry and to a significant infusion of risk-informed and performance-based regulation by the Nuclear Regulatory Commission. This truly represents reality in action both by the plant operators and the regulators. On the other hand, the implementation of nuclear criticality safety in ex-reactor operations involving significant quantities of fissile material has not progressed, but, tragically, it has regressed. Not only is the practice of the discipline in excess of a factor of ten more expensive than decades ago; the trend continues. This unfortunate reality is attributed to a lack of coordination within the industry (as contrasted to what occurred in the reactor operations sector), and to a lack of implementation of risk-informed and performance-based regulation by the NRC While the criticality safety discipline is orders of magnitude smaller than the reactor safety discipline, both operators and regulators must learn from the progress made in reactor safety and apply it to the former to reduce the waste, inefficiency and potentially increased accident risks associated with current practices. Only when these changes are made will there be progress made toward putting realism back into nuclear criticality safety. (authors)

  6. Tutorial on nuclear thermal propulsion safety for Mars

    International Nuclear Information System (INIS)

    Buden, D.

    1992-01-01

    Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments

  7. Safety device for nuclear reactor

    International Nuclear Information System (INIS)

    Jacquelin, Roland.

    1977-01-01

    This invention relates to a safety device for a nuclear reactor, particularly a liquid metal (generally sodium) cooled fast reactor. This safety device includes an absorbing element with a support head connected by a disconnectable connector formed by the armature of an electromagnet at the end of an axially mobile vertical control rod. This connection is so designed that in the event of it becoming disconnected, the absorbing element gravity slides in a passage through the reactor core into an open container [fr

  8. Radiation safety and protection on the nuclear power plants

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Bogorad, V.I.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Litvinskaya, T.V.; Slepchenko, A.Yu.

    2008-01-01

    The main issues of the radiation safety and protection provision on the nuclear power plants are considered in this monograph. The description of the basic sources of the radiation danger on NPPs, the principles, the methods and the means of the safety and radiation monitoring provision are shown. The special attention is paid to the issues of the ionizing radiation regulation

  9. White paper on nuclear safety in 2005

    International Nuclear Information System (INIS)

    2006-04-01

    The white paper consists of four parts. The first part described the outline of international discussions on safety culture and activities promoted by utilities and regulatory bodies in Japan. The second part explained the main activities of the Nuclear Safety Commission of Japan and nuclear regulatory authorities on nuclear safety regulation. The third part introduced various activities for ensuring overall nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster measures at nuclear facilities, progress in nuclear research, nuclear safety regulation by risk-informed utilization, environmental radiation surveys, international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission of Japan. (J.P.N.)

  10. Nuclear Powerplant Safety: Source Terms. Nuclear Energy.

    Science.gov (United States)

    Department of Energy, Washington, DC. Nuclear Energy Office.

    There has been increased public interest in the potential effects of nuclear powerplant accidents since the Soviet reactor accident at Chernobyl. People have begun to look for more information about the amount of radioactivity that might be released into the environment as a result of such an accident. When this issue is discussed by people…

  11. IAEA safety fundamentals: the safety of nuclear installations and the defence in depth concept

    International Nuclear Information System (INIS)

    Aro, I.

    2005-01-01

    This presentation is a replica of the similar presentation provided by the IAEA Basic Professional Training Course on Nuclear Safety. The presentation utilizes the IAEA Safety Series document No. 110, Safety Fundamentals: the Safety of Nuclear Installations. The objective of the presentation is to provide the basic rationale for actions in provision of nuclear safety. The presentation also provides basis to understand national nuclear safety requirements. There are three Safety Fundamentals documents in the IAEA Safety Series: one for nuclear safety, one for radiation safety and one for waste safety. The IAEA is currently revising its Safety Fundamentals by combining them into one general Safety Fundamentals document. The IAEA Safety Fundamentals are not binding requirements to the Member States. But, a very similar text has been provided in the Convention on Nuclear Safety which is legally binding for the Member State after ratification by the Parliament. This presentation concentrates on nuclear safety. The Safety Fundamentals documents are the 'policy documents' of the IAEA Safety Standards Series. They state the basic objectives, concepts and principles involved in ensuring protection and safety in the development and application of atomic energy for peaceful purposes. They will state - without providing technical details and without going into the application of principles - the rationale for actions necessary in meeting Safety Requirements. Chapter 7 of this presentation describes the basic features of defence in depth concept which is referred to in the Safety Fundamentals document. The defence in depth concept is a key issue in reaching high level of safety specifically at the design stage but as the reader can see the extended concept also refers to the operational stage. The appendix has been taken directly from the IAEA Basic Professional Training Course on Nuclear Safety and applied to the Finnish conditions. The text originates from the references

  12. Nuclear safety guide. TID-7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  13. Nuclear safety guide. TID-7016, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, J T [ed.

    1978-05-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information.

  14. Nuclear Safety Review for the Year 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-15

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

  15. The Nordic Nuclear Safety Research (NKS) programme. Nordic cooperation on nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Kasper G. [Technical Univ. of Denmark, Roskilde (Denmark). National Lab. for Sustainable Energy; Ekstroem, Karoliina [Fortum Power and Heat, Fortum (Finland); Gwynn, Justin P. [Norwegian Radiation Protection Authority, Tromsoe (Norway). Fram Centre; Magnusson, Sigurdur M. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Physant, Finn C. [NKS-Sekretariatet, Roskilde (Denmark)

    2012-07-01

    The roots of the current Nordic Nuclear Safety Research (NKS) programme can be traced back to the recommendation by the Nordic Council in the late 1950s for the establishment of joint Nordic committees on the issues of nuclear research and radiation protection. One of these joint Nordic committees, the 'Kontaktorgan', paved the way over its 33 years of existence for the future of Nordic cooperation in the field of nuclear safety, through the formation of Nordic groups on reactor safety, nuclear waste and environmental effects of nuclear power in the late 1960s and early 1970s. With an increased focus on developing nuclear power in the wake of the energy crisis on the 1970s, the NKS was established by the Nordic Council to further develop the previous strands of Nordic cooperation in nuclear safety. NKS started its first programme in 1977, funding a series of four year programmes over the next 24 years covering the areas of reactor safety, waste management, emergency preparedness and radioecology. Initially funded directly from the Nordic Council, ownership of NKS was transferred from the political level to the national competent authorities at the beginning of the 1990s. This organizational and funding model has continued to the present day with additional financial support from a number of co-sponsors in Finland, Norway and Sweden. (orig.)

  16. The nuclear controversy-what are the issues

    International Nuclear Information System (INIS)

    Wyatt, A.

    1976-01-01

    The various issues raised by anti-nuclear groups are outlined and rebutted. Issues are grouped under four headingss - Economic; Technical; Social/Ethical/Moral; Political. Issues debated under economic aspects include conservation, unemployment resulting from energy use, use of alternative enrgy sources, high capital cost of nuclear power, high energy consumption in construction of plants, performance unreliability, depletion of uranium and excessive cost of decommissioning. Technically related issues, reactor safety, possibility of nuclear power plant explosion, waste managment, toxicity of plutonium, emission of radioactive material, thermal pollution and environmental effect of heavy water production are also discussed. Social/ethical/moral issues rebutted include radiation effects on health and genetic effects, deaths among uranium miners, morality of long-term waste storage, lack of faith in technical solutions and technical people, opposition to current life style, secrecy of information, nuclear proliferation and unsuitability of nuclear technology to the needs of developing countries. Political issues discussed are sabotage/terrorism possibilites, police state tactics in protection of nuclear facilities, misuse of technolgy by society, high energy society is capitalist and low energy society is Marxist, centralization of power, need for a great nuclear debate and the question of who pays for safety. Scientists and technical people are called upon to debate in their areas of specialty and are cautioned to be aware of tactics involved in meeting challengers head-on. (J.T.A.)

  17. The nuclear debate - examination of the issues

    International Nuclear Information System (INIS)

    Ellington, H.I.; Addinall, E.

    1981-01-01

    Issues examined in a package of educational exercises, written by the present authors, entitled The Nuclear Debate are discussed. The three sections are entitled: (1) Does Britain really need nuclear power. (2) What sort of nuclear power programme would be best suited to meeting Britain's future energy needs. (3) Is nuclear power socially and environmentally acceptable in an open society such as Britain (alleged dangers to workers, dangers to the general public, and genetic hazards, political freedom and proliferation issues). (U.K.)

  18. Safety culture in nuclear power enterprise

    International Nuclear Information System (INIS)

    Zou Zhengyu; Su Luming

    2008-01-01

    The International Atomic Energy Agency (IAEA) introduced the concept of safety culture when analyzing the Chernobyl accident. Safety culture has now been widely accepted and practiced by nuclear enterprise in the world. As an important safeguard for nuclear safety, safety culture has become the core of nuclear power enterprise and entitled as the soul of nuclear enterprise. This paper analyzes the three levels of safety culture and describes its three developing phases. (authors)

  19. Basic safety principles for nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1989-01-01

    To ensure the safety operation of nuclear power plant, one should strictly adhere to the implelmentation of safety codes and the establishment of nuclear safety code system, as well as the applicable basic safety principles of nuclear power plants. This article briefly introduce the importance of nuclear codes and its economic benefits and the implementation of basic safety principles to be accumulated in practice for many years by various countries

  20. Regional cooperation on nuclear safety

    International Nuclear Information System (INIS)

    Kato, W.Y.; Chen, J.H.; Kim, D.H.; Simmons, R.B.V.; Surguri, S.

    1985-01-01

    A review has been conducted of a number of multi-national and bilateral arrangements between governments and between utility-sponsored organizations which provide the framework for international cooperation in the field of nuclear safety. These arrangements include the routine exchange operational data, experiences, technical reports and regulatory data, provision of special assistance when requested, collaboration in safety research, and the holding of international conferences and seminars. Areas which may be better suited for cooperation on a regional basis are identified. These areas include: exchange of operational data and experience, sharing of emergency planning information, and collaboration in safety research. Mechanisms to initiate regional cooperation in these areas are suggested

  1. Nuclear safety policy statement in korea

    International Nuclear Information System (INIS)

    Kim, W.S.; Kim, H.J.; Choi, K.S.; Choi, Y.S.; Park, D.K.

    2006-01-01

    Full text: Wide varieties of programs to enhance nuclear safety have been established and implemented by the Korean government in accordance with the Nuclear Safety Policy Statement announced in September 1994. The policy statement was intended to set the long-term policy goals for maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It has been recognized as very effective in developing safety culture in nuclear-related organizations and also enhancing nuclear safety in Korea. However, ageing of operating nuclear power plants and increasing of new nuclear facilities have demanded a new comprehensive national safety policy to cover the coming decade, taking the implementation results of the policy statement of 1994 and the changing environment of nuclear industries into consideration. Therefore, the results of safety policy implementation have been reviewed and, considering changing environment and future prospects, a new nuclear safety policy statement as a highest level national policy has been developed. The implementation results of 11 regulatory policy directions such as the use of Probabilistic Safety Assessment, introduction of Periodic Safety Review, strengthening of safety research, introduction of Risk Based Regulation stipulated in the safety policy statement of 1994 were reviewed and measures taken after various symposia on nuclear safety held in Nuclear Safety Days since 1995 were evaluated. The changing international and domestic environment of nuclear industry were analysed and future prospects were explored. Based on the analysis and review results, a draft of new nuclear safety policy statement was developed. The draft was finalized after the review of many prominent experts in Korea. Considering changing environment and future prospects, new policy statement that will show government's persistent will for nuclear safety has been

  2. Nuclear Safety Review for the Year 2004

    International Nuclear Information System (INIS)

    2005-08-01

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

  3. Nuclear safety in crisis regions

    International Nuclear Information System (INIS)

    Ustohalova, Veronika; Englert, Matthias

    2017-01-01

    The use of nuclear energy demands extensive institutional and material infrastructure upon a foundation of stable intrastate conditions and interstate relations. Conflicts can result in catastrophic accidents, either deliberately or unintentionally. If there are nuclear facilities located in a crisis region, the risk of a nuclear disaster is markedly heightened. This can be explained not only in terms of the strategic relevance of the energy supply in military conflicts, but also the increased accident risks and hazards arising from collateral damage, as well as the erosion of the safety culture and institutional control in crisis regions with a nuclear infrastructure. Even just the escalation of a political dispute or the persistence of low intensity conflicts can make it generally more difficult and complex to maintain nuclear safety, if intrastate safety mechanisms come under strain or even fail as a result. So far no instance of military escalation, past or present, has led to an accident in a civil nuclear facility. Nevertheless, questions are clearly raised about the vulnerability of nuclear facilities in crisis regions and the risks associated with this vulnerability. Despite the potentially far-reaching consequences, too little attention is currently being paid to the linkage between intra- and interstate conflicts and the safety of nuclear facilities in crisis regions. The aim of the research presented here was to explore this theme and, after laying the groundwork in this manner, to raise awareness among policy-makers and the wider public. In this context the escalation of conflicts in the Ukraine is a particular focus. The first part of the report begins with a systematic look at the link between crisis regions and/or conflicts and nuclear safety. The various impact pathways relating to nuclear facility safety and the associated risks are described in relation to potential hazards induced by crises and wars. A nuclear facility can itself become a theatre

  4. Nuclear safety in crisis regions

    Energy Technology Data Exchange (ETDEWEB)

    Ustohalova, Veronika; Englert, Matthias

    2017-04-12

    The use of nuclear energy demands extensive institutional and material infrastructure upon a foundation of stable intrastate conditions and interstate relations. Conflicts can result in catastrophic accidents, either deliberately or unintentionally. If there are nuclear facilities located in a crisis region, the risk of a nuclear disaster is markedly heightened. This can be explained not only in terms of the strategic relevance of the energy supply in military conflicts, but also the increased accident risks and hazards arising from collateral damage, as well as the erosion of the safety culture and institutional control in crisis regions with a nuclear infrastructure. Even just the escalation of a political dispute or the persistence of low intensity conflicts can make it generally more difficult and complex to maintain nuclear safety, if intrastate safety mechanisms come under strain or even fail as a result. So far no instance of military escalation, past or present, has led to an accident in a civil nuclear facility. Nevertheless, questions are clearly raised about the vulnerability of nuclear facilities in crisis regions and the risks associated with this vulnerability. Despite the potentially far-reaching consequences, too little attention is currently being paid to the linkage between intra- and interstate conflicts and the safety of nuclear facilities in crisis regions. The aim of the research presented here was to explore this theme and, after laying the groundwork in this manner, to raise awareness among policy-makers and the wider public. In this context the escalation of conflicts in the Ukraine is a particular focus. The first part of the report begins with a systematic look at the link between crisis regions and/or conflicts and nuclear safety. The various impact pathways relating to nuclear facility safety and the associated risks are described in relation to potential hazards induced by crises and wars. A nuclear facility can itself become a theatre

  5. 25 years of nuclear safety

    International Nuclear Information System (INIS)

    Curien, H.; Duclos, D.; Saint Raymond, Ph.

    1998-01-01

    This philosophical dossier is devoted to the last 25 years of nuclear safety. It is organized around three main subjects: the control, the communication with the public and the international relations. The control affected the builder and the operator, but also an independent authority. This duality is essential. The public relations became a main point in the risks management. The transparency leads to a better public information. The last part is devoted to the international relations. It affects the international regulations but also the opinion exchange. The nuclear industries (and even non nuclear industries) should take inspiration from the foreign management and experiences. (A.L.B.)

  6. Nuclear data for criticality safety

    International Nuclear Information System (INIS)

    Westfall, R.M.

    1994-01-01

    A brief overview is presented on emerging requirements for new criticality safety analyses arising from applications involving nuclear waste management, facility remediation, and the storage of nuclear weapons components. A derivation of criticality analyses from the specifications of national consensus standards is given. These analyses, both static and dynamic, define the needs for nuclear data. Integral data, used primarily for analytical validation, and differential data, used in performing the analyses, are listed, along with desirable margins of uncertainty. Examples are given of needs for additional data to address systems having intermediate neutron energy spectra and/or containing nuclides of intermediate mass number

  7. Nuclear safety and the European Community: Broadening perspectives

    International Nuclear Information System (INIS)

    Brinkhorst, L.J.

    1992-01-01

    The European Community's activities in harmonizing of regulations and practices in the field of nuclear safety are described. The issues of aid to Central and Eastern European countries as well as of public information, within this context, are discussed

  8. Nuclear standards: current issues and future trends

    International Nuclear Information System (INIS)

    Landis, J.W.

    1985-01-01

    A summary of the important issues that currently face the nuclear standards field is presented and a discussion of how each of these issues is being resolved is given. The economic benefits that properly developed standards produce are listed

  9. Public policy issues in nuclear waste management

    International Nuclear Information System (INIS)

    Nealey, S.M.; Radford, L.M.

    1978-10-01

    This document aims to raise issues and to analyze them, not resolve them. The issues were: temporal equity, geographic and socioeconomic equity, implementation of a nuclear waste management system, and public involvement

  10. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination

    Directory of Open Access Journals (Sweden)

    Dean Kyne

    2016-07-01

    Full Text Available Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  11. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination.

    Science.gov (United States)

    Kyne, Dean; Bolin, Bob

    2016-07-12

    Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP) reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  12. Nordic projects concerning nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-11-01

    The report describes the nature of the work done in the first half of 1988 within the field of nuclear safety (1985-89) under the Nordic program for 1985-89. Five programmes and their documentation, are described and complete lists of addresses and of persons involved is given. (AB)

  13. Nuclear medicine software: safety aspects

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    A brief editorial discusses the safety aspects of nuclear medicine software. Topics covered include some specific features which should be incorporated into a well-written piece of software, some specific points regarding software testing and legal liability if inappropriate medical treatment was initiated as a result of information derived from a piece of clinical apparatus incorporating a malfunctioning computer program. (U.K.)

  14. Nuclear Safety Review for the Year 2007

    International Nuclear Information System (INIS)

    2008-07-01

    the nuclear industry and regulators as never before. A key challenge now is to properly assess and address the safety implications of these changes. With the globalization of the nuclear business and the consequent implications for supply, ownership and operational management of nuclear power plants, there is greater need for international consistency of standards and their application and for strong leadership and clear responsibility for safety. International experience on plant life management and long term operation has reinforced the need for a comprehensive life cycle approach and the Agency has been urged to establish safety standards for safe long term operation, periodic safety reviews and ageing management. Much progress has been made regarding emergency preparedness in recent years. Even so, most Member States still need to attain and sustain a satisfactory level of nuclear and radiological emergency preparedness, including adequate preparations for first responders. Seismic safety is not a new issue, but the recent earthquake in the vicinity of the Kashiwazaki nuclear power plant in Japan highlighted the need to consider the potential consequences of earthquakes in siting, new designs and ageing management of operating nuclear power plants. The Agency sent an expert mission to Japan and is establishing a knowledge centre for seismic safety, tsunami hazard assessment and disaster mitigation management to develop and share state-of-the-art knowledge and to facilitate its application to enhance nuclear safety. New multi-purpose research reactors have been commissioned or are being designed for utilization as regional and international centres. Safety assessments will need to cover the broad range of experiments and irradiations to be conducted in these facilities. In anticipation of the expansion of nuclear power and the use of new technologies, many Member States will need to enlarge their occupational radiological dose assessment capacity to take account of

  15. Nuclear power: levels of safety

    International Nuclear Information System (INIS)

    Lidsky, L.M.

    1988-01-01

    The rise and fall of the nuclear power industry in the United States is a well-documented story with enough socio-technological conflict to fill dozens of scholarly, and not so scholarly, books. Whatever the reasons for the situation we are now in, and no matter how we apportion the blame, the ultimate choice of whether to use nuclear power in this country is made by the utilities and by the public. Their choices are, finally, based on some form of risk-benefit analysis. Such analysis is done in well-documented and apparently logical form by the utilities and in a rather more inchoate but not necessarily less accurate form by the public. Nuclear power has failed in the United States because both the real and perceived risks outweigh the potential benefits. The national decision not to rely upon nuclear power in its present form is not an irrational one. A wide ranging public balancing of risk and benefit requires a classification of risk which is clear and believable for the public to be able to assess the risks associated with given technological structures. The qualitative four-level safety ladder provides such a framework. Nuclear reactors have been designed which fit clearly and demonstrably into each of the possible qualitative safety levels. Surprisingly, it appears that safer may also mean cheaper. The intellectual and technical prerequisites are in hand for an important national decision. Deployment of a qualitatively different second generation of nuclear reactors can have important benefits for the United States. Surprisingly, it may well be the nuclear establishment itself, with enormous investments of money and pride in the existing nuclear systems, that rejects second generation reactors. It may be that we will not have a second generation of reactors until the first generation of nuclear engineers and nuclear power advocates has retired

  16. Safety performance indicators. Topical issues paper no. 5

    International Nuclear Information System (INIS)

    Dahlgren, K.; Lederman, L.; Szikszai, T.; Palomo, J.

    2001-01-01

    performance, they are just one of a larger set of tools including probabilistic safety assessment (PSA), regulatory inspection, quality assurance, external reviews and self-assessment needed to assess operational safety performance. The integration of information compiled from such evaluation tools yields the best results. Two areas of increasingly common interest are 'risk based' indicators, and 'safety culture' indicators. The key to managing the nuclear business today is to establish a high quality safety management system as well as developing a strong safety culture within the entire organization. 'The safety management system comprises those arrangements made by the organization for the management of safety in order to promote a strong safety culture and achieve good safety performance'. This definition, presented in INSAG-13, illustrates the close connection between 'safety management systems' and 'safety culture' and that they are in fact inseparable. To manage safety effectively you need a systematic approach and at the same time be aware of the effects of the approach on individual and collective human behaviour. This issue covers the following: development of safety performance indicators, indicator selection and use, recommended indicators, indicators collected from nuclear power plant initiatives, management of safety and safety culture, need and feasibility of an international system, plant management needs, regulatory use of safety performance indicators, public communication, and recommendations for priorities in future work

  17. Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    1997-05-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

  18. Nuclear power and nuclear safety 2009; Kernekraft og nuklear sikkerhed 2009

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D.; Nystrup, P.E.; Thorlaksen, B. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2010-05-15

    The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

  19. A global nuclear safety culture

    International Nuclear Information System (INIS)

    1996-01-01

    The article discusses three components characterizing the infrastructure of a global nuclear safety culture, each one satisfying special needs. These are: (a) legally binding international agreements, which were drawn up at an accelerated pace in the 1980s following the Chernobyl accident, with its transboundary implications; (b) non-binding common safety standards, which were developed rapidly during the 1960s and 1970s, a period which saw a desire for harmonized safety approaches as nuclear power and the use of radiation and radioactive materials expanded globally; and (c) review and advisory services, which are provided by international experts, the need for which was underscored by the accident at Chernobyl. 5 refs, 1 fig

  20. Autoclave nuclear criticality safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

    1991-12-31

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  1. Welding faults and nuclear safety

    International Nuclear Information System (INIS)

    Bergemann, W.

    1977-01-01

    Recommendations are presented with a view to further improving the nuclear safety and radiological protection in G.D.R. nuclear power plants by altering the requirements set out in the Labour Safety Regulation 880 for the weld quality of components of nuclear power plant systems. In order to fix the requirements to be met in non-destructive testing of welded joints, the individual systems should be classified taking injury to persons and reduction in availability as criteria. As regards the testing for leaks, it is shown that the soap-bubble test can be replaced partially by the system hydrostatic test and, that the halogen test and equivalent methods need not be applied. (author)

  2. Nuclear safety and health

    International Nuclear Information System (INIS)

    England-Joseph, J.A.

    1991-03-01

    The full extent of nonconforming parts usage in the federal government is unknown. However, large and small companies, both foreign and domestic, have sold nonconforming parts-including counterfeit and substandard items-to nuclear power plants, commercial and military aircraft, naval ships, weapons systems, and the space shuttle. Accidents resulting from the failure of nonconforming parts could be devastating, GAO testified. To eliminate this problem, GAO believes that an aggressive, government wide approach is needed, one that would ensure that federal agencies cooperate and share information about nonconforming products. This paper reports that while a centralized information system may not stop the proliferation of nonconforming products, it should help federal agencies make informed decisions about potential suppliers and products. GAO concludes that the Office of Management and Budget is in the best position to develop an effective, appropriate, and cost-beneficial plan to help resolve the problem of nonconforming parts

  3. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues

    International Nuclear Information System (INIS)

    1992-12-01

    This report is to provide a comprehensive description of the implementation and verification status of Three Mile Island (TMI) Action Plan requirements, safety issues designated as Unresolved Safety Issues (USIs), Generic Safety Issues(GSIs), and other Multiplant Actions (MPAs) that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  4. A PIP chart for nuclear plant safety

    International Nuclear Information System (INIS)

    Suzuki, Tatsujiro; Yamaoka, Taiji

    1992-01-01

    While it is known that social and political aspects of nuclear safety issues are important, little study has been done on identifying the breadth of stakeholders whose policies have important influences over nuclear plant safety in a comprehensive way. The objectives of this study are to develop a chart that visually identifies important stakeholders and their policies and illustrates these influences in a hierarchical representation so that the relationship between stakeholders and nuclear safety will be better understood. This study is based on a series of extensive interviews with major stakeholders, such as nuclear plant managers, corporate planning vice presidents, state regulators, news media, and public interest groups, and focuses on one US nuclear power plant. Based on the interview results, the authors developed a conceptual policy influence paths (PIP) chart. The PIP chart illustrates the hierarchy of influence among stakeholders. The PIP chart is also useful in identifying possible stakeholders who can be easily overlooked without the PIP chart. In addition, it shows that influence flow is circular rather than linear in one direction

  5. Safety in nuclear power plants

    International Nuclear Information System (INIS)

    Koeberlein, K.

    1987-01-01

    In nuclear power plants large amounts of radioactive fission products ensue from the fission of uranium. In order to protect the environment, the radioactive material is confined in multiple 'activity barriers' (crystal matrix of the fuel, fuel cladding, coolant boundary, safety containment, reactor building). These barriers are protected by applying a defense-in-depth concept (high quality requirements, protection systems which recognize and terminate operational incidents, safety systems to cope with accidents). In spite of a favorable safety record of German nuclear power plants it is obvious - and became most evident by the Chernobyl accident - that absolute safety is not achievable. At Chernobyl, however, design disadvantages of that reactor type (like positive reactivity feedback of coolant voiding, missing safety containment) played an important role in accident initiation and progression. Such features of the Russian 'graphite-moderated pressure tube boiling water reactor' are different from those of light water reactors operating in western countries. The essential steps of the waste management of the nuclear fuel cycle ('Entsorgung') are the interim storage, the shipment, and the reprocessing of the spent fuel and the final repository of radioactive waste. Reprocessing means the separation of fossil material (uranium, plutonium) from radioactive waste. Legal requirements for radiological protection of the environment, which are identical for nuclear power plants and reprocessing plant, are complied with by means of comprehensive filter systems. Safety problems of a reprocessing plant are eased considerably by the fact that system pressures, process temperatures and energy densities are low. In order to confine the radioactive waste from the biosphere for a very long period of time, it is to be discarded after appropriate treatment into the deep geological underground of salt domes. (orig./HP) [de

  6. 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

  7. The role of the nuclear safety regulator

    International Nuclear Information System (INIS)

    Mellado, I.

    2007-01-01

    The Consejo de Seguridad Nuclear (CSN), or Nuclear Safety Council, is the only Spanish institution qualified in nuclear safety and radiological protection. Created in 1980, the CSN is independent of the Central State Administration, and possesses its own legal standing, estate and resources acquired directly from tax revenues. The CSN proposes regulations and advises the government on subjects within its competence, including the criteria for siting nuclear facilities once the autonomous regions have been informed. The CSN is responsible for issuing mandatory and binding reports to the Ministry of Industry. Tourism and Commerce, and for inspections and evaluation of the facilities included within its realm of competence throughout their phases (construction, start-up, operating and decommissioning). It is also responsible for the radiological control and surveillance of workers, the general public and the environment, as described below. In 1999, a new responsibility was assigned to the CSN to perform studies, assessment and inspections in relation to all phases of radioactive waste and spent fuel management. The CSN reports to the Spanish Parliament and is not subject to the hierarchy or auspices of the Government or the organisations in charge of promoting nuclear energy. The Council itself is an Associative Body comprised of 5 members, appointed by Parliament for a 6 year term (these members cannot be removed). Under this Council is situated an extensive technical body. A General Secretary is seconded by Technical Directors in the area of Nuclear Safety and Radiological Protection. As well there are a R and D Office, an Inspection Office, and a Technical Standards Office. The CSN counts 446 workers, of which 191 are university graduate specialists in nuclear safety or radiological protection. The average age is 45 years. Ongoing training is provided in technical specialties and management. (author)

  8. Regulatory Regime and its influence in the nuclear safety

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1999-01-01

    A leading internationally agreed principle is that the prime responsibility for nuclear safety rests with each user of nuclear energy. A proper regulatory regime is needed to ensure that this responsibility is met. In the first place it provides a verification that all relevant safety issues are understood and taken into account in the practical measures by the users but it is equally important that the regulatory regime supports the users in their strive to achieve an adequate level of safety (author)

  9. User requirements for innovative nuclear reactors and fuel cycle technologies in the area of economics, environment, safety, waste management, proliferation resistance and cross cutting issues, and methodology for innovative technologies assessment

    International Nuclear Information System (INIS)

    Kupitz, Juergen; Depisch, Frank; Allan, Colin

    2003-01-01

    The IAEA General Conference in 2000 has invited ''all interested Member States to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology''. In response to this invitation, the IAEA initiated an ''International Project on Innovative Nuclear Reactors and Fuel Cycles'', INPRO. The overall objectives of INPRO is to help to ensure that nuclear energy is available to contribute in fulfilling in a sustainable manner energy needs in the 21st century, and to bring together all interested Member States, both technology holders and technology users, to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles that use sound and economically competitive technology. Phase-I of INPRO was initiated in May 2001. During Phase-I, work was subdivided in two sub phase: Phase 1A (finished in June 2003) and Phase 1B (started in June 2003). Phase 1A dealt with the definition of Basic Principles, User Requirements and Criteria, and the development of a methodology for the evaluation of innovative nuclear technologies. In Phase 1A, task groups for several areas were established: (a) Prospects and Potentials of Nuclear Power, (b) Economics; (c) Sustainability and Environment, (d) Safety of Nuclear Installations, (e) Waste Management, (f) Proliferation Resistance, (g) Crosscutting issues and (h) for the Methodology for Assessment. In Phase-IB evaluations of innovative nuclear energy technologies will be performed by Member States against the INPRO Basic Principles, User Requirements and Criteria. This paper summarizes the results achieved in the Phase 1A of INPRO and is a cooperative effort of the INPRO team, consisting of all INPRO cost free experts and task managers. (author)

  10. Nuclear health and safety

    International Nuclear Information System (INIS)

    1991-10-01

    On January 3, 1991, a report on the Department of Energy's (DOE) efforts to clean up the solar evaporation ponds at its Rocky Flats Plant in Colorado was issued. DOE's cleanup activities, which began in 1985, involve excavating ponds used for storing and evaporating low-level radioactive and hazardous waste and solidifying the material in a waste form known as pondcrete. This report is a follow up on DOE's solar pond cleanup activities. Specifically, this report provides updated information on the estimated costs of the project, the status of the detailed plans for conducting and monitoring the program, the status of cleanup activities, and the specific milestones the DOE has met or missed in conducting pondcrete activities

  11. Nuclear power and nuclear safety 2006; Kernekraft og nuklear sikkerhed 2006

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Oelgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2007-04-15

    The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

  12. Nuclear power and nuclear safety 2007; Kernekraft og nuklear sikkerhed 2007

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2008-05-15

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2007 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  13. International conference on strengthening of nuclear safety in Eastern Europe. Armenian Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    Nersesyan, V.

    1999-01-01

    The status of the Armenian Nuclear Regulatory Authority (ANRA) are described in detail with its main task and responsibilities concerning regulations and surveillance of nuclear and radiation safety. The following issues are presented: nuclear legislation; inspection activities; licensing of significant safety related modifications and modernization of NPPs; incidents at NPPs; personnel training; emergency planning; surveillance of nuclear materials; radioactive waste management; and plan of the ANRA perspective development

  14. Nuclear power and nuclear safety 2005; Kernekraft of nuklear sikkerhed 2005

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Oelgaard, P.L.; Kampman, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2006-03-15

    The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  15. Nuclear power and nuclear safety 2004; Kernekraft og nuklear sikkerhed 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-01

    The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  16. Nuclear power and nuclear safety 2008; Kernekraft og nuklear sikkerhed 2008

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2009-06-15

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  17. Survey on Issues related to National Nuclear Promotion Policy

    International Nuclear Information System (INIS)

    Woo, Byungchool; Lee, Youngjoon; Lee, Youngcheol; Jeong, I. K.; Kim, Hyunjun; Kim, Youngsoo; Yun, Sungwon; Moon, Keehwan; Chung, Whansam

    2013-06-01

    Ο Major issues surrounding nuclear are including suspicions about nuclear safety, spent-fuel management, acquiring the advanced R and D capabilities and making the nuclear a creative industry Ο Solid measures for securing safety should be formulated and implemented for reducing public anxiety of nuclear use Ο The long-term R and D performance system from a scientific perspective should be established for expanding Research and Development for safer use of nuclear Ο The spent-fuel management policy should be determined through publicizing process Ο Establishing small and medium enterprises-oriented supply system of reactors and SMRs and Encouraging the radiation fusion technology industrialization for promoting creative industry utilizing nuclear

  18. 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

  19. Nuclear health and safety

    International Nuclear Information System (INIS)

    1991-10-01

    This paper reports that GAO discussed the Department of Energy's (DOE) efforts to clean up the solar evaporation ponds at its Rocky Flats Plant in Colorado. DOE is trying to excavate the ponds used for storing and evaporating low-level radioactive and hazardous waste and stabilize the material by mixing it with concrete. DOE issue a press release in March 1991 stating that it has imposed strict cost control measures in managing the project. Yet DOE's most recent cost data show that total cleanup costs have soared to an estimated $169 million through completion in 2009-$50 million more than the amount GAO reported nine months ago. Delays have plagued the completion and approval of the managing plans for conducting and monitoring the program. Cleanup activities that DOE expected to resume by December 1990 have not yet begun. DOE will not meet the first major milestone of the solar ponds program-cleaning up the ponds and moving all the pondcrete off site by October 1991. Further, unless DOE provides enough project funding or resolves concerns over pondcrete disposal in Nevada, it will not finish pondcrete processing before Rocky Flats' interim status permit for pondcrete operations expires in November 1992

  20. Safety in nuclear power systems

    International Nuclear Information System (INIS)

    Myers, L.C.

    1987-05-01

    This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents that have occurred to date. Details are also provided of Ontario Hydro's problems with Unit 2 at Pickering

  1. Evaluation of the Safety Issue Concerning the Potential for Loss of Decay Heat Removal Function due to Crude Oil Spill in the Ultimate Heat Sink of Nuclear Reactors

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Roh, Kyung Wan; Yune, Young Gill; Kang, Dong Gu; Kim, Hho Jhung

    2008-01-01

    A barge crashed into a moored oil tanker at about 7:15 a.m., Dec. 12, 2007, dumping around 10,500 tons of crude oil into the sea in Korea. The incident took place about 15 kilometers northwest of Manripo beach in South Chungcheong where is Korea's west coast in the Yellow Sea. In a few days, the oil slicks spread to the northern and southern tips of the Taean Peninsula by strong winds and tides. As time went the spilled oil floating on the surface of sea water was volatilized to become tar-balls and lumps and drifted far away in the southern direction. 13 days after the incident, some of oil slicks and tar lumps were observed to flow in the service water intake at the Younggwang nuclear power plants (NPPs) operating 6 reactors, which are over 150 km away from the incident spot in the southeastern direction. According to the report by the Younggwang NPPs, a total weight 83 kg of tar lumps was removed for about 3 days. Oil spills in the sea can happen in any country or anytime due to human errors or mistakes, wars, terrors, intentional dumping of waste oils, and natural disasters like typhoon and tsunami. In fact, there have been 7 major oil spills over 10,000 tons that have occurred around the world since 1983. As such serious oil spill incidents may happen near the operating power plants using the sea water as ultimate heat sink. To ensure the safe operation of nuclear reactors it is required to evaluate the potential for loss of decay heat removal function of nuclear reactors due to the spilled oils flowing in the service water intake, from which the service water is pumped. Thus, Korea Institute of Nuclear Safety identified this problem as one of the important safety. When an incident of crude oil spill from an oil carrier occurs in the sea near the nuclear power plants, the spilled oil can be transported to the intake pit, where all service water pumps locate, by sea current and wind drift (induced) current. The essential service water pumps take the service

  2. Evaluation of the Safety Issue Concerning the Potential for Loss of Decay Heat Removal Function due to Crude Oil Spill in the Ultimate Heat Sink of Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Jong Chull; Roh, Kyung Wan; Yune, Young Gill; Kang, Dong Gu; Kim, Hho Jhung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-05-15

    A barge crashed into a moored oil tanker at about 7:15 a.m., Dec. 12, 2007, dumping around 10,500 tons of crude oil into the sea in Korea. The incident took place about 15 kilometers northwest of Manripo beach in South Chungcheong where is Korea's west coast in the Yellow Sea. In a few days, the oil slicks spread to the northern and southern tips of the Taean Peninsula by strong winds and tides. As time went the spilled oil floating on the surface of sea water was volatilized to become tar-balls and lumps and drifted far away in the southern direction. 13 days after the incident, some of oil slicks and tar lumps were observed to flow in the service water intake at the Younggwang nuclear power plants (NPPs) operating 6 reactors, which are over 150 km away from the incident spot in the southeastern direction. According to the report by the Younggwang NPPs, a total weight 83 kg of tar lumps was removed for about 3 days. Oil spills in the sea can happen in any country or anytime due to human errors or mistakes, wars, terrors, intentional dumping of waste oils, and natural disasters like typhoon and tsunami. In fact, there have been 7 major oil spills over 10,000 tons that have occurred around the world since 1983. As such serious oil spill incidents may happen near the operating power plants using the sea water as ultimate heat sink. To ensure the safe operation of nuclear reactors it is required to evaluate the potential for loss of decay heat removal function of nuclear reactors due to the spilled oils flowing in the service water intake, from which the service water is pumped. Thus, Korea Institute of Nuclear Safety identified this problem as one of the important safety. When an incident of crude oil spill from an oil carrier occurs in the sea near the nuclear power plants, the spilled oil can be transported to the intake pit, where all service water pumps locate, by sea current and wind drift (induced) current. The essential service water pumps take the

  3. Nuclear Data Newsletter. Issue No. 15

    International Nuclear Information System (INIS)

    1991-03-01

    This issue of the Nuclear Data Newsletter (March 1991) gives information on the following topics: Data indexes and bibliographies, new data libraries received, selected new publications on nuclear data, related to the activity of the Nuclear Data Section of the IAEA

  4. Proceedings of the first annual Nuclear Criticality Safety Technology Project

    International Nuclear Information System (INIS)

    Rutherford, D.A.

    1994-09-01

    This document represents the published proceedings of the first annual Nuclear Criticality Safety Technology Project (NCSTP) Workshop, which took place May 12--14, 1992, in Gaithersburg, Md. The conference consisted of four sessions, each dealing with a specific aspect of nuclear criticality safety issues. The session titles were ''Criticality Code Development, Usage, and Validation,'' ''Experimental Needs, Facilities, and Measurements,'' ''Regulation, Compliance, and Their Effects on Nuclear Criticality Technology and Safety,'' and ''The Nuclear Criticality Community Response to the USDOE Regulations and Compliance Directives.'' The conference also sponsored a Working Group session, a report of the NCSTP Working Group is also presented. Individual papers have been cataloged separately

  5. Safety principles for nuclear power plants

    International Nuclear Information System (INIS)

    Vuorinen, A.

    1993-01-01

    The role and purpose of safety principles for nuclear power plants are discussed. A brief information is presented on safety objectives as given in the INSAG documents. The possible linkage is discussed between the two mentioned elements of nuclear safety and safety culture. Safety culture is a rather new concept and there is more than one interpretation of the definition given by INSAG. The defence in depth is defined by INSAG as a fundamental principle of safety technology of nuclear power. Discussed is the overall strategy for safety measures, and features of nuclear power plants provided by the defence-in-depth concept. (Z.S.) 7 refs

  6. Consequences of electricity deregulation on nuclear safety

    International Nuclear Information System (INIS)

    Podjavorsek, M.

    2007-01-01

    The evolution of deregulation of electricity market started a couple of years ago and has not been finished yet. Deregulation causes increased pressure to reduce the costs of electricity generation. This presents a new challenge to regulatory bodies. They have to assess the impact of these changes on the safety of nuclear power plants. Accordingly, it is important to identify the risks to the nuclear power industry resulting from the deregulation. Today's trend is that the number of electricity generating power companies will be reduced in Europe and also in Slovenia due to tough competition in the electricity market. The electricity price has decreased after the introduction of the deregulated market in most countries. This has been also the main reason for less investment to new generating capacities since the price has been lower than the generation costs. Investment problems are also present for the existing units, because of danger of inappropriate maintenance and reduction of the number of staff and their qualifications below the desired level that leads to loss of institutional memory. It is expected that only the biggest companies can stand the consequences of competition in electricity prices and consequential pressure to reduce the cost. In order to review the impact of deregulation of the electricity market some relevant points are discussed in this paper such as the need to cut costs of companies by reducing the number of their activities and increasing the efficiency in the remaining activities and /or outsourcing of activities, power station operating regime, safety culture, grid reliability, reliability and safety of operation, increased number of transients, ageing of components, outage duration, extended cycle and response of nuclear regulators. From a regulatory point of view the impact of deregulation on nuclear safety is an important issue. This paper also discusses analyses and evaluations of this impact and proposes some measures how to

  7. Leadership Actions to Improve Nuclear Safety Culture

    International Nuclear Information System (INIS)

    Clewett, L.K.

    2016-01-01

    The challenge many leaders face is how to effectively implement and then utilise the results of Safety Culture surveys. Bruce Power has recently successfully implemented changes to the Safety Culture survey process including how corrective actions were identified and implemented. The actions taken in response to the latest survey have proven effective with step change performance noted. Nuclear Safety is a core value for Bruce Power. Nuclear Safety at Bruce Power is based on the following four pillars: reactor safety, industrial safety, radiological safety and environmental safety. Processes and practices are in place to achieve a healthy Nuclear Safety Culture within Bruce Power such that nuclear safety is the overriding priority. This governance is based on industry leading practices which monitor, asses and take action to drive continual improvements in the Nuclear Safety Culture within Bruce Power.

  8. The Alsos library for nuclear issues

    International Nuclear Information System (INIS)

    Settle, F.A.; Whaley, T.; Blackmer, E.

    2005-01-01

    Full text: This presentation will describe the content and features of the Alsos Digital Library for Nuclear Issues (http://alsos.wlu.edu). The library, funded by the U.S. National Science Foundation, provides a broad, balanced collection of indexed, annotated references for the study of nuclear issues ranging from nuclear reactors to Japanese poetry. All annotations have been reviewed by members of the library's prestigious National Advisory Board. The searchable collection includes books, articles, films, CD-ROMs, and websites. It currently contains approximately 1600 references and receives over 15000 visits per month. The mission of the library is to make the history and current status of nuclear issues more accessible and comprehensible to the general